ML18094A690
| ML18094A690 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/14/1989 |
| From: | Miltenberger S Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18094A691 | List: |
| References | |
| NLR-N89189, NUDOCS 8909190098 | |
| Download: ML18094A690 (681) | |
Text
{{#Wiki_filter:J.--_.* r Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer September 14, 1989 NLR-N89189 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen: NINETY DAY REPORT FOR INSERVICE INSPECTION ACTIVITIES PERFORMED DURING THE EIGHTH REFUELING OUTAGE SALEM GENERATING STATION - UNIT NO. 1 DOCKET NO. 50-272 Public Service Electric and Gas Company {PSE&G) hereby provides, in the enclosure to this letter, the Ninety (90) Day Report for Inservice Inspection (ISI) activities conducted at Salem Unit 1 during the eighth refueling outage. This report is submitted in accordance with Section 4.0.5 of Appendix A to the Technical Specifications for Salem Unit 1 and Article IWA-6220(b) of Section XI of the ASME Boiler and Pressure Vessel Code. The inspections and examinations performed complete the requirements for the first outage of the first period in the second 10 year ISI interval. This submittal consists of three documents: 1) Form NIS-1, "Owners Data Report for Inservice Inspection", 2) Form NIS-2, "Owners Report for Repairs or Replacements", and 3) 11 1989 Inservice Examination of Selected Components at Salem Generating station", Volumes 1 and 2, prepared by Southwest Research Institute. Should there be any questions with regard to this submittal, please do not hesitate to contact us. Sincerely, Enclosures
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Document Control Desk 2 9-14-89 NLR-N89189 c Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 Mr. E. J. Mossa Assistant Director New Jersey Department of Labor and Industry P.O. Box 1503, Labor and Industry Building Trenton, New Jersey 08615
v-- ------ FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES r ; . Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant~ Unit l
- 4. Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 8. This report covers the examinations that were conducted during the 8th Refueling Outage.
- 9. Components Inspected.
MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SER. NO. NUMBER BOAl*rn NO.
#1 Reactor Combustion 67201 Head Vessel Engineering 67101 Vessel N/A 20757 #11 Steam ~\iestinghouse 1003 N/A 68-10 Generator Tampa Div.
P.O. Box 19218
* #12 Stearn Generator Tampa, Fl 33616 II II 1022 N/A 68-08 #13 Steam Generator II II 1023 N/A 68-09 #14 Steam II II Generator 1203 N/A 68-51 #1 Regen. Sentry Equip. 4195-A4 N/A 385, 386, Ht. Exch. Corp 7, 8, 9 387 Oconomowoc, WI.
Page 1 of 15
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES r Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit 1
- 4. Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 9. Components Inspected (cont'd)
MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SER. NO. NUMBER BOARD NO.
#1 Pressur- Delta Southern 1011 N/A 68-8 izer Chemical United Engineers Volume & & Constructors Control (UE&C) 30 South N/A N/A N/A Piping 17th St., Phila.
System PA 19101 Containment UE&C N/A N/A N/A
'pray Piping *ystern Mains team UE&C N/A N/A N/A Piping Sys. #1 Volume Joseph Oat 1781-2A N/A 374 Control & Sons, Inc.
Tank Camden, N.J.
#1 Excess Atlas Industries 850 N/A 701 Letdown Heat 81 Somerset Place Exchanger Clifton, N.J. #1 Letdown Atlas Industries N/A N/A 694 Heat Exchanger #1 RHR Heat Engineers & Sl5860-C N/A 122 Exchanger Fabricators, Inc.
Page 2 of 15
~'Ol~M NlS-1 O\~NER' S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236,. Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit l
- 4. Owner's Certificate of Authorization (if required) N/A.
- s. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 9. Components Inspected (cont'd)
MANUFACTURER STATION OR COMPONENTS OR MANUFACTURER OR INSTALLER PROVINCE NATIONAL APPURTENANCE OR INSTALLER SER. NO. NUMBER BOARD NO. Pressurizer UE&C N/A N/A N/A Relief .I Piping Sys. I Reactor UE&C N/A N/A N/A Coolant Piping Sys. Steam Gen. UE&C N/A N/A N/A Feed Piping ystem Safety UE&C N/A N/A N/A Injection Piping Sys. Page 3 of 15
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
- 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza, New~rk, 'New Jersey 07101 Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit 1 4 . Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 10. Abstracts of Examinations:
1.0 Examinations were conducted by PSE&G as well as companies under contract to PSE&G. The following examination summary (Section 11) is a brief summary with further details found in the attached report and on file at the Salem Generating Station. Since nearly all inservice examination requirements can be found in Salem's Technical Specifications, this summary lists these requirements first arranged to Tech. Spec. paragraph number followed by applicable NRC Circulars and Bulletins.
- 11. Examination Summary
- 1. 0 Technical Specification 4.0.5 - ASME XI The required number of examinations for the first outage of the first period in the second 10 year interval were completed
- as shown in the ISi Long Term Inspection Plan.
1.1 ISi Examination Southwest Research Institute (SwRI) under the direction of the Salem ISi Group conducted ninety two (92) ultrasonic, one hundred fifty three (153) liquid penetrant, forty three (43) magnetic particle and one (1) visual examination on the Main Stearn, Residual Heat Removal, Reactor Coolant, Chemical and Volume Control, Stearn Generator Feedwater, Safety Injection and Containment Spray Systems. The following nonconforrnances were reported by SwRI: PT Examination of 4-SJ-2120-33, (elbow to reducer) revealed a 9/16" linear indication extending into base metal. After cosmetic buffing by PSE&G personnel, SwRI reexamined the weld and found no recordable indications. Thickness measurements were taken before and after the buffing to insure minimum wall thickness was not violated. Salem Maintenance Department conducted three (3) visual examinations on Nuclear Class 1 bolting and/or valve internal surfaces. No discrepancies were noted. Page 4 of 15
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES ( Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit l
- 4. Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 11. Examination Summary (cont'd):
1.2 Visual Examination of Supports 1.2.l Visual examinations were conducted on one hundred and thirty six (136) Nuclear Class I, two hundred and seventy (270) Nuclear Class II and one hundred and ninety (190) Nuclear Class III supports. Several discrepancies were found i.e., wrong spring settings, rust, loose bolts, .. etc. Of those discrepancies that rendered the support inoperable, a work order was generated and subsequently the discrepancy corrected. Note: Work orders were written to correct all other discrepancies not rendering the support inoperable. 1.3 Safety/Relief Valve Testing The PSE&G Salem Maintenance Department conducted twenty three (23) Lift Set Tests on various system relief valves. Ten (10) of the valves tested exceeded the allowable limits. All were reset to the proper setting and tested acceptable. Three (3) Pressurizer Relief Valves were sent to Wyle Laboratories for testing and refurbishment. Lift set test results were accepted for the as-found tests. After as-found testing, the valves were refurbished and set to their required settings. In addition, all (20 total) Main Steam Safety Valves were removed and replaced with new valves. The new valves were lift set tested at Crosby Valve and Gage Company prior to installation. 1.4 System Leakage Exams
- 1. 4 .1 As required by ASME Section XI, system leakage exams were performed by the Salem ISI Group with assistance from the PSE&G Maintenance Department on the following systems:
Page 5 of 15
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES ( Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit 1 4
- Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 11. Examination Summary (cont'd):
1.4 System Leakage Exams (cont'd) 1.4.l Reactor Coolant, Containment Spray, Residual Heat Removal, Safety Injection, Reactor Coolant Sample, Waste Drain Liquid, Chemical and Volume Control (Operations), Pressurizer Relief Piping, Spent Fuel Cooling, Service Water, Fire Protection, Component Cooling, Auxiliary Feed, Demineralized Water (Restricted), Steam Generator Blowdown and Chemical and Volume Control (water recovery). None of the above listed systems exhibited any excessive leakage. There was however, some minor mechanical leakage (eg. valve packing, etc.) for which work orders were written to correct. Technical Specification 4.4.5.0 - Steam Generator Tube Eddy Current Inspection. Westinghouse NSS under the direction of the Salem ISI Group conducted eddy current examinations on 11 through 14 Stearn Generators. All eddy current data was collected from the hot leg side with the SM-lOW No Entry Fixture, using the MIZ-18 Multi-Frequency eddy current system. The eddy current testing was divided into two phases as shown below. Phase l - Tech. Spec. sample generator. 11 steam generator was selected as the tech. spec. sample generator. The original scope called for testing of approximately 3~% of the tubes (1202) in 11 steam generator which included: (a) 12% random sample required by technical specification (406 tubes). (b) Row l and Row 2 tubes as per a commitment made in Unit 2 LER 311/88-019-00. (c) Row 8 through Row 12 tubes for AVB geometry analysis and to meet the requirements of NRC Bulletin 88-02 .
- ( d) All tubes with previous indications from past refueling outages.
Page 6 of 15
--------1 I
!-'ORN NIS-1 Ol'mER' S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES r
Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit 1
- 4. Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 11. Examination Summary (cont'd):
2.0 Technical Specification 4.4.5.0 - Stearn Generator Tube Eddy Current Inspection (cont'd) Phase 2 - Row 1 and Row 2 tubes in 12, 13 and 14 steam generators per a commitment made in Unit 2 LER 311/88-019-00 and any tubes in these generators which had previous indications from past refueling outages.
