IR 05000317/1990001
| ML20042E371 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 03/16/1990 |
| From: | Harris R, Diane Jackson, Kerch H, Oliveri M, Strosnider J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20042E364 | List: |
| References | |
| 50-317-90-01, 50-317-90-1, 50-318-90-01, 50-318-90-1, NUDOCS 9004200688 | |
| Preceding documents: |
|
| Download: ML20042E371 (19) | |
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1 ' , . . .. U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Report Nos.
50-317/90-01 50-318/90-01 Decket Nos.
50-317 50-318-I License-Nos. DPR-53 DPR-69 Licensee: Baltimore Gus and Electric Company ! MD-Rts 2 & 4 P.O. Box 1535 Lusby, Maryland 20657 Facility Name: Calvert Cliffs Units 1 and 2 Inspection At: Lusby, Maryland j Inspection Conducted: January 8-19, 1990 l Inspectors: 3 //6 /96
L yMaterials & processes Section, EB, DRS W. Kerch, Senior Reactor Engineer, date ' T' 3 //s/90 fr f. H. Harris, NDE Technician, Materials & date ! Processes Section, EB, DRS /m2/ $ / 3//b /96 D. A. Jackson, NRR) Intern ' date &hsh 3l/b/99 ' ff. A. Oliveri, NDE Technician, Materials & date Processes Sec ion,'EB, DRS Approved by: J//4/9e - .J' R. Strosnider, Chief, Materials-and date ' l Processes Section,'EB, DRS, Region I l l ! ' i, " fi '
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I .. Inspection Summary: Routine Announced Inspection Conducted on January 8-19, 1990~ ' (Report Nos. 50-317/90-01 and 50-318/90-01) Areas Inspected: A routine, announced inspection was conducted at Calvert Cliffs
Nuclear Power Station using the NRC Mobile Non-destructive Examination (NDE) ' Laboratory.
The inspection focused on activities related to the inservice inspection, erosien-corrosion, and modification programs. Three vielations and an unresolved item, as listed below, were identified during this inspection.
Violation 90-01-01 Failure to follow procedures (See Section 2.1.6 and 2.1.7).
-l Violation 90-01-02 Procedure NCE-CP-5.020 dated January 15, 1990 for qualifying y
- nondestructive testing technicians to-perform visual examina-tions does not satisfy _ ANSI N45.2.6 as required by Section i
XI of the ASME Code.
(See Section 4.0)._ j i Violation 90-01-03 Failure to mark the center line of welds as required by
Section XI of the ASME Code (See Section 2.1.9).
, Unresolved Item 90-01-04 Failure to identify-starting-point and direction of ' erosion-corrosion thickness measurements.
The first two violations (90-01-01 and 90-01-02) and the unresolved item
(90-01-04) were related to licensee procedures and activities. associated with nondestructive testing of plant modifications and the erosion-corrosion inspection program performed by the corporate Materials Engineering and Analysis-NDE Subunit; not the ISI program.
The violations included. examples of.
. technical and administrative deficiencies in proceduras and fai-lure to-follow ' procedures. These deficiencies indicate the need for improved assurance of quality in this area. One potential hardware deficiency identified by'the NRC , involved a rejectable indication in a Unit 2 auxiliary feedwater system weld (part of violation 90-01-01). This issue is being addressed by the licensee.
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i 1.0 Persons Contacted (30703) Baltimore Gas & Electric (BG&E).
B. C. Rudell, Pressurizer Project Engineer
- M. Melbradt,-Licensing Engineer
't A. Zimmerman, Engineer, Q&A A. B. Anuje, Supervisor, QA
- L. Decker, ISI: Engineer
. ' S. R. Bufbaum, Supervisor NDE Unit
- A. S. Reed, Principal Materials Examiner
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- S. Sanders, Supervisor Radiation Control-K. Hoffman, Supervisor' Engineer L. B. Russell,' Manager-Calvert Cliffs R. Marshall, ALARA Coordinator S. Dobler, Engineer - PSEU D. Shaw, Licensing Engineer U.S. Nuclear Regulatory Commission J. E. Beall, Senior Resident Inspector, RI A. Asars, Resident Inspector, RI
- Denotes those attending the entrance and exit meeting.
