IR 05000259/1987016
| ML20235F396 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/26/1987 |
| From: | Harris R, Kerch H, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20235F378 | List: |
| References | |
| 50-259-87-16, 50-260-87-16, 50-296-87-16, NUDOCS 8707130367 | |
| Download: ML20235F396 (70) | |
Text
{{#Wiki_filter:_ _ - _ _ _. , ', , . U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report Nos. 50-259/87-16 50-260/87-16 50-296/87-16 Docket Nos.
50-260 50-259 50-296 License Nos. DPR-33 DPR-68 DPR-52 Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Facility Name: Browns Ferry Nuclear Power Plant Inspection At: Decatur, Alabama Inspection Conducted: April 13-24, 1987 Inspectors: f//sh7 arry W. Kerch, Lead Reactor Engineer date -' & [l2&b7 'o ichard H. Harris, NDE Technician date Approved by: 4'/J6/#7 pckStrosnider,ChiefM&PS,DRS,EB date Inspection Summary: Inspection on April 13-24, 1987 (50-259/87-16, 50-260/87-16 and 50-296/87-16) Areas Inspected: A special announced NRC independent measurements inspection was conducted at the Browns Ferry Nuclear Power Station, by Regional NDE personnel assisted by two NRC contracted NDE personnel. The NRC Mobile Nondestructive Examination (NDE) Laboratory was utilized during the l inspection. Nondestructive examinations were performed on a sample of pipe , weldments, pipe supports, cable tray supports and miscellaneous pipe materials I which were selected from the Residual Heat Removal (RHR), Recirculation, , Reactor Core Isolation Cooling and High Pressure Coolant Injection Systems.
Results: No violations were identified.
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Tennessee Valley Authority (TVA) Brian E. Blair, Compliance Licensing Joe A. Savage, Compliance Licensing Patrick Cavier, Compliance Supervisor Robert Kosky, Division of Nuclear Engineering Vernon B. Buddle, Division of Nuclear Engineering Ben I. Koon, Division of Nuclear Engineering Gary Wade, Inservice Inspection Unit Supervisor Darrell A. Howard, Inservice Inspection Group Supervisor James E. Simmons, Inservice Inspection Lead Engineer Roger Bentley, Inservice Inspection Nondestructive Examination Mike Turnbow, Inservice Inspection Unit Supervisor Robert J. Downy Jr., Civil Engineer Huge Pomrehn, Site Directory Ed Hartwig, Project Manager John Boone, Welding Projects S. R. Henley, Welding Projects Dan Mukler, Welding Projects Caol W. Hatmaker, Assistant Project Engineer John T. Walker, Quality Engineer Supervisor Larry S. Clardy, Quality Surveillance Supervisor Robert A. Montgomery, Lead Engineer Welding Projects Anthony J. Everett, Welding Engineer Unit Suaervisor Thomas F. Newton, Lead Nuclear Engineer D. C. Mims, Supervisor Technical Supports United States Nuclear Regulatory Commission (USNRC) Jack Strosnider, Region I, Section Chief M&PS John W. York, Region II, Senior Resident Inspector Bellifonte Stew Ebneter, NRC/TVA Projects Gary Zech, NRC/TVA Projects Al Ignatonis, NRC/TVA Projects John Zwolinski, NRC/TVA Projects Gerald Gears, NRC/TVA Projects 2.0 Ind.ependent Measurement, Nondestructive Examination and Records Review of Safety Related Systems: During the period of April 13 through April 24, 1987 an onsite inspection was conducted at the Browns Ferry Nuclear Power Station utilizing the NRC Mobile Nondestructive Examination (NDE) Laboratory This inspection was conducted by region based NRC personnel in conjunction with NRC contracted Nondestructive Examination (NDE) personnel.
The purpose of this inspection was to verify the adequacy of the licensee's welding and quality control program.
This was accomplished by duplicating _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - - _ _ _ - _ -
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. examinations required of the licensee by NRC Regulations, applicable industry codes and FSAR commitments. The NRC inspector made a random selection of pipe hangers, pipe weldments, pipe systems and cable tray supports for examination.
These were intended to provide a representative sample of components, pipe sizes, materials and weldments examined in accordance with specific site requirements. Those items selected were ASME Class 1 and 2 weldments from tae Recirculation, Residual Heat Removal (RHR), Reactor core Isolation Cooling (RCIC), and High Pressure Safety
Injection (HPSI) Systems. -Also, selected for examination were structural components from the Emergency Equipment Cooling Water (EECW) and Raw Cooling Water (RCW) Systems and cable tray supports.
These corponents were examined in accordance with the Nur. lear Construction Issus s Group (NCIG-01, rev. 2) Visual Weld Acceptance Criteria (VWAC) for Structural Welding at nuclear power plants.
2.1 Nondestructive Examination: Examinations were performed using NRC procedures in conjunction with the licensee's specifications, standards, sketches and applicable drawings.
Magnetic Particle Examination: Four (4) safety related piping weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the dry. magnetic particle method technique per NRC procedure, NDE-6, rev. O.
Included in this examination were ASME Class 1 and 2, carbon steel piping weldments selected from the High Pressure Coolant Injection (HPCI) and the Reactor Core Isolation Cooling (RCIC) systems.
Results: No violations were identified.
Liquid Penetrant Examination Eighteen (18) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the visible dye penetrant technique per NRC procedure NDE-9, rev.
O.
Included in this examination were ASME Class 1, stainless steel nozzle to pipe, pipe to elbow and pipe to pipe weldments from the Recirculation System.
Results: No violations were identified.
Radiographic Examination Twelve (12) safety related pipe weldments were radiographer using an Iridium 192 source. The technique and procedures used were in accord-ance with NRC procedure NDE-5 rev. O and the licensee's procedure N-RT-1 rev. 5.
Included in this examination were ASME Class 1 and 2 carbon and stainless steel weldments, selected from the Recircula- _. _ _ _ _ _ _ _ - - _ _ _ _ - _ _ - _ _
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. tion, High Pressure Coolant Injection and Reactor Core Isolation Cooling Systems.
The resulting radiographs were evaluated per applicable code requirements and compared to the licensee's corres-ponding radiographs in order to independently verify that the correct - radiographic file film was on hand.