SUMMARY
OF RESULTS Note: Examinations in 11 through 14 Stearn Generators revealed evidence of tangential cracking in a number of Row 1 tubes. PSE&G decided to mechanically plug all previously unplugged Row 1 tubes in 11 through 14 Stearn Generators. PHASE 1 TESTING Stearn Generator 11: A total of 1402 tubes were tested. Due to the detection of one pluggable indication while performing Phase 1 (a) testing, an additional 200 tubes were examined. Note: Credit was taken for tubes inspected in (b) and (c) of the Phase 1 testing in the sample expansion. Eighty-eight (88) tubes were plugged as a result of this eddy current inspection of which Eighty-Four (84) were Row 1 tubes. PHASE 2 TESTING Steam Generator 12: A total of 205 tubes were tested. Eighty-nine (89) tubes were plugged as a result of this eddy current inspection of which Eighty-four (84) were Row l tubes. Stearn Generator 13: A total of 207 tubes were tested. Eighty-Six (86) tubes were plugged as a result of this eddy current inspection of which Eighty-three (83) were Row l tubes. Note: Three (3) Category "4" plugs were removed from 13 Steam Generator Hot Leg and replaced with Category 16" plugs and one (1) Category "4" plug had a hot leg PIP (plug in plug) installed. Page 7 of 15
FORM NIS-1 OWNER'S DATA REPORT FOR Il'ilSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
- l. Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101 Plaht: $alem Generating Station P.O. Box 236, Hancock's Bridge,
.2. New Jersey 08038
- 3. Plant: Unit l
- 4. Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 11. Examination Summary (cont'd):
PHASE 2 TESTING (cont'd) Steam Generator 14: A total of 710 tubes were tested. One-hundred (100) tubes were plugged as a result of this eddy current inspection of which Eighty-Four (84) were Row 1 tubes. Note: One (1) hot leg PIP (plug in plug) installed in 14 steam Generator due to an unanalized plug heat existing in that location. Current Status of the Steam Generators At this time the total number of tubes plugged in the Salem Unit 1 Steam Generator are as follows: Genera tor 4~ 11 12 13 14 Tubes Plugged 102 107 103 131 Note: In the Steam Generators 11-14, the first five (5) and the last five (5) tubes in row l were explosively plugged because of a generic wearing problem on the tubes due to the vibration of the tube lane blocking device. 3.0 Technical Specification 4.6.1.2 (d) Containment Type "B" (Penetration) and "C (Valves) Leak Rate Testing. PSE&G Research Corporation under the field supervision of th~ Salem ISI Group conducted leak rate tests on sixty-three (63) Type "C" Mechanical Penetrations (122 valves), four (4) Type "B Mechanical Penetrations and sixty-six (66) Type "B" Electrical Penetrations. 3.1
SUMMARY
The results of these tests revealed several Type "C" valves exceeding leak rate acceptance criteria, which were reworked to an acceplable conditon. A total As-Found leakage of 8,500 SCCM was measured through all containment penetrations (minimum penetration flow path of combined Type Band Type C tests). After corrective maintenance, the total As-Left leakage rate was 23,742 SCCM (maximum penetration flow path of combined Type Band Type C Tests). Both of these values are within the Technical Specification acceptance criteria of 129,750 SCCM (0.6 La). Page 8 of 15
FOH.M NIS-1 mvNER 'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
- 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit l 4
- Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 11. Examination Summary (cont'd):
3.1
SUMMARY
(cont'd) The As-Found Type A tests results based on a running Type A leakage just prior to the start of the outage of 92,494 SCCM added to the total As-Found minimum flow path leakage of penetrations tested (8,50C SCCM) is 100,994 SCCM or 0.467 La. This value is with the Technical Specification acceptance criteria of 0.75 La. 4.0 Technical Specification 4.6.1.3 (b) Elevation 100' and 130' Airlock Leak Rate Testing. 4.1
SUMMARY
PSE&G Research Corporation under the field supervision of the Salem ISI Group conducted leak rate tests on the 100' and 130' personnel airlocks. At this time the combined total As-Left leakage through the airlocks is 1,184 SCCM which satisfies the Technical Specification acceptance criteria of < or = to 0.05 La (10,812 SCCM). 5.0 Technical Specification 4.7.9 (a) "Visual Inspection of Hydraulic and Mechanical Snubbers 5.1 Summary Contract personnel under the direction of the Salem ISI Group conducted visual examinations on twenty four (24) hydraulic and one hundred and fifteen (115) mechanical snubbers. No discrepancies were found that would effect operability. However, several minor indications were found such as minor rust and attachment ends having washers missing and union leaks (hydraulic snubbers). All discrepancies were corrected. Page 9 of 15
FORM NIS-1 OWNER'S DATA REPORT :fOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
- 1. Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant~ Unit 1
- 4. Owner's Certificate of Authorization (if required) N/A.
- 5. Con~ercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 11. Examination Summary (cont'd):
6.0 Technical Specification 4.7.9 (c) "Functional Testing of Selected Hydraulic and Mechanical Snubbers" 6.1 Summary - Hydraulic Snubbers Technical Specification 4.7.9 requires functional testing on 10% of the total number of installed hydraulic snubbers, during each plant refueling outage. In addtion, all snubbers which failed their previous functional test shall also be functionally tested. Hydraulic snubber in-place functional testing was performed by Wyle Laboratories using the Wyle API Hydraulic Snubber Test System. The results of these tests revealed the following:
- One (1) 200 Kip main steam isolation valve (MSIV) hydraulic snubber "as found" test acceptable.
- Two (2) 1000 Kip Steam Generator (S/G) Rexnord and one (1) 1000 Kip Steam Generator (S/G) Paul Monroe hydraulic snubbers
~ere "as-found" tested acceptable. There were no previous failures to be tested.
- 6. 2 Su1mnary - Meehan ical Snubbers Technical Specification 4.7.9 requires functional testing on 10% of the total of each type of installed mechanical snubbers during each plant refueling outage. In addition, for each snubber that does not meet the acceptance criteria, an additional 10% of that type of mechanical snubber shall be functionally tested.
Page 10 of 15
FORH NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit l
- 4. Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 11. Examination Summary (cont'd):
6.2 Summary - Mechanical Snubbers (cont'd) The mechanical snubber functional tests were performed on-site by PSE&G under supervision of Wyle Labs. The first (10%) sample of mechanical snubbers consisted of: 6 - PSA -l's, 2 - PSA-3's, 2 - PSA-lO's and 1 PSA-35 for a total of 11 snubbers. In addition to the initial sample, all the PSA l/4's (5) and PSA l/2's (4) were tested. The PSA l/4's and l/2's are tested each refueling outage due tv their failure rate from previous refueling outages. There were no failures per the procedure, however, four (4) of the mechanical medium snubbers exceeded the fifty percent increase in drag force acceptance criteria per Tech Spec's. These snubbers were dispositioned acceptable for use, however, an additional (10%) sample of mechanical medium snubbers were selected for testing. This sample consisted of 4 - PSA-l's, 3 - PSA-3's and 3 - PSA-lO's for a total of 10 snubbers. All were tested acceptable, however, three (3) of the snubbers exceeded the fifty percent drag force increase. An emergency Tech. Spec. relief was processed and approved to delete the requirement for performing the drag force comparisions. The relief was based on industry experience and approved Tech Spec's changes of other utilities which showed the drag force comparison test was not a valid indicator of snubber degradation. No additional snubbers were tested. 7.0 Technical Specification 4.4.10.1.1 Reactor Coolant Pump Flywheel Examination
SUMMARY
Southwest Research Institute (SwRI), performed ultrasonic examinations (UT) of the top sides only on No's 11, 13 and 14 Reactor Coolant Pump Flywheels. No reportable indications were observed. Page 11 of 15
PORI*l NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES
- l. Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit 1
- 4. Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. Natio~al Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 11. Examination Summary (cont'd):
8.0 Special Examinations
- NRC Bulletin 82-08, "Thermal Stresses in Piping Connected to Reactor Coolant System", sixteen (16) 1.5-inch Safety Injection, two (2) 2-inch and two (2) 3-inch Chemical and Volume Control we:~s were examined with UT. No reportable indications were noted.
- NRC Bulletin 88-11, "Pressurizer Surge Line Thermal Stratification," all four (4) welds on the 14-inch Pressurizer Surge Line were examined with UT. No reportable indications were noted.
- NRC Bulletin 87-01, "Thinning of Pipe Walls in Nuclear Power Plants", measurements were taken at forth one (41) locations to identify possible pipe corrosion/erosion.
- NRC Bulletin 82-02, "Degradation of Threaded Fasteners in the Reactor Coolant Pressure Boundary of Power Plants", Visual (VT) and Magnetic Particle (MT) examinations were performed on the Primary Manway closure bolts from four Steam Generators. No reportable indications were observed. All bolts were then lubricated with a thin coating of Felpro N5000 Lubricant and reinstalled. The Reactor Coolant Pump Main Flange bolting were visually examined in place. No reportable indications was observed.
- NRC Circular 76-06 and NRC Bulletin 79-17 Commitment to examine and/or flush stainless steel lines containing stagnant borated water. As part of the ISI program, SwRI performed NDE on twenty seven (27) piping welds covered by this circular. There were no adverse findings in the examinations.
Quarterly Chemistry Samples were taken by the PSE&G Chemistry Department and the results transmitted to the Salem ISI Group as required by Chemistry Procedure CH-3.5.060. During the Past 18 months this program identified a few nonconformances. The nonconforming piping was flushed and the situation corrected. This was verified by additional sample analysis. Page 12 of 15
FORM NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES L Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit 1 4 . Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 11. Examination Summary (cont'd):
9.0 Summary NUREG 0578 - TMI Lessons Learned Perform System Leakage Exams on systems outside Containment and take corrective actions necessary to reduce leakage as low as possible on systems likely to contain radioactive liquids in the event of an incident. The Salem ISI Group performed System Leakage Exams on the Safety Injection, Chemical Volume and Control, Residual Heat Removal and Containment Spray Systems. In adLition, PSE&G Research Corporation under the direction of the Salem ISI Group conducted the Waste Gas System Integrated Leak Rate Test in accordance with ISI Procedure M9-ILP-WG-l. There were no adverse findings in the examinations or tests conducted relative to this bulletin. Page 13 of 15
r---~--~~~~~~*----------------~~~------- FOHN NIS-1 OWNER'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit 1 4 . Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 12. Owner's Report for Repairs or Replacements, Form NIS-2
- 1. 0 In accordance with the requirements of Paragraph IWA-7520(A)(8) of Section XI, 1983 Edition, including Summer 1983 Addenda, completed Owner's Report for l~epairs or Replacements, Form NIS-2, are submitted as an attachment to this report.
Note~ A reference index has been prepared and is also included with this attachment. Page 14 of 15
- t'*ORM NIS-1 0111NER 'S DATA REPORT FOR INSERVICE INSPECTIONS AS REQUIRED BY THE PROVISIONS OF THE ASME CODE RULES Owner: Public Service Electric & Gas Co., 80 Park Plaza, Newark, New Jersey 07101
- 2. Plant: Salem Generating Station P.O. Box 236, Hancock's Bridge, New Jersey 08038
- 3. Plant: Unit l 4 . Owner's Certificate of Authorization (if required) N/A.
- 5. Commercial Service Date 7/1/77.
- 6. National Board Number for Unit N/A.
- 7. Examination Dates: 03/28/89 through 06/18/89.
- 12. Owner's Report for Repairs or Replacements, Form NIS-2 We certify that the statements made up in this report are correct and the examinations and corrective measures taken conform to the rules of the ASME Code Section XI.