The above listed personnel were present at-the-exit meeting. The inspector also contacted other administrative and: technical personnel ' during the inspection.
2.0 Independent Measurements - NRC Nondestructive Examinat'on and Quality i Records Review of Safety Related Systems During the period January 8-19, 1990 an onsite independent: inspection was. conducted at the Calvert Cliffs Nuclear Power Station. The inspection-was conducted by NRC regional based inspectors. The objectives of the
inspection were to assess the adequacy of the licensee's inservice inspection, welding quality control, erosion-corrosion,.and modification-programs and to assess the licensee's actions regarding. configuration control for piping hangers and supports. This was accomplished.by repeating examinations required of the licensee by regulations and codes and then' l , evaluating the results.
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. ,x 2.1 Nondestructive Examination-(NDE) 2.1.1-Visual Examination of Piping Welds (57050) Thirty-five (35) safety related pipe.weldments and adjacent base material (1/2 inch on either side of the weld) were visually examined - in accordance with' NRC -procedure NDE-10,; Rev. -1, Appendix A, and the associated site _ procedure-for. Visual. Examination of pipe systems and_ attached components,:QC documents, isometrics and as-built drawings.
This inspection included ASME Class-1, 2 and 3 pipe weidments fromt - the High Pressure Safety Injection ~(HPSI), Main Steam (MS),' Auxiliary _' Feedwater (AFW), and Shutdown Cooling (SDHX) systems._ The examina-- tion was performed specifically.to: identify any cracks or linear indications, gouges, leakage, arc strikes with-craters, or corrosion, which may infringe upon the. minimum pipe wall thickness. Mirrors, flashlights and weld gauges were used to aid in the inspection-and-evaluation of the weldments.
Results: The welding and overall workmanship inspected was satis-factory. No violations were identified.
2.1.2 Visual Inspection of Hangers and Supports (57050) During this inspection twenty-one_ (21) safety related hanger ard supports were visually inspected per NRC procedure NDE-10,-Rev. 1, Appendix A and B in conjunction with the site procedure for visual . examination of pipe systems and attached components, QC documents and . associated isometric drawings.
Included in this inspection were hangers and supports selected from_the Safety Injection (SI), Service Water (SW), Component Cooling Water (CCW), and' Shutdown Cooling (SDHX) ~ Systems. The accessible ~ surface area.and adjacent base metal for a distance of one-half inch on either side of the welds was examined.
In the area of component integrity specific. attributes looked for were proper installation, configuration or modification of supports, evidence of mechanical or structural damage, corrosion ~and bent, missing or broken members. Attachment #2 is a list of specific hangers and supports inspected.
Results: Welding and overall workmanship were acceptable. No violations were identified.
2.1.3 Liquid Penetrant Examinations (57060) Twelve (12) safety related pipe weldments and adjacent base material (1/2 inch on either side of the weld) were examined using the visible dye, solvent removable method per NRC procedure NDE-9, Rev. O, in conjunction with the licensee's procedure and associati:d QC records.
Included in this anspection were ASME Class 2 stainless steel weldments selected from the Safety Injection (SI) and Shutdown Coolirg (SDHX) Systems.
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,, t . Resul ts: The surface areas examined were.. properly prepared for_ the examination.
No violations were identified.
~ ' 2.1.4 Magnetic Particle Examinations (57070)- .[ Eighteen (18)_ safety related pipe lweldments and adjacent base material (1/2 inch on either side of the weld) were examined using the direct _ contact method (Yoke) with dry powder as the inspection medium, The examination was performed in accordance.with:NRC procedure'NDE-6, Rev. 1,.in conjunction with~the licensee's procedure and associated-QC records. -Included in this examination were ASME Class 2 and-3 ' pipe weldments selected from the plant pipe modification program.
The packages selected were for modifications made to the Main' Steam (MS) and Auxiliary Feedwater (AFW) systems.