Results: Radiographs met code and the radiographs reviewed against file radiographs were positively identified.
Ferrite Measurements Eighteen (18) safety related pipe weldments.
Selected from the Recirculation system were examined for. delta ferrite content using a type II ferrite indicator (Severn Gauge).
This test was intended to verify that the weld filler metal composition had achieved adequate (as-deposited) delta ferrite content to eliminate hot cracking.
Results: No violations were identified.
Hardness Test: Eighteen (18) safety related pipe weldments and adjacent base material, selected from the Recirculation system were tested using the Equo-Tip hardness tester per NRC procedure NDE 12, rev. O.
This is a test, in which an object of standard mass and dimension is bounced from the surface of the work piece being tested and the height of rebound provides a measure of hardness.
Measurements taken from the impact device are processed into "L" values as a digital read out; the numbers ("L" values) are then converted to Brinell hardness values and approximate tensile strength by means of a conversion table and compared to the appropriate Certified Mill Test Reports (CMTR'S).
Results1 No violations were identified.
Visual Examination Twenty seven (27) safety related pipe weldments were examined in accordance with NRC procedures NDE-10, rev.0, Appendix A, NDE-14, rev. O and the licensee's associated drawings.
The examinations were made specifically to identify any cracks or linear indications, gouges, arc strikes with craters or corrosion which may infringe upon the pipe minimum wall thickness. Aids, such as mirrors, lights and weld gauges were used in the inspection and evaluation of the weldments.
Included in this sample were ASME Class 1 and 2 material from the Recirculation, High Pressure Coolant Injection Residual Heat Removal and Reactor Core Isolation Cooling Systems.
Results: No violations were identified.
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Ultrasonic Examination: The inspector selected two (2) safety related pipe weldments, one from the Reactor Core Isolation Cooling System and one from the Residual Heat Removal System.
The ultrasonic examinations were performed using a Sonic Mark 1 ultrasonic flaw detector and in accordance with NRC procedure NDE-1, rev. 0; Tennessee Valley Author-ity procedure N-UT-25, BF-UT-17 and associated ultrasonic data reports.
Instrument calibration (linearity) was performed using NRC procedure NDE-2, rev.0.
A distance amplitude correction curve (DAC) was constructed using the licensee's calibration blocks, BF-29C and BF-57, to ensure repeatability of ultrasonic examinations.
Instru-ment setting and search units (transducers) were matched as nearly as possible to those indicated by the licensee's ultrasonic data reports.
, Results: No violations were identified.
Visual Examinations and Review of Associated Documentation i Approximately one hundred and thirty-seven (137) hanger and support weldments were examined in accordance with Nuclear Construction Issues Group (NCIG-01), Visual Weld Acceptance Criteria (VWAC).
These examinations were performed using visual aids such as mirrors, lights, fillet and english welding gauges.
The inspection was performed to determine the general condition of the components and welds, including identification of any cracks, corrosion, loose or broken members, bent or missing parts and improper installation.
Some components were examined after protective coating had been applied.
Therefore cracks and fusion type discontinuities could not be evaluated for those weldments with protective coatings.
The following attributes apply for weldments with protective coatings: 1, Fillet and flare bevel weld size l 2.
Location
3.
Leg and throat size 4.
Length of weld 5.
Gross undercut and large porosity 6.
Overall workmanship Included in this sample were supports from the following plant systems; Emergency Equipment Cooling Water (EECW) pipe hanger, Residual Heat Removal (RHR) pipe support and cable tray supports.
Results: The specific items examined as part of this inspection are listed in attachment No. 4.
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. Four (4) record packages supplied by the licensee were compared to the results of the NRC independent re-inspection.
Include in this review and comparison were records of visual weld examinations item 8, WP-C-BFN; item 12, WP-C-BFN; item 33, WP-C-BFN and item 34, WP-C-BFN.
The inspections were performed to the licensee's (TVA) procedure N-VT-6, Rev. O. and Nuclear Construction Issues Group (NCIG-01) Visual Weld Acceptance Criteria (VWAC).
It could not be determined, in most cases if the specific criteria shown on the TVA record of visual examination had been satisfied although, TVA procedure No. N-VT-6, Rev. O, Visual Examination of Structural Welds, paragraph 4.1 states in part "The inspector shall perform the required inspection and determine acceptance or rejection separately for each acceptance criteria." The inspector was informed by the licensee that the visual examination records reviewed were not final documents, and that the final documents would include appropriate indication of acceptance or rejection.
Results: Attachment No. 2 is a tabulation and comparison of the NRC independent inspection and the licensee's (TVA) inspection. The Acceptance criteria attributes in the column for NRC will indicate acceptance or rejection, and the TVA column, based on the preliminary records described above, may or may not indicate acceptance or rejec-tion.
3.0 Observations (a) Review of ISI Inspection Data During the review of inservice inspection data the visual inspection report numbers 1015, 1016, 1021, 1022, 1031, and 1071 were examined.
The reports covered the viual inspection of the main steam isolation valves following disassembly for maintenance and repair. The reports indicated that pressure retaining bolting would be examined after reassembly and under tension for the following: cracks
wear corrosion a physical damage a erosion
TVA procedure N-VT-1 revision 8 which is written consistent with ASME Code, Section XI 1974, Editions Summer 1975 Addenda provides the inspector with a choice of performing the visual inspection when bolting is in place or when the bolting has been removed.
The inspector discussed with cognizant TVA personnel the appropriate time to perform visual bolt examinations.
TVA personnel indicated that procedure N-VT-1 would be changed to reflect that when valves are disassembled the pressure retaining bolting would be examined prior to reassembly.
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. , (b) Ultrasonic Data Review Ultrasonic data reports R0 352_R0412, RD831-R0974, R0540-50590, were reviewed.
It was determined that documentation generated by the ISI ultrasonic techr:icians at Browns Ferry Unit 2 such as weld profiles and plots of tecncician evaluations are not retained by TVA, thus verifica+, ion of Isi ultrasonic data could not be performed by the inspector. Althou;.t TVA is not required by their current code commitments to maird.ain these types of data, it does represent industry practice.
TVA has proposed and ;be NRC has accepted March 1, 1988 as a common date for all three Brovns Ferry Nuclear Plants to begin the second 10 year inspection interv I.