Date~*)?, 19ff Signed PSE&G Owner By Certificate of Authorization No. (if applicable) N/A Expiration Date __ ltf/A: CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National oard oi £oiler and Pressure Vessel Inspectors and/or the State or Province of New Jersey and employed by Lumbermen's Mutual Casualty Company, Long Grove, Illinois, have inspected the components described in this Owner's Data Report during the period 03/28/89 to 06/18/89 and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this Owner's Data Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed of implied, concerning the examinations and corrective measures described in this Owner's Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ., Page 15 of 15 I I I __J
- NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS INDEX CODE JOB PACKAGE NO. DESCRIPTION S87-008 VALVE lPSl REPAIR S88-086 VALVE 14SJ156 REPLACEMENT S88-091 VALVE 12GB4 REPAIR S88-158 VALVE lPSl REPAIR S88-320 1FE641A REPAIR S89-007 VALVE 11SW25 REPAIR S89-017 VALVE 12SJ45 REPAIR S89-019 VALVE 14MS10 REPAIR S89-027 VALVE 1CV386 REPLACED S89-040 lMS-3017 PIPE SPOOL REPAIRED S89-057 I S89-085 VALVE 11GB4 REPAIR S89-058 VALVE 12CS48 REPAIR S89-062 VALVE 1CC280 REPAIR S89-063 VALVE 11MS169 REPAIR S89-066 VALVE 12SJ142 REPLACED S89-067 VALVE lCV3 REPAIRED S89-068 VALVE 1CV5 REPAIR S89-069 VALVE 1CV4 REPAIR S89-075 VALVE 12GB4 REPAIR S89-080 VALVE 1CC113 REPAIR S89-081 VALVE 11SJ113 REPAIR S89-082 VALVE 13GB4 REPAIR S89-086 VALVE 14GB4 REPAIR
- S89-087 1
VALVE 12GB4 REPAIR
- NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS ODE JOB PACKAGE NO.
S89-088 INDEX DESCRIPTION VALVE 13GB4 REPAIR S89-089 VALVE 1CV302 REPAIR S89-096 11 S/G MANWAY BOLTS REPLACED S89-099 VALVES 1SJ906 & 1SJ907 REPLACED S89-100 RX VENT INST. TUBING REPAIR S89-108 VALVE 11BR151 REPAIRED S89-118 VALVE 1PS4 REPAIR S89-119 VALVE 1PR1 REPAIR S89-120 12 S/G PRIMARY MANWAY BOLT REPLACEMENT S89-121 14 S/G PRIMARY MANWAY BOLT REPLACEMENT S89-123 14 S/G HELICOIL HOT LEG MANWAY S89-124 12 S/G HOT LEG BOLT #14 REPLACEMENT S89-125 11 S/G PRIMARY MANWAY BOLT REPLACEMENT S89-133 VALVE 11SS188 REPAIR S89-134 VALVE 12MS9 REPAIR S89-135 VALVE 1SS33 REPAIR S89-139 VALVE 11SS181 REPAIR S89-141 VALVE 11CA330 REPAIR S89-142 14 S/G MACHINING HANDHOLE S89-147 VALVE 1WL258 REPAIR S89-152 VALVE 11CA330 REPAIR S89-154 VALVE 1PR3 REPAIR 2
NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS INDEX CODE JOB PACKAGE NO. DESCRIPTION S89-155 VALVE llMSlO REPAIR S89-173 VALVE 12SJ156 REPAIR S89-194 12 BAT PUMP REPLACED 3
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date_J_a_n_u_a_r_y_3_0_,_1_9_8_9_ _ _ _ _ _ __
Name Foot of Buttonwood Rd, Hancocks Bridge, NJ Sheet_~l~__ of__l~---------- Address 08038
- 2. Plant Salem Nuclear Generating Station Unit #1 Name Foot of Buttonwood Rd,~ Hanc*ocks Bridge, NJ Code Job Package #S-87-008 Address Repair Organization P.O. No., Job No., etc.
08038
- 3. WorkPerlormedby~P~S~E~&~G~C~o~*----------~ Type Code Symbol Stamp _ _,N=R~--------
Name Authorization No._~~---------- Foot of Buttonwood Rd, Hancocks Bridge, NJ Expiration Date October 3. 1991 Address 08038
- 4. Identification of system Reactor Coolant (RC) Nuclear Class I
- 5. (a) Applicable Construction Code 198..3.__Edition,_._l_,9~8'-3.___ _ _ Addenda, Summer Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3_ __
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Copes lPS-1 Vulcan N/A N/A None N/A Repairs N/A
- 7. Description of Work Replaced plug, stem assembly, studs and nuts on lower bonnet.
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Other D Pressure N. 0. P. psi Test Temp. N. 0. T. *o F Visual Leak Examinations NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
- (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
/
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Hepa i r conforms to the rules of the ASME Code, Section XI. repair or replacement Certificate C T _ h n t i Q _ f.-=3::..6.::.._,,------------Expiration Date __o""c-"-'t'""'o"'b"--"e"'r'--""3_,,'--""1"'9'""'9~1_____ Signed ~ ,.......-~ Owner or Owner's Designee, Title Mc.,_A stl. ",, Q.,l\oate _ __..l1+/__,3"'--=o+/----'s=--J+---, 19 _ __ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casuali ty Co. of L""o""""n"-'-----'G"'r""o"-v-'e_:,~_I_L______________---:---::--..--,-,..,.------have i!JJi?ted the components described in this Owner's Report during the period _ _ _ _ _ _...L..~'--_,,,._..c.._ _ to IA 7-()7. , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this
--~--~~_f_,_Cv_-~ _______ Commissions _ _National _/i,C(~~J_J~J~-----------
Board, State, Province, and Endorsements Date_ _i-"-._-*_/_()_ _ _ 19 f"J
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date __J_u_n_e_l_5----=--,_1_9_8_9_ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet __l _ _ _ of _ _l_ _ _ _ _ _ _ _ _ __ Address
- 2. Plant Salem Nuclear Generating Station Unit # 1 Name Foot of,Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package # S88-086 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp __N_R_ _ _ _ _ _ _ __
Name Authorization No._"""3"""6_ _ _ _ _ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Safety Injection Nuclear 1
- 5. (a) Applicable Construction Code Bl6. 5 19~ Edition,~1_9~6~9_ _ _ _ Addenda,~1~9_7_0~~---Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19--=8'-"3,___
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME
.. Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve 14SJ156 N/A N/A N/A N/A N/A Reolacement NIA
- 7. Description of Work Replace bonnet stud in kind
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D In service Leak Examination Other D Pressure _ _ _ _ _ psi TestTemp. _ _ _ _ _°F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1 l size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. -
- (12/82) This Form (E00030l"may be obtained from the Order Dept., ASME, 345 E. 47th St., New Y.ork, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and thisReplacement conforms to the rules of the ASME Code, Section XI. repair or replacement
---=~------------Expiration Date October 3, 1991 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumberme.ns Mutual Casualty Co. of
-'L==oo.::n::...:i---=G=-=r=-o=--=v-=e=..L--=I=-=L=---------------__,~~~...,.._,,__ _~have inspected the components described in this Owner's Report during the period to J_,.,iz_,,!(" , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this .owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date_ _ ___,.f'--.r-"-)_ _19 t?
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 . Owner Public Service Electric & Gas Co. Date __J=u~n,,,e'-----'l,,_,2"'-L'_,,,1'""9'""8,_,9,,___ _ _ _ _ _ __ Name Foot of Buttonwood Rd. ,Hancocks Bridge,NJ Sheet 1 of _ _...__ _ _ _ _ _ _ _ __ Address
- 2. Plant Salem Nuclear Generating Station Unit-"-_,.,!~----------------
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package i S88-091 Address -""""'""'-'R~e-p"'-a""'ir""o"-r-g""'a""'ni"""z""at""io"'n,,i.=P-.0_,,.'-N-'o""'.. . _,J.uoc::b:..u..:Nz.o.L.,-e-tc-.--
- 3. Work Performed by __P_S_E_&_G_C_o_m~p_a_n~Y~------- Type Code Symbol Stamp _ _N_R_ _ _ _ _ _ _ __
Name Authorization No. _____3_6_ _ _ _ _ _ __ Foot of Buttonwood Rd. ,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System _ _ _
- _st Ma_i_n _e_a_m_ _ (MS)
_____ Nuclear _ _ _ _Class ____ II_ _ _ _ _ _ _ _ _ _ _ _ _ __
- 5. (a) Applicable Construction Code B31. 7 19___§2_Edition,_1_9_6~._9_ _ _ _ Addenda,l_..:.9--=7--=0'------Code CaseN/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Model # 12GB4 Masonelian N/A N/A 37-2X871 N/A Reoair N/A
- 7. Description of Work. _ _I_n_s_t_a_l_l~p~l_u~g~i_n __l_u_b_r_i_*_c_a_t_o_r__
h_o_l_e_a_n--=d.:......:s=-e.::....::.:ac=l:....:wc...e=-c=l-"-d'-------------
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Inservice Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
- (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement
---"---'--------,:;>""'-------Expiration Date --=O'-"'c::..t=o"'b'""'e"'r=---=3'-",'--=1"'9'-'9"-1=-------
,tftj . 19-fr CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of _ New Jersey and employed by Lumbermans Mutual Casualty Co. of
__L_o_n_g,,__G_r_o_v_e_,_,_I_L~.--------------.--:::-,,.---::--:"'7"---7~aJ...)niercted the components described in this Owner's Report during the period _ _ _ _ _ _ ___,_--"--""--"-/,'--- j 70 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date._~6~~-/_f _ _ _19 rr I
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date ___N_o_v_e_m_b_e_r_2_5_,_1_9_8_8_ _ _ _ __
Name Foot of Buttonwood Rd., Hancocks Bridge,NJ Sheet __l_ _ _ of _ _ _l_ _ _ _ _ _ _ _ __ Address 2 . Plant Salem Nuclear Generating Station Unit ____ l _ _ _ _ _ _ _ _ _ _ _ _ _ __ Name Foot of Buttonwood Rd., Hancocks Bridge,NJ Code Job Package #S-88-158 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by Public Service Electric & Gas Type Code Symbol Stamp ___N_R_ _ _ _ _ _ __
Name Authorization No. _ _ _ _3_6_ _ _ _ _ _ _ __ Foot of Buttonwood Rd. , Hancocks Bridge, NJ Expiration Date October 3, 1991 Address
- 4. Identification of System _ _ _R_C _ _('-R_e_a_c_t_o_r__
C_o_o_l_a_n_t"""')_ _N-'u'-c"-1=-"e-'-a=r'---C=-l=a=s=s=--I=----------.,,.----
- 5. (a) Applicable Construction Code XI 19__JLl_Edition,_l-'9_8~3~_ _ _ Addenda, Summer Code CaseN/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8=-=3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) l-PS-1 Copes N/A N/A XA-10 N/A Repaired N/A Vulcan
- 7. Description of Work ____R_e-'p=--l_a_c_e_d __i_n_t_e_r_n_a_l_s_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure[] Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number .of sheets is recorded at the top of this form .