, Results: No violations were identified.
2.1.5 Radiographic Examinations (57090) , Twenty (27) safety related pipe weldments were examined using an Iridium 192 source. The procedure and method used to perform radiography were in accordance with NRC procedure NDE-5, Rev. 1 in conjunction with the licensee'siprocedura for radiographic examination of welds NDE-5.300, Rev. O and associated drawings and QC documentation.
Included in this examination were ASME Class 2 and'3 weldments selected.
~ from the Mainsteam (MS), Auxiliary Feedwater ( AFW) and Safety Injection
Systems.
' ' . Results: The resulting radiographs were reviewed for indications of defects and compared to site radiographs to ensure that the welds identified were the same as those identified by the NRC.
No violations were identified.
L 2.1.6 Review of Licensee's Radiographs (57090) Seventy (70) safety related radiographs fromLthe licensee's files were , L reviewed to verify the adequacy of the radiographic program.
Radiographs were reviewed for technique, film quality'and weld integrity.
See Attachment 4 for specific licensee radiographs reviewed.
. Results: This ' inspection revealed numerous problems in the licensee's radtographs. The problems are summarized in the Attachment 4 and discussed below.
The following examples of failure to follow existing procedures were identified.
1.
Film Density Radiographic-film density on 13 of the films reviewed did not meet ASME code or the licensee's radiographic . procedure density requirements for density range (2.0 minimum s r - . s e
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. . 6- . to 4.0 maximum) nor. uniformity (-15% to_+30%). The licensee's . radiographic procedure NDE-5.300, paragraphs 10.2, 10.4 and 12.7 has the same density requirements!as the; code.- 2.
Missed Indications -The NRCLinspector identified rejectable- .
indications (porosity with tails indicating possible cracking) ' . on the licensee'_ radiograph 'of weld 7, view 8-11, in the. auxiliary-feedwater. system. The wel_d'was made as_part of a modification in 1982 and was.radiographed atlthat time.
Subsequent to the- - NRC inspector _ identifying.the. rejectable indications, the licensee:
independently verified _ the: condition and issued NCR M-82-6178.
3.
Inconsistent Marking On-Piping: Paragraph-6.2 of-the licensee's. P Scedure NDE -5.300 requires that reference' starting locations be marked on welds.when they are ultrasonically examined.,The-inspector found that most welds examined as part: of. the modifica-
, tion process did not 'have the required reference; marking.
] The'three findings discussed above are~ examples of failure.to-follow' existing procedures. This-is.a violation of 10CFR 50,: Appendix B,- l ~ , Criterion V. (90-01-31) Another example of failure _to= follow pro- . cedure is discussed in the ~section of this report entitled," Failure to Document NDE Deficiencies in NCRs." During the~ inspection, it-also was noted that the quality of the radiographic film:was poor due , to improper film processing._ Seven' film packets contained film with 'i streaks. The streaksiindicate that the' developing fixer was?not; .l adequately removed from the film.- In time,Lthis can cause fading of- / the developed radiographic image.
The~ methods of determing acceptable j residual fixer concentration levels are presented in. standard SE94
part III, processing films and viewing'and' storing radiographs, which ! is referenced by Section V of the ASME Code.
Site radiographic
procedure NDE-5.300, paragraph 12.6 states-that the manufacturers recommendation in developing exposed film ~is to be used. Although . the streaks on the radiographic film were out of the area of interest, ! they indicated poor film developing practices.
' ' The inspector also identified the.following areas where improvement ' could be made in Radiographic Procedure NDE-5.300.
1.
Radiographic Procedure NDE-5.300 references the wrong procedure in paragraph 11.0.
The procedure references NDE-CP5.002 "Quali-i fication and Certification of NDE Personnel" when it should
reference procedure NDE-CP-5.020.
- 2.
Radiographic Procedure NDE-5.300 does not address how radiographs of repairs are to be tracked.
Recording of repairs'on radiographic reader sheets is not performed in a consistent manner.