TVA plans on upgrading their ISI program to the 1933 Edition of the Code and Summer 1983 Addenda.
Major program and procedure changes are necessary for the next 10 year inspection interval. Tnis would be an opportune time for TVA to establish an improved 151. program.
Several discussions were held during this inspection with cognizant TVA personnel.
Below is a list of the items discussed with TVA that would represent improved practices and in some cases are required by a committment to the more recent edition of the code.
Profiles of welds should be made and retained.
- Plots of reflectors should be made and retained including root
geometry.
Plots of the code required volume examined should be retained.
- All plots of reflectors should be referenced from center
line of the weld.
Permanent marking of centerline of welds and weld
identification (required by ASME Section XI Article III-4000).
Sketch or photo of actual inspection interferences.
- 10% surveillance of personnel performance should be documented
- on examination data reports by the Level III.
10% review of examination data reports by the Level III should
be performed in order to assure compliance, i Re-examination of welds on a sampling basis by the Level III to
assure accuracy of technician reporting.
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. (c) Chemical Control A discussion was held with the Browns Ferry Chemical Technical Services Group and Inservice Inspection Group in regards to the elimination of all Magnaflux Liquid Penetrant Material from the site. Browns Ferry. Chemical Technical Service is in the process t of implementing procedures to control all chemicals used et Browns Ferry. Magnaflux liquid penetrant material is one of the chemicals recently icentified as of having a form of methyl chloroform that the site chooses to control.
The basis for this concern is chloride contamination of chloride sensitive matericls.
(Most aerosal sprays use methyl chloroform as a propellant.)
This caused a concern in that site procedures for Liquid Penetrant (N-0T-1 thru 7) permitted magnaflux penetrant material still to be used at Browns Ferry site and Magnaflux liquid penetrant materials were still available on site.
TVA ISI personnel promptly removed the magnaflux liquid penetrant materials from site and restricted, by changes to the liquid penetrant procedure N-PT-1 thru 7, the use of Magnaflux liquid penetrant materials at the Browns Ferry facility on April 23, 1987.
The apparent disconnect in implementation of the new chemical control procedures and the use of magnaflux material by the ISI group resulted because the ISI group had not been formally noti-fied of the new chemistry controls.
This appeared to be a potentially generic problem on site in that implementation of the new procedures by the chemistry group had not been communi-cated to all other groups on site. The chemistry group indi- > cated they would take actions to insure appropriate notifications are made to implement the new chemical control program.
The inspector contacted Magnaflux quality control at their main office in Chicago in regards to their Liquid Penetrant Materials.
They assured the inspector that all liquid penetrant products contain Methyl Chloroform and that it evaporates and disapates before the liquid penetrant spray reaches the material to be examined.
The inspector had no further concerns with this matter.
(d) Welding Repairs . During +'4s inspection the inspector assessed the quality of welding 2.
this facility. The inspector established that Browns Ferry Unit 2 has not implemented specific management controls to preclude multiple repairs to stainless steel welds.
It was also difficult to establish weld quality at this facility by using the conventional method of reading radiographic film and counting the number of code required "R"'s for repairs. An i example is safe end weld 2RB6 R12. The "R12" would normally indicate there were 12 code repairs made to this weld; thus, indicating a welding problem.
Further investigation .. _ _ _ _ _ _ _ _ _ _ _ _ _ _ <
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. revealed that this was not the case. The "R12" actually indicates there were 11 in process radiographs plus one for the code weld repair.
The normal practice would ha/c documented this as 2RB6 RI.
The foregoing are observations and not regulatory requirements; the inspector had no further questions regarding these matters.
(e) Welding of Unistrut Material During the course of this inspection the inspector reviewed the ongoing welding at the fabrication shop for conduit supports. A detailed review of conduit support number 3000-87 referenced on drawing 48B810-2 R1 was performed. Welding was accomplished on unistrut material P-1000(A570) using TVA welding procedure SM-P-1.
Qualification for Flare Bevel and V welds for unistrut P-1000 material were referenced in TVA memorandums B46-86 1030-001 and B45-840312-251.
No discrepancies were found.
(f) Ultrasonic Thickness Measurements of Feedwater/ Condensate Piping for Wall Degradation TVA has performed thickness measurements on 32 carbon steel pipes and fittings in selected areas based on the following parameters.
- Areas of Singe Phase flow
- Temperature 250 F to 400 F
- Flow Velocity 5 to 12 f t/sec
- Flow Path Geometry (Keller's Geometry Factors)
A final report by TVA has not been issued, however preliminary data , have not identified any pipe wall erosion problems at Browns Ferry Unit 2.
(g) Ultrasonic Thickness Measurements of the Drywell Wall The licensee has not started the thickness measurements of the Dry-well wall in response to the NRC Information Notice 86-99 and General Electric Company Rapid Information Communication Service Information Letter (RICSIL) No. 09.
These documents alerted utilities of pos-sible corrosion of the drywell wall based on experience at the Oyster Creek Nuclear Power Plant.
The licensee has stated that drywell wall thickness measurements will be performed but were not the first priority considering TVA's overall workload and the schedule for restart of Browns Ferry Unit 2.
The inspector pointed out that if there is a problem regarding wall thinning of the Drywell, it is preferable to detect it early since it could take some time to resolve.
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. 4.0 Review of Procedures The procedures listed below were reviewed to verify their technical adequacy and conformance to regulatory and code requirements.
- N-RT-1 Rev 5 Radiography
- N-PT-1 Rev 6 Liquid Penetrant
- N-VT-1 Rev 8 PSI /ISI Visual
- N-PT-1 Rev 6 Liquid Penetrant
- N-VT-3 Rev 7 Visual of welding and dimensional
- BF-UT-17 Rev 5 Ultrasonic of piping
- See Section 3C on Chemical Control
- See Section 3 on review of ISI inspection data No violations were identified.
5.0 Review of Material Certification During this inspection, activities involved with the replacement of recirculation piping on Unit 2 were examined.
The inspectors reviewed the following material certifications for compliance with the applicable ASME Code for chemical composition, material properties and traceability.