- (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
....... - WU# FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Certificate of Authorization No. 36 Expiration Date October 3, 1991 Qo~t , Signed ~, ~ Owner or Owner's Designee, Title Mt' ~~ QA Date 1).:i s . 19_~~~~ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Co. of __L_o_n_g~_G_r_o_v_e_,,,___I_L__________~~~~--------have inspected thVomponents described __~_7______ to in this Owner's Report during the period _ __,_;-'-'7_*' I ;J- ;) Y , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. National Board, State, Province, and Endorsements
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Pr.ovisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Company Date January 31, 1989 Name Foot of Buttonwood Rd, Hancocks Bridge, NJ Sheet __l _ _ _ of ___ l _ _ _ _ _ _ _ _ __
Ad~e~ 08038
- 2. Plant Salem Nuclear Generating Station Unit_l~----------------
Name I Foot of Buttonwood Rd, Hancocks Bridge, NJ Code Job Package #SS88-320 Address 08038 Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by __P_S_E_&_G_ _ _ _ _ _ _ _ _ _ _ __ Type Code Symbol Stamp_~N=R~--------
Name Authorization No. _ __,,3,._,6,,___ _ _ _ _ _ _ _ __ Foot of Buttonwood Rd, Hancocks Bridge, NJ Expiration Date October 3, 1991 Address 08038
- 4. ldentificationofSystem Residual Heat Removal (RHR) Nuclear Class II
- 5. (a) Applicable Construction Code_X~I_ _ _ _ _ 198..3_Edition,_J.._9..._..8'"'3'--_ _ _ Addenda, Summer Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19__..8,_.3,__
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) 1FE641A PSE&G Co. N/A N/A None N/A Rea pi red N/A
- 7. Description of Work Replaced studs and nuts in orifice flanges
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure N ! 0. P. psi Test Temp. N. 0. T. ° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is BY. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
- (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. re.pair or replacement Certificate of Authorization No, ____3_6___________ Expiration Date _ _O_c_t_o_b_e_r __3~,_1_9_9_1_____ Signed QQ~ Manager-Station Owner or Owner's Designee, Title QA Date _ _ __,_;-+/~~~{_* I
- - - - . 19 B?
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Co. of .......L.,.o....n..._g-_,G..,r~o...,v...,e_,_r.......r..________________________ have inspected the components described in this Owner's Report during the period _ _-L/__,('-----_,,:9:::;__,_Z_-__.Fe.'___ --_r to ;Y-1 ~ - n . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this
/VJ-7 OL / ---,<r-----....,..---::7""-+-.-::-:-----------Commissions _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
National Board, State, Province, and Endorsements
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date August 22, 1989 Name Foot of Buttonwood Rd. ,Hancocks Bridge.NJ Sheet _ _ _ _ of_....__ _ _ _ _ _ _ _ _ __
Addrea
- 2. Plant Salem Nuclear Generating Station Unit-"'------------------
N*me Foot of Buttonwood Rd.,Hancocks Bridge,NJ Addr- Res>*lr Org*nintion P.O. No., Job No., *tc.
- 3. Work Performed by _ _P~S.-E-....&""'G~--------- Type Code Symbol Stamp _ _ _ _N--R....__ _ _ __
N*m* Authorization No. _ _ _ _ _ _3;;;;..;:6_ _ _ _ __ Foot bf Buttonwood Rd.,Hancocks Bridge,NJ Expiration D1te _____o__c""t'""o...b""e=r---3_.,_....1""9:;..9::;..:l_ _
- 5. (a) Applicable Construction Code Bl6
- 5 19~ Edition,_N_._/A;;.;;;..._ _ _ _ Addenda,_N~/=A_ _ _ _ Cod1 c..
lbl Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. ldentificirtion of Components Repaired or Replaced and Replacement Components ASME Code Nation el Rep1ired, Stamped Name of N111T1e of ManuflctUl"lr Board Other Ynr RepllCld, (Yet Component Manufacturer Seri1I No. No. Identification Built or Replecement or Nol Valve 11SW25 ITT Grinnel NIA NIA NIA ~1 Q7? Ron:iir"'n /"/J,
- 1\T
- 7. Dtteriptlon of.Work_--'R=e..,.p...l..,a....c=e..,d.....,.v...a...1.,,y......,e.......,b,..o..,n..,.wn...e...t_1._*n...__..k_.j._.n...d....__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 8. Tests Conducted: Hydrostetlc 0 Pneumirtic 0 Nomin1I Opereting Pr1aure 0 Visual Leak Examination*
Other 0 Preuura psi Test Temp. °F NOTE: Supplementll sheets in form of llltl, sketcha,. or drawinga mmy be used, provided (1 l size is 8~ in. x 11 in., 121 informe* tion in itm 1 t!'trough 8 on this repon ii included on Mich sheet, end (31 11Ch shftt is numbered and th1 num~r of sheets is recorded It the top of this form. (12/821 This Form (E00030) mey be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Backl Applicable Manufacturur's Data Reportl to b9 *ttached
.CERTIFICATE OF COMPLIANCE We certify th et the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. rep*ir or replacement
----'--'"-"'---------Expiration Date -~O~c""'t..1o~h~>:J1o:.L-~*-,...--li.;9:z,;;i9e.1l_Ff ____.,....._
Signec1_*--=~.....i.=...,,,........:::.t-::?~-:--'---:.,....,.2l:l~~i=..=__.~~~.!.!.!.~:o....,. Date ..El.!:...J ,19 _ _ __ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, hol_ding a valid commission iaued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by_ Lumbermens Mutual Casua 1 t¥ Campany of Long Grove, IL have i":'fted the components described in this Owner's Report during the period _ _ _ _._._ _,./_-_./}_,'O.._,..,_..J:f"-1---to 1- 2/"' . , and state that
. to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certifiatl neither the Inspector nor his employer makes any Warranty, expr-d or implied, concerning the examinations and corrective me.Ur* described in this Owner's Report. Furthermore, neither the Inspector nor his employer shell be liable in any man11t1r for any personal lniury or property damage or a loss of any kind arising from or connected with this ____a_,.~*1*"~1 1'-<--~=0:-.:;,.1*;_8_.~('" 'n-:. . ' ~~;....=.* in1P9ction.
~
-* ,. **w
... ___ eommission1.....;rJ_j""'.::..-""'3___:....'7~J----------
Natlon*I Bo*rCI, State, Province, *nd EndorMments .. Date CZ-M 19?9
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date August 8, 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet 1 of 1 Address
- 2. Plant Salem Nuclear Generating Stat.ion Unit #1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-017 Address Repair Organization P.O. No., Job No., ate.
- 3. Work Performed by _ _P_S_E_&_G_ _ _ _ _ _ _ _ _ _ __ Type Code Symbol Stamp ____N_R_ _ _ _ _ __
Name Authorization No. _ _ _ _ _ _3_6 _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date _ _O_c_t_o_b_e_r_3_,_1_9_9_1_ _ __ Address
- 4. Identification of System Safety Injection (SI) Nuclear Class II
- 5. (a) Applicable Construction Code _ _ _X_I_ _ _ _ 19~Edition, 1983 S Addenda,_N_,/_A _ _ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components
- Name of Component Name of Manufacturer Manufacturer Serial No.
National Board No. Other Identification Year Built Repaired, Replaced, or Replacement or No) ASME Code Stamped (Yes Valve 12SJ45 N/A N/A N/A None N/A Repair N/A
- 7. Description of work Added break flanges in leak off line and replaced studs and nuts on bonnet.
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure 0 Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8¥.. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement
..,,;;..3_6
_ _ _ _ _ _ _ _ _ _ _ _ Expiration Date _--.:.O:....:c_t_o:....b--.:.e_r_3:.....!...,.,,,._l:....:9:....:9:....1=---- ifr. 195 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL ha~n~ecte);I _;tie components described in this Owner's Report during the period _ _~_:::;;J-:..__-...:.t"._J""----.--_P_,_!__ to _ _ _,,.£_'---'-7 __--;r_-"-7____ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with .this inspection.
,!J4' ?./-6J- rvT& /y /l//
'National Board, State, Province, and Endorsements Date. _ _ _ _-___;.y____19,_Y_,_f_
§-:....*
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 . Owner Public Service Electric & Gas Co.
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ _1_ _ of _ _ _ 1 _ _ _ _ _ _ _ _ __ Address
- 2. Plant _ Salem
____ Nuclear _____ Generating _ _ _ _ _ _Station_ _ _ _ __ Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-019 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by __P_S_E_&_G_____________ NR Type Code Symbol StamP--~--------
36 Authorization No. -,,___,_ _ _. . ,,,....-~~~---- Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ 0ctober Expiration Date _ _ _ _ _ _ _ 3,_1991 Address
- 4. Identification of System _ _ Main
___ Steam _ _ _ (MS) ____ Nuclear _____ Class _ _ _I_ I _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 5. (al Applicable Construction Code Sect* III 19~ Edition, N/A Addenda, _ _N_/_A___ Code Case (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components
- Name of Component Name of Manufacturer Manufacturer Serial No.
National Board No. Other Identification Year Built Repaired, Replaced, ASME Code Stamped (Yes or Replacement or Nol 14MS10 Valve Masoneilan N/A N/A None N/A Repaired N/A
- 7. De~riptionofWork _ _R_e_p_a_i_r_e_d_g_a_s_k_e_t __s_e_a_t_i_*_n~g_s_u_r_f_a_c_e__b~y_w_e_l_d_i_n_g~*------------
- 8. Tests Conducted: Hydrostatic D Pneun;iatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure ff() psi Test Temp. .-5 3 2= °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is SY.. in. x 11 in., (21 informa-tion in items 1 through 6 on this report is included on each sheet, and (3l each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the repo~ are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL have i~cted _;.~components described
- Z f' , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date_ _ ""-[f_-_7____19 rf(
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date August 31, 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet 1 of 1 Address
- 2. Plant Salem Nuclear Generating Station Unit #1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-027 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by __P_S_E_&_G_C_o_.- - - - - - - - - - Type Code Symbol Stamp _ _ _N_R_______
Name Authorization No. ------:--3_6_______ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October *3, 1991 Address
~ ldentificationofSynem _ _C_h_e_m_i_c_a_l __V_o_l_u_m_e_C_o_n_t_r_o_l________~~~U~C--_~~-----------
Draft
- 5. (a) Applicable Construction Code Pump Valve 19~Edition, __N_,_/_A____ Addenda, __N...:./_A ____ Code Case (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19 _ __
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve Rockwell 1CV386 Edwards N/A N/A None N/A Replaced N/A
- 7. Description of Work Replaced valve in kind.