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Radiographic Procedure NDE-5.300 does not address which weld is _ intended to be reviewed when more than'one weld is on a single
radiograph.
4.
Calvert Cliffs QA Policy Rev. 20, Appendix 1B FSAR invokes-L ANS3.2-1076,- paragiaph 5.3.2(3) which states that. references should be included in procedures.
However,. radiographic Procedure' NDE-5.300, paragraph 3.0 and associated NDE reports do notJ . r reference the' applicable code addenda and year for Calvert-Cliffs. The procedure ~only states that the weld shall be evaluated--in - accordance with the applicable code.
During this inspection,. 'I the inspector found.it extremely difficult to identify the.
~ appropriate code addendum;and year for modifications that had
been performed'. -It is important that the applicable acceptance
criteria be clearly identified and readily available to the NDE-technicians to assure appropriate reviews.
It should be noted that the above violation (90-01-01). and procedure deficiencies are related to activities and-a procedure. associated with the BG&E Corporate Materials Engineering and Analysis-NDE Subunit ' and 'nvolve primarily modification activities and not the ISI program-inspections.
, 2.1.7 Failure To Document NDE-Deficiencies In NCRs:. It Also was' deterrrined during this-inspection-that the licensee was not-documenting NDE - deficiencies, -including those identified as part'of the -inservice inspection program, in nonconformance reports s required by their-a procedure QAP26.
Examples included deficiencies identified in welds 13-200W1W2, 13-2002W1, 13-2003W4 and valves 9048-3,fE9047-l'and-E9047-2. The inspectors determined that the deficiencies were. tracked i , through the maintenance M0 system and the welds ~were repaired and re-radiographed, but this system.does.not provide'the sameflevel of' [ review as the NCR system.
Failure to document deficiencies identified ' ' by NDE activities on an 'NCR as explicitly required cy procedure QAP26 is another example of violation (90-01-01) of failure to' follow . procedures.
2.1. 8 - Ultrasonic Examination (57080) ' ' Five (5) safety related. pipe weldments were ultrasonically examined using a Krautkramer USL48 ultrasonic flaw detector in-accordance.with NRC procedure NDE-1, Rev. O, licensee procedurt Southwest Research - ' Institute (SWRI) procedure-SWRI-NDT-800-36, Rev. 24 and associated < ultrasode test data.
Instrument calibration (linear veoification)- , was performed using NRC procedure NDE-2, Rev'. O.
A. distance amplitude correction curve (DAC) was constructediusing the licensee's calibration standards numbers 16, 62, 42,'and 59. To ensure repeatability of the ultrasonic examinations, instrument-settings and-search units (trans-ducers) were matched-as neerly as possible to those indicated by the . licensee's ultrasonic data reports.
' Results: No violations were identified.
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2.1. 9 -- ISI Reference Working System (73753) During their independent inspections, the inspectors determined that ' neither welds made as part of piping' system modifications-nor balance of plant piping system welds that are included in the
' Calvert Cliff's ISI program are marked as; required by Section XI IWA2600, Appendix III, Supplement 2 of the 1983 ASME Code. The - following welds did not:have the centerlines marked as required by ASME Section XI: Class 2 weld numbers 4R and SR in system 16FW2018,: Class 2' weld numbers 2R and 3R inf system -16FW2019, and. Class.1-weld numbers 5 and 31 in system SI2011'. Failure to mark the center of these welds,in_ accordance with Section XI IWA2600 and Appendix III,. Supplement 2 of the-ASME Code-is a violation of 10 0FR 50.55a.- -(90-01-03) 2.1.10 Erosion-Corrosion'(57080)- Five pipe components were examined for erosion-corrosion using a Nova 0-100 ditigal thickness gauge.
The method and procedures used were in accordance with NRC procedure NDE-11, llev.
0., the" licensee's-procedures, and quality assurance records.
The erosion-corrosion:- examination was performed or. selected pipe _ components to determine if wall thinning was present and to v'erify the accuracy. of licensee data.
The. thickness me u urements were taken at predetermined' locations.in the.systehm sC ected and were on a 2 inch by.2 inch grid pattern.