Austenitic Stainless Steel Piping Fittings ASME SA 403, GR.316 NG Heat No. TTD9441-1
Heat No. TTD9439-1
Heat No. TTD9443-2
Heat No. TTD9440-1 + Heat No. TTD9442-1
Heat No. TTD9458-1
Heat No. TTD9456-1
Heat No. TTD9460-1
Heat No. TTD9457-1 - Heat No. TTD9459-1
Austenitic Stainless Steel Forgings, ASME SA182, GR.F316 NG Heat No. 131BN
Austenitic Stainless Steel Weld Material Weld Wire, Heat No. S8E0591, ASME SFA5.9, 308L
Weld Inserts, Heat No. 5493T308L, ASME SFA530, 308L
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- N-VT-6 Rev 0 Visual NCIG-01
- N-MT-1 Rev 5 Magnetic particle G-28 Rev 8 Construction of Piping
- See section 2 and attachment 4 No violations were identified.
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. 6.0 Personnel Qualification The inspector reviewed the qualification and certification records for the following ISI personnel
- Ten TVA personnel
- One Stone and Webster employee
- Four Bechtel personnel No discrepancies were found.
7.0 Attachments Attachment No. 1 is a tabulation of spec 1*ic piping weldments inspected and the inspection results.
Attachment No. 2 is a list of specific structural items re-inspected and compared <ith the licensee's inspection results. Attachment No. 3 is a specific list of the licensee's file Radiographs and those that were compared with NRC re-radiographs.
Attachment No. 4 is the tabulation and results of specific structural items examined.
8.0 Exit On April 23, 1987, the NDE Van personnel had an exit meeting with the licensee's staff.
The findings of this inspection were described at that meeting.
No written material was provided to the licensee during this inspection.
ATTACHMENTS: As stated above.
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_ ___ -_ ___ _ _.
.-__ ' , . , WR-C-BEN:34- ' - ' BFNP MMI 168 Revision 0 O__._ E- . -- ATTACHMENT A Marked Drawings / Sketches with completed data sheets.
, . . A2 ah- - T /@ Ql --3.,_,4 RUBE STEEL ,7 i BASE 12 / m / A l l ~ v < v
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_____ ___-_ -___ - __ ______--____-_ _ - _ _ - ,, ,. ., , t . , . W9-C BEN-3.+ . BFNP' MMI 168 Revision 0 ERYU -- ' ATTACHMENT A_ Harked Drawings / Sketches.with completed data sheets.
. . > rf : I 73"4 TUBE STEEL BI , , SI-No WELD - O" ' ' ^ LI-FLARE BEtML VlN$ FILLET REINF-2 L2 b"FILLEY-I" L f.
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SECT 8-6 Ml-FLARE BEVEL Vl$UNDERFILL ~=N" . M e w/fi' g fg 'Y ZOIAL tJGLD - O 2" Li 'W _ -A/ T~ d I I ' A ! i , ,
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[' '; BENP - - MMI 168 Revision 0 ATTACHMENT A - - --- Marked Drawings / Sketches with completed data sheets.
. J . , g3."& TUBE STEEL -
CI , , C 1 - No wEto - O " L Nl-FLARK BEVEL Wh$'UNDERFILL--2 ~ ' N2 '4$'rILLET-2 'k L f \\ PI - No WELD - O" L IN ' N) TOTAL k/ ELD - 4 %" SECT C -C , , l . NI l I ' _g p ' l A ' ' r
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_ ___ ___ _ _ _ _ _ - _ - _ _ _ . ' . . . , , i WP - C - BF1L-3+ - BFNP MMI 168 Revision 0 PBGE l+
_ _. _ ATTACHMENT A Marked Drawings / Sketches with cornpleted data sheets.
f . g.374 TUBE STEEL a Ol-A/o WELD - O" L 01-FLARE BEvGt_ w/ ISUNDERFILL-2S D ' _QB Y "- FILLET E N " L S z \\ RI-NO WEL D - O "I_ IO Q} TOTAL \\r/ ELD - 5" i SECT D -D . . i ' . Ql ! ' 'Y I I _ .g _R - , I i ! /. ', I I , g i .; , e , I l l l' ll l - - i i i s , II , I i il 'l i.
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. W52 - C2BF_N-3_4 - - BFNP~ MMI 168 Revision 0 U - 15 Ef t o_._ _ ATTACHMENT A Marked Drawings / Sketches with completed data sheets.
, ! i ,, ,.I 7 3_"4 TU8E STEEL EI E.L-NO %ff.La 0" __ \\ \\ " ' SI-VLARE BEVEL W/15UNDERWILL-2h" S2-Wi'RLLCT - h"L.
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. . . WP - C-BEN-3.k ' . BFNP MMI 168 Revision 0 P6GE lG f 20 ATTACHMENT A , Marked Drawings / Sketches with completed data sheets.
. ' . I g.3_"@ TUBE STEEL FI
Fl-NO WELD - O" V.L-Elb8E EEV.ELW$0NDERELL8 ' ~' ' U.1 Y FlLLET- / b" L
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, ! . - WP -C - BEN-39 BFNP MMI 168 Revision 0 ' ATTACHMENT A AN l O- - --
Marked Drawings / Sketches with completed data sheets.
- .
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7 3.'.'4 TUBE STEEL GI ' GI-NO WELO __O " ' - - 2 - --._ b Wl-FLARE _BCVEL WlhYUNDERElL8 V2-%[MLLE2 4"I,. ! \\ XL-blQ.WCLD - Q" ' lW Wl IQTAG.MGLO = 4 V "
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.
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HI H l-NO WEl f3 - O" Yl-FLARE BEVEL to/h{UNDERMLL-25 h - $ -._
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, -Ab , " ' ... - l// // // / //s \\/ / //\\ C0 i/ t/ s Ai L - $b,h 8 s 4 4'N3~X1[kO'.3."
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BFNP MMI 168 Revision 0 20 G E. 2 0 -." 7._o C ATTACHMENT A Marked Drawings / Sketches with completed data sheets.
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_ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _._ /jrracHMENT Na'. 3 LIST OF LtWNCff RActoGtAPMS #f*'!Wfe . , $RA010Gn'APMS COMMt0 TD INCO*t'WOM NMC WA0'W9'f"3 SYSTEM /uME WR0 L D.