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8¥.i in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the "statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section XI. repair or replacement _3_6____________ Expiration Date --'O=-c==t"'o:..::°'::J_:;.;e~r=-1-.:::3c..1--'l=-9~9_,,l,_____ Signed..IL..-=.._.....::;~--~--M_a.:.;;.;;_;n"'a'""'"'e°"'r~----=S=-t=-a=-=t=i:...:o:..:n:.:__..e..::.;A=----Date 'if/3u ,19 8j CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL i~nspected the components described in this Owner's Report during the period _ _ _ _ _ _ _._,,2,,.~1-f--rtr"""'----to /.- fl , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer. shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
-----+(}~*""""'---
~Signature
- /[:~,--=L~-'--~------Commissions_A{J.--""'. "--'-}--'-J3 _ *- - - - -
National Board, State, Province, and Endorsements Date_ _ _ _ 9._-_7._____1 9 "
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner _Public
_ _ _ _ Service _ _ _ _ _Electric ______ &_ _ _Co. Gas __ Date _ _J_u_n_e __2_1~---1_9~8~9~-------- Name Foot of Buttonwood Rd. ,Hancocks Bridge,NJ Sheet_-=l=--__ of _ ____.,l'----------- Address
- 2. Plant Salem Nuclear Generating Station Unit # 1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package # 589-082 Address Repair Organization P.O. No., Job No,, ate.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp~N=R~--------
Name Authorization No._3=6_ _ _ _ _ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Main Steam (MS ) Nuclear Class - 2
- 5. (a) Applicable Construction Code_I~I~I_ _ _ _ _ 19---1.l_ Edition,~N~/-A~---- Addenda,__..N..,./""A...__ _ _ _ Code Case (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19_,,8"'3'---
- 6. Identification of Components Repaired or Replaced and Replacement Components
- ASME Code National Repaired, Stamped Name of Name of Manufacturer . Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) 13GB4 Masonelian N/A N/A N/A 37-2X871 Repair NIA
- 7. Description of Work Installed new stem, plug and seats in kind
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other~ Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _* F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement
--~"-----------Expiration Date _..::O~c:::..t=oo.::b~e::.:r=--==3'---"'1""9:..:9:::..1::....._ _ __
1Ai- ,,9f5 __ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Lon Grove, IL ha e inspected the components described in this Owner's Report during the period 76ZC -fr to , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or impl_ied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. _ _ _Q---1-6'-~~o~!.L/---=~'--'-""C.,:Qi~~--commissions_/'--V...:;_J,-'0.-J...:...1_'.3_ _ _ _ _ _ __ T lf(sp;c;:o;::, Signet~ National Board, State, Province, and Endorsements oate._ _ _-=(g_-....:..2-...:::Jc____ _ 1sF'f i
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 . Owner Public Service Electric & Gas Co. Date June 19, 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_=l_ _ _ of 1 Address
~ ~a~ Salem Nuclear Generating Station Unit--'.__,l~--------------~
Name Foot of Buttonwood Rd.,Hancocks Bridge, NJ Code Job Package i 889-086 Address Repair Organization P.O. No., Job No,, etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_N_R_ _ _ _ _ _ _ __
Name Authorization No. - " 3 - ' 6 ' - - - - - - - - - - - - - Foot of Butt.onwood Rd. ,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Main Steam (MS) Nuclear Class II
- 5. (a) Applicable Construction Code B31. 7 19~Edition,..=l..;;;9...:6;....:9'--_ _ _ Addenda,_.N,,_/'-"'A=-_ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3_ __
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Valve 14GB4 Masoneilan ilDOBD-1-4 NIA Nnne NIA Reoaired NIA
- 1. DescriptionofWork Replac_ea hndy to hnnnet stnds and nnts in kind
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other G Pressure _ _ _ _ _ psi TestTemp. _ _ _ _ _°F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1 l size is 8% in. x 11 in., (2) informa*
tion in items 1 thro\,lgh 6 on this report is included on each sheet, and (3) each sheet is numbered and the numl:!er of sheets is recorded at the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement
-~""""'-----------Expiration Date _,O""c"'-t=o'-"'b""e""r.__"'3..i,__.1""'9"-9=1'------
Signed--=-1L..........:::~....:...~~::=--:¥.µ.......=.w...i..&l..l....r...!.UA...~""-----Date _____ ____, 19_fJ.;.....<.-- C,_,_.O_bU CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove' IL h
- s ected the components described to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector r:ior his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
----~~2=!~~=-..L~..:*~~- ,~!:.::::::._/_Co~missions A/(J31.J National Board, State, Province, and Endorsements Date._ _ __.B~/_t...__f_1£/._
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date June 19 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ __,l~ __ of_..___ _ _ _ _ _ _ _ _ __
Address
- 2. Plant Salem Nuclear Generating Station Unit_......__~l~---------------
Name Foot of Buttonwood Rd.,Hancocks Bridqe,NJ Code Job Package f S89-087 Address Repair Organization P.O. No., Job No,, etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp~N=R~--------
Name Authorization No. _3~6~---------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. ldentificationofSystem Main Steam (MS) Nuclear Class I I C1lf 71 N/11
- 5. (a) A~plicable Construction Code -BJl. 7 ~<;:\\~* 19 9- Edition, ~d5'D~ Addenda,_N._../~A~_ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve 12GB4 M::q:::nnPi 1 rin N00130-l-J N/A None N/A Repaired N/A
- 7. Description of Work Replaced body to bonnet studs and nuts in kind
- 8. Tests Conducted: Hydrostatic 0 Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other [1j: Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repaj r conforms to the rules of the ASME Code, Section XI. repair or replacement
-"""'~-----------Expiration Date October 3, 1991 Signed _ _ .m..41-~~l.<'.-----M---=g:..:r:...*:...--=.S...:t:..:a.:..t:..:1=-*o.:..::..:n:........!Q=:A:.::...._ _ _ _ oate _ _ _ _ _ _6.--'-/J-~____,19 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL have )~~ected the components described in this Owner's Report during the period _ _ _ _ _ _lfL'..::-=-"2..cf'.,__-_q""-'i-1--to ?- f:o'l , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
---=r(}'b'-~"'-"'J==---....;;...(_.
F'inlP8Ctor1 Signature
~.......__"
_ _ _ Commissions_.:...;,;J,:.....:::..j-'0-}-=---13_ _ _ _ __ National Board, State, Province, and Endorsements Date_ _ --=-&_*-_t_Z--__19 f"f
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co.
Name Foot of Buttonwood Road, Hancocks Bridge, NJ Sheet_~l_ _ of_~l..__ _ _ _ _ _ _ _ __ Address
- 2. ~a~ Salem Nuclear Generating Station Unit.....__~l,._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Name Foot of Buttonwood Road, Hancocks Bridge, NJ Code Job Package i 889-088 Address Repair Organization P.O. No., Job No=, etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_~N~R~-------
Name Authorization No.~<-=------------ Foot of Buttonwood Road,Hancocks Bridge,NJ Expiration Date October 3, 199] Address
- 4. Identification of System Main Steam (MS) Nuclear Class II
- rn: 7/
- 5. (a) Applicable Construction Code B31. 7 ~~ 19~Edition, *9£-9= Al/A Addenda, ...N""'/._A
_ _ _ _ _ Code Case (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME
- Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) 13GB4 Valve Masone'ilan N00130-l-R NIA Nnne NIA Reoaired NIA
- 7. Description of Work Replaced body to bonnet studs and nuts in kind B. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure Ovisual Leak Examination Other [] Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and thisRepair conforms to the rules of the ASME Code, Section XI. repair or replacement
-"""'"-------------l;xpiration Date ~O.!.!c...t,,,,,,o,,..b.!.!e=:.r=-_,,3<..L..,....=1""9~9<!..l~-----
( jus> 1sM CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boile.r and Pressure Vessel Inspectors and the State or Province of New Jersey and emplo.,,ed by I.umbermens Mutua 1 Casua 1 ty Company of G ve IL have Jrected the components described
-Y, , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expres5ed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
----'fJ~. ~~~(.__,~~--Commissions_M--=-.J_.3_?3
/i;;;pectC)T' ; Slgna~ _ _ _ _ __
National Board, State, Province, and Endorsements Date t---22 1sf'f
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Company Date _ _J,,_,,,u"'l,,.y,__l~4..,.,__1~9~B~9,___ _ _ _ _ _ __
Name Foot of Buttonwood Rd. ,Hancocks Bridge.NJ Sheet _ _ _ _ of_~----------..:.. Address
- 2. P~nt Salem Nuclear Generating Station Name Unit--'......---------------~
Foot of Buttonwood Rd.,Hancocks Bridge.NJ Addrea
- 3. Work Performed by __P_S_E_&_G_ _ _..,.,.._ _ _ _ _ _ __ Type Code Symbol Stamp_--"N""'R"---------
Nam* Authorization No. _____3~6_ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date Oct. 3, 1991 Address
- 4. Identification of System _c_h_e_m_i_c_a_l_V_o_l_u_m_e_C_o_n_t_r_o_l_ _N_u_.__ C_l_._2_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 5. (al Applicable Construction Code B31. 7 19~Edition, 1969 Addenda, Winter Code Case NA (bl Applicable Edition of Section. XI Utilized for Repairs or Replacements 19_8_3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Ye1 Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Valve l-CV-302 Grinnel N-2 NA NA 197~ "Dor.~ i .,..,,:i lo.Tl!.
- 7. Description of Work Replaced missing nut in kind.
- 8. Te1ts Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pres1ure 0 Visuiil Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp, _ _ _ _ _°F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1 I size i1 8% in. x 11 in~. (21 informa-tion in items 1 through 6 on this report i1 included on each sheet, and 131 eech sheet is numbered and the number of sheets is recorded at the top of this form.