Included in this inspection were various size components selected from the Feed Water (FW), Heater Drain (HD), and Main Steam (MS)? systems.
Results: Based on the. inspections performed, the following problem in Materials Engineering and Analysis Implementing Procedure (MEE&A) 5.05 " SECONDARY SYSTEM PIPING EROS!M 1 RR0SION INSPECTION PROGRAM" was discovered. ME&A IP 5.05. At B, paragraph:2 states "The- - examiner will also be respor.stble n ..he following on the geometric sketch provided on the bottom of the.Jtrasonic' thickness report A.
Inspection startir.g point..." This "0" starting point was either missing from the data reports or it was unclear in which direction from the starting point it.was intended to perform the inspection (i.e., axial or circumferential).
The NRC reviewed five welds and for four _of-these welds the procedural requirement to identify'the = starting points was not adhered to (see attachment'No. 3 for tabulations).
Failure to identify the starting point and direction of Inspectior. precludes effective. trending of inspect'on results.
This is an unresolved item (90-01-04).
3.0 Review Of Open Items Violation 89-21-02(closed): During NRC inspection 89-21 the inspector fouid that the licensee's procedure for qualification of NDE personnel included a 60 day grace period beyond the ASME Code requirement'for requalification every 3 years. During this inspection, the inspector found-that the licensee deleted the 60 day grace period for NDE certification from the subject procedure. An audit of NDE records-was performed _by the T icensee which identified 8 inspections that required being. reperformed.
. ' Based on the above action, the inspector considers violation 89-21-02 closed.
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4.0 Review of Site NDE-Procedures and Manuals " The procedures listed in Attachment 5 were reviewed in the regional office during this-inspection period for compliance to the licensee's FSAR committnents and applicable codes,- standards and specifications.
Results: Calvert Cliffs has used two different qualification and.certifica-tion programs for visual ASME Section-XI VT1, VT2, VT5 and VT4 personnel.
Procedure CCI-613D is a Calvert Cliffs prv: dure used for the qualification of test and inspection personnel. This_ procedure meets the applicable: ANSI'N45.2.6-1978 requirements including the required minimum experience ~ of 3 years.
The second' procedure, NDE-CP-5-020, >1s a Baltimore Gas & Electric C-any procedure for qualification and certification of non-destructive examina- , tion personnel to ASME Section XI. visual.VT1, VT2, VT3 and VT4 requirements - also. ' Personnel qualified by this procedure performed ~ code required inspections at Calvert Cliffs. However, this'precedure does.not meet the ASME Section XI-1983 requirements and ANSI N45.2.6.. For example, the .. three months minimum experience listed in Attachment 2 of procedure " NDE-CP-5-020 does not meet the minimum of. 3 years required by ANSI s N45.2.6-1978.
This is a violation of 10 CFR 50.55(a) that requires plant inservice L inspections be performed in accordance with applicable editions of the ! ASME Code (90-01-02).
Furthermore, it was-noted that the-independent review of the procedure, as. required by Sectiion XI of the ASME' Code,.did
not identify this deficiency.
5.0 Attachments- !
Attachment No. 1 is a tabulation of specific pipe weldments and components examined and the examination results. Attachment No. 2 is a. tabulation of hanger and support components examined and the examination = results.
Attachment No. 3 is a tabulation of specific areas selected for. examination from the site erosion-corrosion plan and the examination results.
Attachment No. 4 is a tabulation of. radiographic films reviewed.
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6.0 Unresolved Items l Unresolved _ items are matters about which more information is' required ,
in order to ascertain whether they are acceptable items or violations.
An unresolved item is identified in Section 2.1.5.
, o 7.0 Management Meetings (30703)
Licensee management was informed of the scope and purpose of.the inspection at the entrance interview on January 8, 1990.
The findings of the. inspection were discussed with the licensee representatives during the course of~the inspection and presen t to licensee management at the exit interview (see , paragraph 1.0 for atts nees).