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, . AtteHeilr % - VISUM. EXAMINATION RECORD FOR NCIG.01 WELDSPage _/ of d Site 3 4o4N5 fc#4v MA47 2 Reference coqueent: NCIG-01(VWAC) Examination Package No': ' Iffy p) Inspect 10n No. 97-go -O Y Component identifIcat1on No: tVrh8 -8FA]- B D a t e <,/.16 -97 l'.fi. Q u). HFI Md;6M 5 Accept / Reject Weld No.
Weld No. Weld NO.
We!O NO.
Weia No.
Acc ept ance go,g p g,g7 gg, y r g,yy g,g At t ribut e Criteria fft- /17 AB - MI.8 41V-A/J n/1-Msg nu-M22 Nects 1.2.2.1 uM ^)/n ^)/k Al/ n Al/&
e
1 + Weld Size 1.2.2.2 /dd /ld e Aad.
Ac d.
4ae Inconplete Fusion 1.2.2.3 & M/A 4//A ' M/4 d/4-- N//l over1 so 1.2.2.4 Add Ad-L AG.6 A 6 d-noe Uncerfillec Cr aters 1.2.2.5 Ad.g
- dd Ad (P Ad.c.
t4d e weto Prefiles 1.2.2.6 Aad Add /M /' (Me Ad G Uncert t 1.2.2.7 Add Add _}gf g ar adg Forcstty _ 1.?.?.S Ad6 Add _5
7 Add _ _ _ V1Ge AG.C.
W
held Lengt's l ano t catson 1.2.2.9 a sed e Add Alte 40.6 pdc Arc Strikes 1.2.2.10 Add'. Add i A46 Aet Adf.
Surf ace Slag and kela Spatter 1.2.2.l1 Add 14dd-19d G /te L f160.
Relevant Oats Mtssing kelas See AltaCh. /V/' / /)//} A))/) j]/}{ Alfa n ifu i See htLOCY Nf/0 / fll AI/A Alf/] U ' , Inaccessible See At tach. 4//// // d M/M A//d Al/( weld Type See Attach.YM NDE Reauirea Yes No V .- Technician (s) (jo W W QA V ID ro SM Refer to indicated paragraph (s) of Nu le Visual Weld Acceptance Criteria fy'k) Construction I5 sues Group (NCIG-01) -l Reviewed and Approved by: ] ~ k o & a r%t ' , Datt .. _ -
- - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ .'. , , . . VISUAL EXAMINATION RECORD FOR NCIG-01 WELOS Page Lof Q Site 9/004)H bcArt y dmTE neference Ooqueent: NCIG-01 (VWAC) Examination Package Noi 'II.tet & Inspection No. 6 7- /4, -/3 5/ Component identification No: tA)P-o O ff J B Date d/.- 2 9 ~g r t FE. c, wi. W ANGEALS Accept / Reject . Weld No.
Weld No.
Weld No. Wela No, weia No, Acc ept anc e b o u T' v o n o u-t-ye s e r vos a u r--- rn t w At t ribut e Criterta A 2 3 sq,t.s* pgt,-g2r pp9-R3l Ag2 -nys/ gzg:ppy ) Cracks 1.2.2.1 AI/k J)/ W U/$ U/8- /J/R Weld $1re 1.2.2.2 A d d.
/7dd- //6 d- /)dd Ad.C Inco,1ete Fusion 1.2.2.3 ///B A//4 AJ/4-A//#- A//8 Overl ap ' 1.2.2.4 Ad C.
Add Ad6 44 c.
- 9dd Uncerfilleo Craters 1.2.2.5 A d d-
- dd.
/;fd/3 Mid /M O _ ' We1e Profiles 1.2.2.6 86 d d[(I //80 MPfE Me Unce rc ut 1.2.2.1 A d G.
4(i fi Add A de rt.& c Add
- dd Add Forosity 1.?.2.8 ed C
//d/1 _ weld Lengin ano L ocat ton 1 ?.2.9 8dC ' JJ e tt A C 0, /}{0e yg Arc strikes i.2.2.10 dac ned i A d-('- /7ed A&a Surf ace Slag anc welo spatter 1.2.2.11 868
- Gd AdC.-
Add-W d.d ) Relev ant Dat.i l i . Missing Welos See Attach y//) l M/A.
A//j4 rJ/A- >J//) . '
r i (~ Missing Welds Due to Congifurat ion See Attach jg//] gjjj n)/ja jg//4 dA . Inaccesstele see Attact. M,/A //) ,/A ,/A MA - < . Weld Tyve See At tBCh Nl}f' h)l} dl}Y' h)llh J]l}Y~ - NDE Requiree Yes No __ Technician (s)hoyoffy [,-fgg,g hp/g/; p kt spfg Refer to inoicateo paragrapn(s) of Nu lecr Visual Weld Acceptance Criteria fvWsC) Construction issues Group (NCIG-01) - Reviewed and Approved by Iw d %1 6.27.-f / j Date I ' , _ _ _ _ - _ _ _ _ _ - - - - - - - - - - - -
- - - _ - _ _ - __--__ - -_ - -- - --
. , * *. . l "
. l
Vl$Udt. EXAMINATION RECORD FOR NCIG.01 WELOS Page d of J Site 3RadNs Nav Nu/Tf-Reference ooqueent: NCIG-01 (VWAC) l Examination Package No: ' 2 T f/V1 8 Inspect 10n No.8]- /6-d Y Component ident ifIcation No: W P- ('- 8F ed -6 Date A23_gy l I?.C.C.VJ HAdGERS Acc ept /Rejec t . Weld No.
Weld No. Weld No.
Wela No, weia no, l Accept once pgwr i Attribute Criteria A38 - p yf
.. Cracks I.2.2.1 N/A Weld Site 1.2.2.2 A06 Inconplete Fusion 1.2.2.3 M/h Overl ap 1.2.2.4 /k38 '- Oncerfi11ec Craters 1.2.2.5 Ac.c ! Weld Profiles 1.2.2.6 Ad c, Uncercut 1.2.2.7 /he Porosity 1.2.2.8 460-l ~ held Length and L oc at ion 1.2.2.9 Adp Arc Strikes 1.2.2.10 Add, i Surf ace Slag and Weld Spatter 1.2.2.II Rd.d.