(12/821 This Form (E000301 may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufa_cturer's Data Reports to be anached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Certificate of Authorization No. _ 3_6_ _ _ _ _ _ _ _ _ _ _ _ _ _ Expiration Date _ _.::0;.:C:..t=-'-"--'3"-L,__,l,,_9"""9:...,1~------ Manager-Sta tion QA Signed~-ll'O!>..d:liu:....__~-------~-----=-='---':;;.:'----Date _ _ _ _ _......1.~~-=--~..L-----. 19~ 7 h '-/ c-< CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National* Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL h::: ipj?;c~ ,.ihe components described in this Owner's Report during the period _ _~_9.L..._*_.;;.d----'f='--_~_f'_9' ___ to, ___...tL__ _,_'L___ __:_ :..7_____ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date,_ _--'<-[j_' --...L7____ 19,_,f--'f'---
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date August 7, 1989 Name Foot of Buttonwood Road, Hancocks Bridge, NJ Sheet 1 of _ _ _ _ _ _ _ _ _ _ _ __
Address
- 2. Plant __S=a:.::l:..:e:..:m.:.:.....;;..;Nc::u:..:c:..:l=-e=ac::r'--'G7-:e=nc.::ec::r:..:a=-t=-1=*=..:nc:;g.__,S=-t=-a=-=to.:i:..:o:.:n:=..-_ Unit _ __.._,,l~-------------~
Name Foot of Buttonwood Road,Hancocks Bridge,NJ Code Job package #S-89-096 Address Repair Organization P.O. No., Job No., etc. NR
- 3. Work Performed by __ P"'S"'E""&"""G"--_ ___,..,----------- Type Code Symbol Stamp _ _ _.....,.._ _ _ _ _ __
Name Authorization No. _ _ _ _ _ _ _ _ _ _ _ _ __ Foot of Buttonwood Road,Hancocks Bridge.NJ Expiration Date October 3. 1991 Address
- 4. Identification of System Main Steam ( M. S. )
- 5. (a) Applicable Construction Code Section III19....2.5__Edition,_~1~9~6~6~_ _ Addenda, _ _.N,..l.....Au..-_ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19__.._8.._3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
#11 Steam Generatcr Westinahm se 1003 hR-10 N/A 19f>R Repaired y
- 7. Description of Work Replaced ( 3) bolts in secondary manway.
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure ~Visual Leak Examination Other 0 Pressure JI t/ 0 psi Test Temp. 5'"3 I °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the tOP of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement 36 xpiration Date ___O_c_t_o_b_e_r_..,.3~,_1_9_9_1____
?/Y.1J2 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Co. of Long Grove, IL ha'j-i~spe~~e components !::lescribed in this Owner's Report during the period ____0~-*""? __Y'_-_f"'_,_?___ to L , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date 6""- 1
------------- 19,P-'f
- FORM NIS-2 OWNEfrS REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date _ _,J""'u""n...,,,e'"-"'1~9'"-',......__.l......_9_,,.8'""'9'----------
Name Foot of Buttonwood Rd.,Hancocks Bridge.NJ Sheet_...__ _ o f - - ' - - - - - ' - - - - - - - - Address
- 2. Plant Salem Nuclear Generating Station Unit......:1~.L....-~------------~
Name
- Foot of Buttonwood Rd.,Hancocks Bridge.NJ Cade Joh Package i $89-099 Address Repair Organization P.O. No., Job No=* etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_N=R=----------
Name Authorization No.-"3'""6~---------- Foot of Buttonwood Rd.,Hancocks Bridge, NJ Expiration Date October 3, 1991 Address 0
- 4. Identification of System _ _ S_a_f_e_t_y..__I..;;;n'-'J.._e;;;...;;;.c..;;;t"'i""o'-"n"'--"N'-"u:..;c:..;l;;;.e=a;::r'--C:::.l=a;::s:..:s=-----=2'-----------------
- 5. (a} Applicable Construction Code B31. 7 , 1s......§.2_Edition, 1969 Addenda, Winter Code Case N/A (bl Applicable Edition of Section XI Utilized for 'Repairs or Replacements 19._,8=<-3=<---
- 6. ldentJfication of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) 1SJ906 Rockwell N/A N/A FA127 N/A Replaced N/A 1SJ907 Rockwell N/A N/A FA127 N/A Replaced N/A 1.c;,T90h Yarwav B8733 N/A FA130 N/A N/A N/A 1 ~.T907 Yarwav B9258 N/A FA130 N/A N/A N/A
- 7. Desi:ription of Work Replaced valve 1SJ906, 1SJ907 type FAl27 with FA-130
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F
. NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1 I size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the numb~r of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacement conforms to the rules of the ASME Code, Section XI. repair or replacement ___3_6_ _ _ _ _ _ _ _ _ _ Expiration Date _,O""'c"-t"'-"'o,.,b""e""'r"--,,,.3.i,__.1"""'9,,_9µ1~---- Signed_...J<~~!!:::...li...L....,>i~-----=-M=...gO!...:r:....:..---=S:....:t:..:a=-t=i..::o:.:.n:.......::s;;A:..::..__ _ _ _ Date _ _ _ _ _ _ _ _ _ ~-s.-~-- 19 fj CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed byLumbermens Mutual Casualty Company of Long Grove' IL have in~ected the components described in this Owner's Report during the period r- J -rr to C- <0~0:::-7 . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector ~or his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
-~(}-'t:::la'"-""" ~~----_/--={:.:...,_*___;;!J_=----_ _ Commissions-=-/!i-"'<-~_....J'-!....?~J------
f if;sp~tor'~gneture National Board, State, Province, and Endorsements 7-LtJ Date_ _ _ _~_ _ _ _ _ _1sfl_/ ra
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service electric & Gas Co. Date _ _August
_____ 9,_ _1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ _1 _ _ _ of _ _1_ _ _ _ _ _ _ _ _ _ __ Address
- 2. Plant Salem Nuclear Generating Station Name Foot of buttonwood Rd. , Hancocks Bridge,NJ Code Job Package #S-89-100 Address Repair Organization P.O. No., Job No., etc.
- 3. WorkPerlormedby _ _ _ PSE&G
_ _ _ ____,_ _ _ _ _ _ _ _ __ NR Type Code Symbol Stamp _ _ _~~------ Name 6 Authorization No.--=--,.-..,..--,......-~~~- Foot of Buttonwood Rd.,Hancocks Bridge,NJ _ _ _ _ _3, Expiration Date _ _ _October _ _1991 Address
- 4. Identification of System _ _ _Reactor
_ _ _ _ _Vent_ _ _Inst._ _ _ _Tube ____ Nuclear _____ Class ____ II_ _ _ _ _ _ _ _ _ _ __
- 5. (a) Applicable Construction Code B31. 7 19 ___6 7 Edition, _N/A
_ _ _ _ _ _ Addenda, _ _ N/A_ _ _ _ _ Code Case 8 (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19__ _ __3
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) 840-lA Tube#
6527XD PSE&G Co. N/A N/A None N/A Repaired N/A
- 7. Description of work _ _R_e~p=--a_i_r_e_d_..=.p_i_n_h_o_l_d_1_*n
__t_u_b_1_*_n""'g'---b~y.___w_e_l_d_i_n_,,g'-.--------------
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 811. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. ' repair or replacement _3.;;..;;;6_ _ _ _ _ _ _ _ _ _ _ _ Expiration Date _ __,O"-'C=-t=oc:b:..::e""'r"---.:::3_.,___,l=-9=9-=l,___ __ Signed_~~~'-'--="F-...,.-.,,...--,----.::,;Mo.;:a:..:n.::.a=..;;ic:e:..:r::..--=S--=t:..:a=-t=ic:o:..:n=-.i=A=-----Date.------'~=-..:.......:... _ _ _ _ , 19 __57_-__ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL have inspected 1-,e components described in this Owner's Report during the period ___ 5=_-_:_/_._.:::N_,__
... ___ to /t --/O ,..-- ! , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. National Board, State, Province, and Endorsements
!:- //J Date,_ _~(l_'--_ _ _ _ _ _ _19 0 e--c(
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section. XI
- 1. Ovvner Public Service Electric & Gas Company Date __J_u_l~y,___1_8~,_1_9_8_9_ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd. , Hancocks Bridge, NJ. Sheet_l;;;;....__ _ of 1 Addreu ---=~---------~ 2* Plant Salem Nuclear Generating Station Unit #1 Name Foot of Buttonwood Rd.,Hancock~ Bridge,NJ Code Job Package #S-89-108 Addreu Repair Organization P.O. No., Job No., ~tc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_......,N..._R.___ _ _ _ _ __
Name Authorization No.----~~-------- Foot of Buttonwood Rd.,Hancockd,Bridge,NJ Expiration Date October 3, 1991 Addr-
- 4. Identification of System __C_h_e_m_i_c_a_l_V_o-'l""u""m~e--'C:;...o::.;n=-::t:.::r:...::o:;.:l=--_,_(-=C'-'V-'C:::...L..)_ ...N,_,u:..:c"'l=e.,.a..,,r'--'C"'""'l""'a"'s..s..__...
r ...r~-------
- 5. (a) Applicable Construction Code_I_I""I'--_ _ _ _ 19.....§2-Edition,-=l-"'9-"6'""'6...__ _ _ Addenda, Summer Cod*Caw (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yet Component Manufacturer Serial No. No. Identification Built or Replacement or Nol 11BR151 Grinnell N/A N/A None N/A Repaired N/A
. 7. Description of Work __R_e_p_l_a_-c_e_d_s_t_u_d_s_i_*n__ v_a_l_v_e __b_o_n_n_e_t_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 8. Tests Conducted: Hydr0static 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other~ Pressure _ _ _ _ _ psi TestTemp, °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1 I size is BY.a in. x 11 in., (2) informa-tion in items 1 through 6 on this report ii included on eech sheet, and (3) e.i:h sheet is numbered and the number of sheets is recorded at the top of this form.