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< INDEPENDENT-.MEASUPEMENTS PROGRAM-- ATTACHMENTH1 :PAGE.1'OF 2' SITES CALVERT CLIFFS' .DATE: 01/08/90-THRU 01/19/90-p ' - I D -. SYSTEML CL/ .PT MTn-RT UT-VI-ACC REJ COMMENTS , , '
- 2-103-W1 MAINSTEAM.
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X X X-X EB2OO1-W4 AUX FW
X X X-X . EB2OO1-W5 AUX-FW
'X' ~X X X ' SI-2OO1A-2 SAFETY INJ.
X '2 Xc CAL BLK E6" . SI-2OO2-1 SAFETY INJ.
X-X X: CAL' BLK 62.- SI-2OO9-1' SAFETY INJ.
'X X X: CAL-BLK 42 SI-2011-5 SAFETY..INJ.
X X X CAL BLK 59 'O S1-2001-31 SAFETY.~INJ.
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' ' DATE::01/08/90:THRU,01/19/90 ,_ '
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"DATEO 01/08/90 THRU;01719/90/ .
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REJ - COMMENTS.
CC-6-2OOB-H 17 SK-36493-REV.3 SI EX HB222-2124-R21 SK-2-5906 REV.1 SI X-
DC-1-2010-H3 SK-211304 REV.4F SI-X DC-1-2010-R5
- SK-2113Q4 REV.4F SI
- X DC-1-1000-H11 SK;1435iREV.Ot SI.
X DC-1-1008-R9-SK-1435.REV.O SI X-(HB-22-2352-H34 SKa9913 REV.1-fSW - X - HB-22-2252-R1C JSK-9914'REV.O SW X HB-22-2124-R21-SK-2-5906 REV.1 SW X HB-22-2282-R2' SK-2-21002 REV.3 End' X-HB-23-2031-H3 SK-2-11205 REV.2 CCWl X 'HB-23-2012-H11 SK-2-114 REV.5F ~ CCW X HB-23-2045-HB-SK-2-112 REV.3F CCW
- X GC-3-1007-H4 SK-1633 REV.1 SDHX
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GC-5-1004-R14 SK-1138 REV.1 SDHX X.
. . A HC-3-1006-R15X SK-1142 REV.1 SDHX- 'X .i ! MC-3-1006-64 SK-178/1115 REV.4 SDHX X - ] GC-2-1006-R3 SK 178/1115 REV.4 SDHX i
i ~~HD-22-2035-R17 SK-2 5917 REV.4F SW .X, HB-22-2035-H14 SK-2-5922 REV.4F' SW X . " -1 '_ t + E . j{
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C LVEST-CLIFFS-PALE 1.OF 1-1/8/90-1/19/90 EROSION / CORROSION ATTAC;;;1ENT' 3 - . '
COMPONENTS SYSTEM COMMENTS .{ GB-06-2OO1-11 HEATER DRAIN "O" MARKED ON SKETCH LUT AXIS UNCLEAR GB-06-2062-12 HEATER DRAIN NO "O" MARKED HD-08-2013-05 FEEDWATER ACCEPTABLE HB-08-2015-05 FEEDWATER NO "O" MARKED - EB-03-2010-01 MAINSTEAM "O" MARKED ON SKETCH BUT AXIS UNCLEAR __.
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' . c-, . , ATTACHMENT 4 Tabulation of Radiographic Film Reviewed System /Lig Weld ID Comments 13"2002 W1 Accepted 13-2002 W2 Accepted-13-2002 W3 Accepted 13-2002 W4-Ac'cepted 13-2002 W5 Accepted 13-2002 W7 NRC rejected area 8-11-(porosity with tails) 13-2002 W8 Improper Development 13-2002 W9-Accepted 13-2002 W10-Transverse indication under-film area
- 2 outside of weld not reported nor-I dispositioned l
l 13-2002 W12 Accepte'd- ! 13-2002 W13 Density 13-2002 W14 Accepted I 13-2002 W14 Accepted-13-2003 W1 Accepted 13-2003 W2.