) Relevant Data Missing beids See Attach. MJ l l % Missing welds Due i to Congifuratton See Attact. A/fA Inaccessible see Attact.)
t ~ \\ - wela Tge see Attact p/// , ! l NCE Required Y es No ._ Technician (s) h-fergs [gif,p ksgn g Refer to inoicateo paragrapn(s) of.Nu lear Visual Weld Acceptance Criteria fVyC) Construction Issues Group (NCIG-01) - !-#7-87 Reviewed and Approved try
y -/ ~/ /' Datt ' , __..m . _ _ _ _ _ _ _ _ _. - _ _ _ _ _ _ _ _ _ _ _ _. _ _. _ _ _ _ _ - _ M
_________ _ - - _ _ _
, kfb@0N91E* >T ~ ' A VISUIL EXAMIMTION RECORD FOR NCIG-01 WELDS Page 2 of J ' Site 8 ew.o M y (/w//-8 Reference D umerit: NCIG-01(VWAC) Examination Package No* 'farrM / 2.
Inspec On No. 87~ //, -d.$ , Component Identification No: W P-C-B FN.-/Z D ate _ </- 2 3 -6 7 flek) He bh) Supped $ - Accept / Reject . Weld No.
Weld No. Weld No. We la rio.
Weia No.
Accept anc e Attribute Criteria 6I"# 7
DI 2' D3 (:: 1, 2,
/ f? sar P an M T' Yh s Nr pan ur ensnr ~. Cracks 1.2.2.1 N/A d/ A' 8J/A
- J/A O//L Weld Sire 1.2.2.2 Ag e.
'Rs J Qao M J.
M< b I incomplete Fusion 1.2.2.3 M M M N / / '/ { ' Overlao 1.2.2.4 Ad 8 Add he d_ /966 Ad6 Underfilled Craters 1.2.2.5 AMO-Ado 40 6.
Add vi df_, Wela Profiles 1.2.2.6 A dd_ Adn AOLL A gd gg Undertut 1.2.2.7 MdC rid n.
4ap,
- d/,
M f Porosity 1.2.2.8 A dC, 13d c nee A dt, r$d l.
t Weld tength and l oc at ion 1.2.2.9 Ad,d.
A 60_ i AA/8 jf/t d Add Arc Strikes 1.2.2.10 Ad(L, Ag a.
i fh/g //dd, vidg Surf ace Slag and Weld Spatter 1. 2. 2. 11 Ad/1 AdA I4 d.d./ /M #, //d6 Relevant Data Missing Welds SeeAttach . M/A /J/jt a)//) A/j/J ///j) - t Missing Welds Due to Congifuration SeehttaCY l'lA-bl/A N/A Al/A +)/>t . 0S l /b/A v/A I/A M.
inaccessible Soedeamd I s i Weld Type See Attact M/pP j)/-g s/A DB, Fl . NDE Required Y e', _ No \\ l / Technician (s) de,w y 3, rec Wp Z 5 en f Refer to indicated paragrapn(s) of Nu lear Visual Weld Acceptance Criteria fVWAC) Construction Issues Group (NCIG-01)
- Reviewed and Approved by: t/-27-[[ D / ' ' ' ' Date . .- l " a -- . -----. ._ -. --
_ _ __ _ _ _ _ _ - _ _ _ _ _ - - _ _ - _ _ _ _ _ _ - - __-_____ _____ - _ _ . . 1.
.. . . . . . VISUA'L EXAMINATION RECORD FOR NCIG-01 WELDS Page f. of j Site / Iowa M er //w//"8 Reference 0 userit: NC1G-01 (VWAC) s Examination Package Noi ff2! Cop /'#, Inspec 10n No. 8 7- /4 - dj Component Identification No: wf F-d -13 F A/ /g Date Y-23-F7 .. . Accept / Reject . Weld No.
Weld No. Weld No. Wela NO.
Wela No , Acc eptance Attribute Criteria Mp}"5 M* / ~ 8 d3, /- b~ d'/]-b~ k* [ - 6 ~. . PnmT Pa eaY TAiMT' PAhnt r~ 19 uar Cracks 1.2.2.1 t4/A M/n N/A rJ/A rJ/A Weld Size 1.2.2.2 A dc.
Art /7, /2d.d, /7ce (led, . M,A M N, ,MI Inconplete Fusion 1.2.2.3 A.
,,. ,- Overlap 1.2.2.4 46.0.. Ac p Ad@ ado. /$ d,e Underfilled Craters 1.2.2.5 Aa1 Ae6 Add Ate, A G d.
Weld Profiles 1.2.2.6 Ad a. leda N-Gd 4ed d undercut 1.2.2.7 A ge., h66 A d t, Ado /lde Porosity 1.2.2.8 AaA.
4eg ada 4d d., Me Weld Length and t oc at ion 1.2.2.9 Ag.
n d.c, /}dt A-Ce Add . Arc Strikes 1.2.2.10 A00.
Ac c l
- d.1 m(L.
Ace Surf ace Slag and Weld SDatter I. 2. 2. 11 Add.
40.c-MU-kG O.- Add Relevant Data Missing Welds See Attach v/A ,.1/A Al/A / /A //-S d . Missing Welds Due to Congifuration See Attach. p/ g N/f; /s/4 g/,g N/g
inaccessible See Attact A>/A 8/A N/A /g // . t A//A J3 f Jb[ M/f/ Weld Type M1 /A . ( NCE Required Yes No [ . Technician (s) doWxv, karAs DA t/in bs AA , Refer to indicated paragrapn(s) of. Nuclear) Construction Issues Group (NCIG-01) Visual Weld Acceptance Criteria (VWAC .- Reviewed and Approved by ' I " -I f/-//- [[ - ~( j/ Date ' ' ~ . .- , -- ____ ?? .. -,m 4.-,,.,..,-..,.m,- . __m ..m- - __ _ m ____ _ z_ _ _
1 l J p., .
. . p vl504L EXAMIETION RECORD FOR NCIG-01 WELOS Page 1 of g Site JIAetvAls M,Mu Owg8 Reference Ooqueent: NCIG-01(VWAC) Examination Pack age No: ftFJvt f '2.