(12/821 This Form (E000301 may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair confomns to the rules of the ASME Code, Section XI. repair or replacement Type Code Symbol Stamp _ _ NR_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ 36 October 3, 1991
~"""---------------Expiration Date _ _ _ _ _~----------
Signed _ _ _ _-,c..._ _ _ _ _ _ _ Manager-Station _ _ _ _ _ _ _ _ _QA "')~;i> _ _ _ Oate _ _ _ _ _ _ _ _ _ _ _ _ , 19 " / ~ CERTIFICATE OF INSERVICE INSPECTION I, the undersigneq_~holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State
. f t~ew Jersey d db Lumbermens Mutual Casualty Company f or Prov1nce o an emp 1oye y o Long Grove, IL
=--,,.........,... ______ have inspected the components described in this Owner's Report during the period _ __._,""' __
c-_3=-_-__f'_C('---_-to cf- /O -- rf , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. (}
-------~--,-1 n-~.,..,-'~'l.o=~""*""~"""*~""n...,~"'~"'~--------Commissions .fl{1ofn:?a:~ta:::r?:nc::::End:.::!ent~
!?-;;_'/() P-C}
Data _ _ __.:_0_______19 0 f
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Company Date July 18, 1989 '
- Name Foot of Buttonwood Rd. ,Hancocks Bridge.NJ. Sheet of _ _~----------
Addrea
- 2. Plant Salem Nuclear Generating Station Unit--#-'----------------
- Name
.~ ' . ~ :
Foot of Buttonwood Rd*. ,Hancocks Bridge;NJ Code Job Pask~~e #S-89-118 Addrea
- 3. Work Performed by _ _PSE&G _ _ _ _ _ _ _ _ _ _ _ _ _ __ Type Code Symbol Stamp _ _-"'N..._R,___ _ _ _ __
Nam* Authorization No. -----~3:..:6;:.__ _ _ _ _ __ Foot of Buttonwood Rd ** Hancocks ,Bridge,NJ ExpirationDate Oct. 3, 1991 Addrea
- 4. Identification of System _ _R_e_a_c_t_o_r_C_o_o_l_a_n_t_...:(_R_C--'-)---=N"-'u::..::..*.....::C::::l""'.,__"'l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
AS~E Draft
- 5. (al Applicable Construction Code Va ve & Pump19__§JLEdition, _ _N~A...____ Addenda, ___Ji....rn~---Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19,_""'8.,,3,____
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME
- Code National Repaired, Stamped Name of Name of Manufacturer Boerd Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Valve l-PS-4 Ke rote st 6-PSW-225 NA NA NA Repair NA
- 7. Description of work Replaced valve bonnet and stem in kind.
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Preuure 0 Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _* F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided. (11 size is 8% in. x 11 in., (2) informa*
tion in items., through 6 on this report ii included on eech sheet, and (3) eKh sheet is n.umbered and the number of sheets is recorded at the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement 36 3
- - - - - - - - - - - - - - - E x p i r a t i o n Date _o_c_t_._--..!.,---=l=-9=-=-971:......______
Signed _ _ _a::...=.._g.=.:___-...i~----M-a_n_a...:g_e_r_-_s_t_a_t_i_o_n_.=Q_A_Date _______ __--* 19 _YJ-=--
/-<--.c..£ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holdinJa valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New ersey and employed by Lurnberme.ns Mutual Casualty Company of Long Grove IL
' ,have~spected the components described in this Owner's Report during the period S:l)-l{y to ~Z /if 6 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ___(}-+-'=,'-' 1
=="'=-/~(~,-~~___;....,_-*___ Commissions~r/{_:'0::.........--=J:.._J!..:~:__
~ector'1 Slgnmture N11tlon11I Boud, State, Province, *nd Endorsements Date._ _ __,f:<---,r.::...l,...;..z,_ _ _
- 1so=1
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
. 1 . Owner Public Service Electric & Gas Co.
Name Foot of Buttonwood Rd. ,Hancocks Bridge,NJ Sheet 1 of_------------~- AddreS!l Salem Nuclear Generating Station
- 2. Plant---------------~-"--~~=.:"---
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Address Repair Organization ~.O. No., Job No,, etc.
'3. Work Performed by PSE&G Company Type Code Symbol Stamp~N=R~--------
Name Authorizatlon No. _.,,3""6'------------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3 , 1991 Address
- 4. Identification of System Reactor Coolant (RC) Nuclear Class I
- 5. (a) Applicable Construction Code ASME III 19..1.LEdition,__,N=-/._.A.___ _ _ Addenda,_.N.,/""'A"'------Code Caw (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19~8~3~-
- 6. Identification.of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve lPRl Cones Vulcar. 95QQ1-16L -2 NIA Nnn<> N/A Repaired N/A
- 7. Description of Work Rep} aced* nuts on studs in kind after inspection
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other Ci] Pressure _ _ _ _ _ psi Test Temp. ______* F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8~ in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is
- recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacament Certificate o ..,....-3~6_ _ _ _ _ _ _ _ _ _ _ Expiration Date __ O_c_t_o_b_e.,.r_3_,_,_1_9_9_1_ _ _ _-1 Signed _ ___,"'-_-"'-_ _ _ _ _ M_.__r_._-_s_t_a_t_i_o_n~Q=-A_ _ _ _ Date _ _ _ _ _ _ b...:/_u_,___, 19tf7 ____ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Lon Grove, IL have )~ected the components described _z,,,Tr , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, SeC:tion XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or imr;ilied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any menner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection; *
----'a.~~-==---"'-~-'
/ln;p;cto'l* Slgnmture
~----Commissions--ltf!~J:o:<,_-.:_) 1;__5_ _ _ _ __
Nadonal Board, State, Province, and Endorsements Date,_ _ _ __;_7_.-_/_f_c___19 f?
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date ----'A=u'-"gc..::u:.:s:...ct=--l=O-'-,--=l:..:9:...c8:...c9=---------
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_-=l'-- of 1 Address
- 2. Plant Salem Nuclear Generating Station Unit _ _ : # c . . . : l = - - - - - - - - - - - - - - - - -
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-120 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by _ _P_S_E_&_G _ _ _ _ _ _ _ _ _ _ _ __ Type Code Symbol Stamp _ _ _...:N::.R::..:..__ _ _ _ __
Name Authorization No. _ _ _ _ _ _.=3...:6:...__ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date ---=O...:c:...ct::..o::..b~e-=r'---'3~,--=1:..:9;...;9:...cl=----- Address
- 4. Identification ofSystem_--=.~::..!a::..1=*~n~S:...ct::..e::..a~m~(~M~S~)--=-N~u::..c::..l~e-=a:.:r~C~l-=a:..:s:..:s~=I-------------~----
- 5. (a) Applicable Construction Code Sect. III 19~Edition, Winter Addenda,_--=.N:.L/-=A.;;:.__ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8=-=.3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
#12 vestinghouse Steam Generat or 1022 68-08 NIA NIA Reoaired y
- 7. Description of Work. _ _"'R""e""p""'l"'a=c-=ec::d:.....:b::..o=l-=t'-=s'--'1'°'*n=--"k==i°"n""d=..=.*-----------------------
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure O Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8'1.i in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached Bolt #11 Cold Leg Bolt #12 Cold Leg Bolt #6 - Hot Leg CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement
- - - - - - - - - - - - - - E x p i r a t i o n Date _ _ O_c_t_o_b_e_r--=_3~,_1_9_9_1_____
Signed Manager-Station QA Date <[(/1/ 19 Pf CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of _L_o_n_g_G_r_o_v_e_,__I_L______________=o;:;;:-,.-:;;-------::.-hav~ected the components described in this Owner's Report during the period _ _ _ _ _ __.llL-_.._L-"~'--- -2 , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this* Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures .dE!Scribed in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property. damage or a loss of any kind arising from or connected with this inspection. _ _f(}-+-'~~/-~-~~* iflSP<<tOrs Signet~
-=--Commissions--=M-=->::f~J'---/3 _ _- - - - : - : : : - - : - - -
National Board, State, Province, and Endorsements Date,_ _ _ _..y:'.-_Z._;_'
.. _ / _19 ff
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date August 9, 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ _ l _ _ of ___l_ _ _ _ _ _ _ _ __
Address
- 2. Plant Salem Nuclear Generating Station Unit #1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-121 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by _ _P_S_E_&_G _ _ _~-------- Type Code Symbol Stamp ___N_R_ _ _ _ _ _ __
Name Authorization No. _ _ _ _ _3_6 _ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date ___O_c_t_o_b_e_r_3.....:...,_1_9_9_1 _ _ __ Address
- 4. Identification of System ___M_a_1_'n__S_t_e_a_m_....:(c_M_S.....:...)_N_u_c_l'-.e_a_r_C_l_a_s_s'--I-'--------------------
- 5. (a) Applicable Construction Code Sect. III 19~Edition, Winter Addenda,_N_:_/_A_ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components
- Name of Component Name of Manufacturer Manufacturer Serial No.
National Board No. Other Identification Year Built Repaired, Replaced, ASME Code Stamped (Yes or Replacement or No)
#14 N'estinghouse Steam Genera or 1203 68-51 N/A N/A Repaired y
- 7. Description of Work _ _R_e_,p'--'-'1-'-a'"'c'--'e=-d=--"'b-'oc.:l=-t;;:_:;:_s_::i=-=n=--'k=i=n=-=d=--"--(s:::..::.e.::e__;:r=-e~m=a=-=r=-=k=-s=--'--)-=-*---------------
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 811. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
- FORM NIS-2 (Back)
Applicable Manufacturer's Data Reports to be attached Bolt #13 Cold Leg Bolt #4 Hot Leg Bolt #7 - Hot Leg CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement __3_6_ _ _ _ _ _ _ _ _ _ _ _ Expiration Date ---'O=-c~t=o~b=-e=r....,...,3,,__...,_,,1""'9"-=9_,,l~--- Signed Mana er-Station A Date----=~-_._7_, 19__,,,.5 __ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of _L_o_n_g=--_G_r_o_v_e-'-,_I_L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _=-...,...__,.....,...---...,,- hav~ected the components described in this Owner's Report during the period _ _ _ _ _ _ _ _5=-*-,.-~~--'.-cr~'J~-to ',..z , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this
*~-= /_c=c~-
i-nsp-ec_t_in_n-1.,....... 0n_,_
~~ctor's Signature
. _C,A___,_
_______ commissions_li_V__,cf~J~Z..:::'J_* National Board, State, Province, and Endorsements Date
-----~-~~----
f- ;2 / 1sfl
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date _-=A;...::u:...g'"'u""s::...t.;;.._.::;l...:;0_,_,---'1::...9:....8.::....:...9_ _ _ _ _ _ __
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ ___:!~- of _ _ _l _ _ _ _ _ _ _ _ __ Address
- 2. Plant __s_a_l_e_m_N_u_c_l_e_a_r_G,...,e_n_e_r_a_t_i_*n_g_S_t_a_t_i_o_n_ _ Unit~#~!-----------------
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-123 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by _ _P-'S"--E"'"&_G_ _ _ _ _ _ _ _ _ _ __ Type Code Symbol Stamp ____ N_R_ _ _ _ _ __
Name Authorization No. 36 Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Addr.ess ~ ldemH~ationofSy~em _ ___:M;._;:a~i~n~S::...t~e~a~rn~~(M~S~)__N~u~c...:;l~e~a~r~...:;C~l....;a....;s~s~I~---------------~
- 5. (a) Applicable Construction Code Sect. III 19----22.Edition, Winter Addenda, _ _N~/~A _ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced,. (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol
#14 Westinghouso Stearn Genera1 or 1203 68-51 NIA NIA Reoaired y
- 7. Description of Work Installed helicoil in #11 bolt hole in HT/LG primary rnanway.