Improper; Development I
13-2003 W3 In: proper ~ Development- ]. 13-2003 W4 Accepted i 13-2003 W5 . Accepted j 13-2003 W6-Accepted 13-2004 W8 Improper Development 13-2004 W9 Accepted ' i
.. - - . -. . , v.
. . .- Attachment 4
, System /Line ' Weld 10 ' Comments 13-2004 W10 Improper Development 13-2004 Wil Accepted 13-2004 W12 Accepted 13-2004 W13 Accepted ^ 13-2004 W14-Density less than 2.0 in penny of l all views l 13-2004 W15 Density less-than 2.0-in penny all views 13-2004 W16 Acceptance-13-2004-W17 Density -15 in all rems 13-2004 W18 . Acceptance 13-2004 W19 Acceptance 13-2004 W20 Density over 4.0 under #12 13-2004 421 Acceptance.
13-2004 W1 Acceptance 13-2004 W2 . Acceptance I , 13-2004 W3 Improper Development-a 13-2004 W4 Acceptance-13-2004 W5 Density under 2.0 13-2004 W6 Improper Development , 12-2007 W1 Acceptance 12-2008 W4 Acceptance 12-2008 W1 Acceptance 12-2007 W4 Acceptance-13-2010 W1 Acceptance
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o: . ( <.. c' ' Attachment 4
System /Line Weld 10 Comments 13-2010 - W2 Acceptance i 13-2010 W3 Acceptance 13-2010 W4 Acceptance 13-2010 WS Acceptance-i
8-2002 W2 Acceptance { - l 8-2003 W2 Acceptance ' 2MS-109 W1 Acceptance
2MS-109 W2 Acceptance ! 2MS-103 W1 Acceptance - g . I 2MS-103 W2 Acceptance
2MS-103 W3 Acceptance 2MS-103 W4 Acceptance' 2MS-106 W1 View 2-3 exceeds +30 density-View-3-4 exceeds +30 density-View 4-1 exceeds +30 density 2MS-106 W2 hcceptance i 2MS-106 W3 ' Acceptance 21 S/G AFP W2 View.1-3 less than -15 View 2-3 less than -15 . 89-10-322A W1 Accepted
- 11 pump
'
22 S/G AFP W7 Accepted 22 S/G AFP W8 Accepted 22-S/G AFP W9 View 1-2 exceeds -15 density _ View 3-4 exceeds--15 density' , 22 S/G AFP W10 Accepted i i , , ! '
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- - Attachment 4
.
System /Line Weld 10 Comments ! 22 S/G AFP W6 Accepted
l i L 22 S/G AFP W5 Two welds on film procedure.
i l nor weld identifyings'which.
i weld is being RTed l 22'S/G AFP-W1-Accepted 22 S/G SFP W2 Accepted-j-22 S/G AFP W3 Accepted
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. l . L ATTACHMENT 5 PROCEDURES REVIEWED .l Procedure'titie-Number / Revision: l' VISUAL EXAMINATION OF PIPE SYSTEMS NDE-CP 5.020 issued.- , NON-DESTRilCTIVE EXAMINATION PERSONNEL January 15, 1990
VISUAL EXAMINATION OF PIPE SYSTEMS NDE 5.702, REV 8-AND ATTACHED COMPONENTS
1 . NDE 5.300, REV. 0 RADIOGRAPHIC EXAMINATION OF WELDS RADIOGRAPHIC EXAMINATION OF NONFERROUS NDE 5.301, REV. 2-L
- RADIOGRAPHIC EXAMINATION OF STEEL CASTING NDE 5.302, REV. 0 l
MATERIALS ENGINEERING AND ANALYSIS ME&A IP 5.05, REV. 0 l.
IMPLEMENTING PROCEDURE
. QUALIFICATION OF TEST AND INSPECTION PERSONNEL CC-6130, Ch. 1 . Southwest i;e:-earch Institute (SWRI) MANUAL ULTRAEONIC EXAMINATION OF AUSTINITIC NDT 600-31,-REV.~24 - PRESSURE PIPING WELOS ' i . . . p I , i i ! i , .- a . -
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