Inspection No. 8 7-//u- 03 * Component ident ification No: h)p-c-e FiV-/Z.
Date </ - 2 9 - 17 - < Accept / Reject . Weld No.
Weld No. Weld No. Wela No.
Weia 110, '. Acc ept anc e Attribute Criteria // -l(f K7-[f/ U-LZ l Pnitar ratNT F'H e N T Cracks 1.2.2.1 r4/4 til/A N/A Weld Size 1.2.2.2 A6C AeA Airl inconclete Fusion 1.2.2.3 M4 k h.
Overlap 1.2.2.4 Fr 0 0.
,4d6 Add Underfilled Craters 1.2.2.5 b6 C, M.E.
Ade Weld Profiles 1.2.2.6 6d.(L.
4d.0 Ac i Underrut 1.2.2.7 M t.
Ac c.__ Jet Poros1ty 1.2.2.8 (Vic.
Ibd.a At6 Weld Length ano tocation 1.2.2.9 i S d.L-Acc, Mg l Arc Strikes 1.2.2.10 ()&_o_ gg l ,1 Q l Surface Slag and i Welo Spatter 1.2.2.11 Md6 $d//- W66 Relevant 0.1t4 ) Missing helds 5- ^^h. k('[p [lf dp ' Missing helds Due to Congsfuration See AttacF v/A g/A g/j . i; t Inaccessible See Attach . AI}A rJ/A 11/A Weld ivpe See Attact /A A) /g . g[ 40E Reauireo Yes No ._ Tec hn i ci an ( s ),),,y,ygt v q zgx'3 hyto SKA / Refer to indicated paragrapn(s) of Nuclear Visual Weld Acceptance Criteria (VWAC)C0hStruction issues Group (NCIG-01) , - Reviewed and Approved by: / J/ [ </-f f-8 7 m/ ; W__ ) { Datt
' . .- _ - _ - _ _ - _ - - -
- _ _ _ _ _ _ _ _ -.-. hf/////&GR)f h . . VISUA't. EX/MIMTION RECORD FOR NCIG-01 WEL.D5 Page ] of j Site [pe dery (dI/~8 Reference Document: NCIG-01 (VWAC) Examination Package N6:.CTrry/ $__ Inspection No. 9 7-g,- d2 Component Identificat ton No: W P-c - C FAJ - 38 Date V.2 3-s 7 CA6<.17KA4 SUP/btr -. Acc ept /Rejec t Weld No.
Weld No. Weld No. Wela No, weia rio.
Acceptance Attribute Criterta Al-AV 4/- 4 2 d/-of. D/ - P2 E /- E 2- ' .. Crac k s 1.2.2.1 ABC, AG.c.
A CC, AdC (4d.d. < Weld Size 1.2.2.2 f(d. flgd.8) AOL Add,. Age . Incorrplete Fusion 1.2.2.3 lPe.J. A r,. Ato A ce., A ce, ago I Overlap 1.2.2.4 400.
Add.
ACE Ad.C AO R Underfilled Craters 1.2.2.5 Add * Ad.d.
(3GO, Ad.d AdG Weld Profiles 1.2.2.6 ffd.
Add.
A 0.c /4c(P Agg uncercut 1.2.2.7 %J 42 A3 4 d.c. Add.
Aap joa > Forosity 1.2.2.8 6cc. Aad.
400 Ado, Ac.g.
held Length and Locat icn 1.2.2.9 Ad.c. Aac., i Ad.c.
4 d.0 s40 e.
Arc Strikes-1.2.2.10 A m, * Acc, Act A d.d, Ad0
Surf ace Slag and i wela Spatter 1. 2.2.11 4 d.c.
Acc AO.a - A C-d-4d# Relevant Data Missing Welds see-Attach p//4 A//A /J//)- ///# A/// ) . Ni u ti n see Attact o/A - M/g
M/p g '
. inaccessible See AttacF ra/A M/d' // M/B M/A . See Attact c//l N/# k////- M/[ Af/4 h Weld Type
, ' [t {. ( \\ / -. < NDE Required Yes No ,i' ]N . Technician (s) M uy h e c Mn e, h e.,gA ' l Refer to indicated paragraph (s) of NufVWAC) Construction Issues Group (NCIG-01) lear , i Visual Weld Acceptance Crit.eria , - , Reviewed and Approved by: ( . w "/ '~ V*,2/-[[ ' Date - . + em .
. _nc <+ fywr q-t > 1.m n-me M- . et'n er s _
. . @ . , , .- . e--:. -~ -., - - -
,,. m,m ,..,,,.,., -
. . , wrd6wur% i . " . f ' e} - , , ,3 . -
VISUAL EXAMINATION'RfCORD FOR NCIG-01 WELOS Page 1 of 3 [{ Site [ cma S h Mw//- d " Reference Document: NCIG-01(VWAC)
- Examination Package Noi TN/H 36/
Inspection No. 8 7-/d2-O/ ~ Component Identification Wo: W F-d - G P'AJ - B Y Date _V-23 - A 7 Cast.t +6V sorpetT*
.f Accept / Reject-d . . Weld No.
Weld No. Weld No. Wel0 NO.
Wela No ( . Acceptance i" ' Att ribute ' Criteria 4/- A[ 4/- 4 4' $/ ~8/2-A// " A/2 Q / -(2 N ' l ... racks 1.2.2.1 &?d, /t d.c.
Aac.
Acn Ae1
- (
' g
Weld $'I2e-1.2.2.2 b N-b N~I-M NI b3 NI ID h 9
Incow lete Fusion 1.2.2.3 Adc.. A&. Acc AC'c /bc.
$ l Overl ao 1.2.2.4 Ac.c.
/}dd &c.c Acc.
/uc -- , underfilled Craters 1.2.2.5 Ac o.
Aec A t e_ Ac.c Aca.
'* Weld Profiles 1.2.2.6 A d d.
Ace n e o.
Adb Aac.
. Undercut 1.2.2.7 4 c.c. Ad-c Atc 6 04.- doc-I Porosity 1.2.2.8 4 d.0. AM A ce.
6 d.a.
Ad.c ( A Weld Length' b and L ocat ion 1.2'2,9 Af6 Add -
- Ad.C.
A d.d-Ad.C . Arc Strikes 1.2.2.10 Aid.." A 60, de e-Adr.
Ac.c_ , .,, Surface Slag and ? Weld Spatter 1.2.2.11 AC.d.. M-c.
6 00 (MG.
Aac-- ' '?
- %
I elevant Data R Missing Welds See O ch.SY - 9/A As/4-g/4 gJ/4 .h . i , , x Missing-Welds Due J to congifuration - see Attact.h W/A M/A L)/4 N/A , . hl ., , inaccessible See Attact. M/A xdll d/A . A/A- /J,/A .{ I Weld Type i See Attact. N//P g/A d//p 0/A " ' 4DE Require Yes No [ ' q w y Technician (s) Jos~~~ 64u.. T me Ess~ d ' ' WN) Construction Issues Group (NCIG-01) % Refe'r to indicated paragrapn ) of 'u e . Visual Weld Acceptance C teri . W - h / Reviewed and Approved byb - W-2 F f f Date , -
+;'. t. -e 'pgw* asmw+ ,, (Tigr.9 4, ggj y w 4.;,,..,g m, f,
, _ _ _ _ _ _ l . .. . .
i ~ ^ k . ! . VISU L EXAMINATION RECORO FOR NCIG-01 WELDS Page f of } Site 8 ow,v M ev (.d/b8 NCIG-01(VWAC) Reference 01userit: Examination Package Moi rrtM 3*/ Inspect 0n No. g,7- //, - 6/ Cceponent Identification No: u]P C - BF N -M Date e/.23 - 8 ~7 , '
Accept / Reject - a . Weld No.
Weld f40. ' Weld tio, Wela No.
Weia No
. Acc ept ance "I Attribute Criteria SI - 3 2 U)-02 03 W I-h/ 2 Yl-Y2 [j Eracks i.2.2.1 aed.
nea.
400.
A.
e.
Weld Site 1.2.2.2 (J s i ReJ. R'tz,1 <?s/ WI Ado,
. Incomplete Fusion 1.2.2.3 Add, Add, //dd, j;@c.
//dd.
Over1 ao 1.2.2.4 Add.
,fg e, 7)gc gg,1, pgg, N Underfilled Craters 1.2.2.5 Add, //dd, MdC.
A10, //M.
, Weld Profiles 1.2.2.6 /7d. C-AdC . y? Uncertut 1.2.2.7 Add, Arc, dat2.
Add.
- !t? >
Forosity 1.2.2.8 Add, sydd, $ddo /;tte,. Abt2.
RG3 Weld Length and L oc at ion 1.2.2.9 51 - 5 2.
Scf.
- E./ *
/ld.e, Aa.
, Arc Strikes 1.2.2.10 %. /kfc.
Add.
//dd.
ddd - Surf ace Slag and Weld Spatter 1. 2.2. 11 Add' //dd.
Add, Ad 8' Add.
Relevant Data Missing Welds See-Attach O/A /J//) t,/a n/a
- g
. - e c Missing Welds Due to Congifuration See Attach p/ A gy n.
h/A g/3 ,gg ,, . , Inaccessible See Attach. M/4 //) d/A M/i A//// l ,, Weld Type '. See Attach OfA ^> >h rs/r is,'/v ru //+ - .. i > \\ '( , ., 1DE Required .' Yes No ' d . Technician (s)t)oyanu&.jp,t Qpu,p ({, gg . -l / a Refer to indicated parasrapn(s) of.NufVWk) Construction Issues Group (NCIG-01) " le Visual Weld Acceptance Criteria - s nevie.,co and Approved by: (d/O ddC v-27-rf "/ ' Date . ,t q , /4 l L---- m _ -- - - - - . w%-- e.c m - . _ _ - -
____ - _ _ _ - _ _ - _ _ _. .
. , . , . . . . VISuit EXAMIMTION RECORD FOR NCIG-01 WELDS Page 1 of 1 Site /8cnw M<v /.d/b8 Reference Documerit: NCIG-01(VWAC) Examination Package Noi 7.TFM c3M Inspect 10n No. 97-/4,- v/ ,; Component Identification Ho: wp -c - SFN -3 9/ Date 4/-23 -B7 H S /h a 5 # CA6uf WW .. j ' Accept / Reject . . Weld No.I Weld No. Weld No. Wela No.
Wela no
_ , Acceptance . l At t ribut e Criteria 4/-/-A/*2 [/ 8-[/-fM/-[M A/-/-[[2 8*/ '] racks 1.2.2.1
- dd 4dd,
' Add.
IR
- dC.
Meld Site 1.2.2.2 Add.
A66 A66 AG I *b2'S k*b Inconglete Fusion 1.2.2.3 /;fd8 Add, Add 84CE-
- dd.
Over1ap 1.2.2.4 Add Add.
sko.
40 E Ate Underfilled Craters 1.2.2.5 Add 466 ed.
Red AOL.
l Weld Profiles 1.2.2.6 4 e d.
A dc, gdC 4pg_ pec , Unce rc u t 1.2.2.7 dd6 gu Mof.
r1dc MA.
Porosity 1.2.2.8 Add jp/n jfdd AdA wee.
Weld Length and L oc at ion 1.2.2.9 46a sf46
- At d-Ad-d, Ad.d_
Arc Strikes 1.2.2.10 p2 d d, 4dd - l Add, M,0 - 4td, Surface Slag and
.- l Weld Seatter 1.2.2.11 Add.
- d/,
466, Aep., AW ' l Relevant Data Missing We1ds See Attach /d//7 /Y//l /v//1 AJ//F (/A . Missing Welds Due / to Congifuration See Attach. N/ g 9/4 j//A Affk [A l , . Inacces;;ble See Attact N/A $//// 24, /A2 A . See Attach. pgl}} );//) /Q-AY} lh Weld Type s , - , Yes No [ f 40E Required ' Technician (s)du f,p_ts. 9ny,o fis gn , Refer to indicated paragrapn(s) of NufVWAC) Construction Issues Group (NCIG-01)
lear Visual Weld Acceptance Crimia y Reviewed and Approved by: . /-/j-[[ - / bate ' . .- P d __.-___$______ _ _ _ _ _ _ - - _ '~ }}