- 8. Tests Conducted: Hydrostatic D Pneumatic 0 Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are c~rrect and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL have
- pected the components described in this Owner's Report during the period , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in *this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. _ __::;()~*
~to;;
~-___./{."'--,-=Ck~_*_ _
Signature
- Commissions.....:....:M:...>.oo<.,f--"°-J.<--...J.J_ _ _ _ __
National Board, State, Province, and Endorsements Date. _ _ _ ~_,._)_)-'---19Yf
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner _Public
_____ Service _ _ _ _Electric ______ &_Gas_ _Co.__ Date ___A_u_g_u_s_t_9_,_1_9_8_9_ _ _ _ _ _ __ Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_1_ _ _ of ___l _ _ _ _ _ _ _ _ __ Address Salem Nuclear Generating Station Unit __#_l_ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 2. P l a n t
- _ - - - - - - - - - - . , . , , - - - - - - - - - - - -
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-124 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by _ _ PSE&G
_ _ _ _ _ _ _ _ _ _ _ _ _ __ Type Code Symbol Stamp _ _ _--:N:-R_ _ _ _ __ Name Authorization No. --:--:--:----,=-3_6-::--::-::-::---- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Exp iration Date _ _o_c_t_o_b_e_r_3_,__ 1_9_9_1_ _ __
- 5. (a) Applicable Construction Code Sect. I I I 19~Edition, Winter Addenda, __N-'/'-A_ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3__
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
#12 WestinghousE Stm. Generate r 1022 68-08 N/A N/A REpaired y
- 7. Description of work Replaced #14 bolt in kind on primary manway hot leg.
- 8. Tests Conducted: Hydrostatic 0 Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8¥.i in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement
---"-------------Expiration Date _ _,,O"'c""'t,,,.o=b'-"e=r=---~3'--'--""1""9'""9<...l=-----
Signed er-Station A rl7 Date _ _ _ _ _ _ _ _ _ __,__, 19 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL _pave -~cted the components described in this Owner's Report during the period o -/o*-n to b-.tf , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. _ _()~(To?UJ~*y/_(_~_- _ _ _ commissions_M_if'_}_7._.J_ _ _ __ F I nsP8Ctors Signature National Board, State, Province, and Endorsements Date _ _ _ f?-_-_J/_-_ 1 9 &
1-* I
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. *awner Public Service Electric & Gas Co. Date August 9, 1989 Name Foot of Buttonwood Rd. ,Hancocks Bridge,NJ Sheet_~l=--__ of_---=l~----------
Address
- 2. Plant Salem Nuclear Generating Station Unit_.JJ..:l~--------------~
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-125 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by_-=P'-'S::.:E=&_,,G,___ _ _ _ _ _ _ _ _ _ __ Type Code Symbol Stamp ___N.,.,,,R,__ _ _ _ __
Name Authorization No. _ _ _ _ __,,3,..,6.c__ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge.NJ Expiration Date _ __;O....,.Cc>t,,,o._.b"'-'e"'-"'-r~3,_..,.__... l_,.9c.:9c..l.___ __ Address
- 4. Identification of System _ __,M,_.a=i,..n._,S,,,_t..,_,,.e"'a"'m"--'-'(M"""'S'-')--'N"-u"'-"'c-=l,_,,e.,a""r"--_,.C:.:l'"'a"'s"-s~-=I~-----------------
- 5. (a) Applicable Construction Code Sect, I I I 19---6.5... Edition, Winter Addenda, _ _.N.:J.J-./A.....__ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
#11 Westinghous~!
Steam Gener ab r 1003 68-10 N/A N/A Repaired y
- 7. 1?escription of work Replaced #2 bolt in kind on primary man way cold leg.
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure O Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. *
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey arid employed by Lumbermens Mutual Casualty Company of Long Grove, IL in this Owner's Report during the period , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. __ fQ--""'-~~__,£""-'--, il1SP8CtOl"S
.=..Ck:-"'-.
Signature
-'---commissions_/1/,-"--','f.]"-.L..J_'.J_ _ _ __
National Board, State, Province, and Endorsements Date_ _ _ r;_,/;_/__19~'f
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner _Public
_ _ _ _Service _ _ _ _ _Electric ______ &_Gas_ _Co. _ ~ Date -~J...::u:::cn=..:e:::......c2=-2=--r..,-=l:...:9:....:8""'9,,___ _ _ _ _ _ __ Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_....::l=---- of _ _--=l~--------- Address 2 . Plant Salem Nuclear Generating Station Unit # 1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package # S89-133 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp _ _....,,,___ _ _ _ _ _ __
Name Authorization No.--'"'-""------------ Foot of Buttonwood Rd.,Hancocks Bridge,Nj Expiration Date October 3, J 991 Address
- 4. Identification of System Sampling System Nuclear Class - 2 ASME DRAFT PUMP & VALVE CODE 1968
- 5. (a) Applicable Construction Code 19 _ _ Edition,__.N~/.cA.___ _ _ Addenda,_N_,_/_A_ _ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components
- Name of Component Name of Manufacturer Manufacturer Serial No.
National Board No. Other Identification Year Built Repaired, Replaced, ASME Code Stamped (Yes or Replacement or Nol Valve N00243-700-4 NIA l\T /D. N /D. n~:::-~i r~.:i 1\1 /n. 11SS188 Masoneilan
- 7. Description of Work Skim cut plug seating
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1. through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement
- Certificate of Authorization No._~,_,,,__ _ _ _ _ _ _ _ _ _ _ _ Expiration Date October 3, 1991 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL ip. . ins~ec~ .t~eZcomponents described
/ a . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described.in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date____ D0- ,,.,,;tJ _________19 f ""1 I _I
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date __A_u_g_u_s_t __8_,_1_9_8_9_ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet ___1_ _ of __1_ _ _ _ _ _ _ _ _ _ __ Address
- 2. Plant _ _ Salem
_ _ _Nuclear _____ Generating
- -:------ Station
------- Unit_#_l_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd.,Hancocks Bridge1NJ Code Job Package #S-89-134 Address Repair Organization P.O. No., Job No., ate.
- 3. Work Performed by_P_S_E_&_G_ _ _ _7"7"""_ _ _ _ _ _ __ NR Type Code Symbol Stamp _ ____,,,....,,--------
Name 36 Authorization No. ---::---,---.--- ....,..-.........,,.,.,.,.....---- Foot of Buttonwood Rd.,Hancocks Bridge, NJ Expiration Date _ _ _ _ _ _ _ _3, 0ctober _ _1991 Address
- 4. Identification of System _ _ _M_a_i_*n__s_t_e_a_m __(_M_S_)__N_u_c_l_e_a_r_C_l_a_s_s__ I_I_ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 5. (a) Applicable Construction Code Sect. III 19~Edition, N/A Addenda, _ _ N_/_A_ _ _ _ Code Case (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3_ __
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve 12MS-9 Velan N2 N/A None 1973 Repaired N/A
- 7. Description of work _ _R_e'-p=--a_i_r_e_d--=g'-a_s_k_e_t_s_e_a_t_i_n....:g:___s_u_r_f_a_c_e_b...:y:__w_e_l_d_1_*n-=g_._ _ _ _ _ _ _ _ _ _ __
8, Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp, °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1 l size is 8J4. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is rec~rded at the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement NR Type Code Symbol Stamp~~~~~~--------------------------------
------:,.....,=--------Expiration Date OCtober 3' 1991 Signed_-=---ff.<.~'-=--"-..::::::"'l:::.""7'---=:-:----------Q_A _ _ Date _ _ _ _ _ _---1t/J;,.<-.,f"-6J/,__ __ , 19_%2_
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned._bolding_ a valid commission.issued by the National Board of Boiler and Pressure Vessel Inspectors and the State gr Prov11J.Ce o f New Jersey .an d emp 1ayedby Lumbermens Mutual Casualty Company o f Long Grove, IL
. _p $ h::_e,.... i=':.t1- t~ components described in this Owner's Report during the period ' L /;;l- {_ to ([__ L , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date._ _ Y_--_7____1ef-7
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS
. As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date July 24, 1989 Name Foot of Buttonwood Road,Hancocks Bridge,NJ. Sheet 1 of _ __,l~----------
Addrea ----
- 2. Plant Salem Nuclear Generating Station Unit~~l~----------------
Ne me Foot of Buttonwood Road,Hancocks Bridge,NJ Code Job Package #S-89-135 Addrea ReP*lr Or11*nlz11tlon P.O. No., Job No., etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_...N,..R..__ _ _ _ _ _ __
N*me Authorization No,---~"""""-------- Foot of Buttonwood Road,Hancocks, Bridge.NJ Expiration Date October 3. 1991 Add,_
- 4. Identification o~ System _ _R_e_a_c_t_o_r_C_o_o_l_a_n_t__S_a_rn~p~l_e_s_.y_s_t_e_rn__N_u_c_l_e_a_r__C_l_a_s_s_-_ _ 2 _ _ _ _ _ _ __
ASME Draft
- 5. (al Applicable Construction Code Pump & Valve19~Edition, N/A Addenda, _ _.::.:N._/.::.:A,___ _ Codt Case N/A (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8~3~-
- 6. Identification of Components Repaired or Replaced and Replacement Componanu ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Valve lSS-33 ~asoneilan G89456-l- 5 N/A NIA 1974 Reoair N/A
- 7. Dtscriptlon of work Replace stern, plug and bonnet nuts.
- 8. Tests Conducted: Hydrostatic 0 *Pneumatic 0 Nominal Operating Preaunt 0 Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided. (1) size is 8% in. x 11 in., (2) inform11-tion in items *1 through 6 on this r9pon Is included on each sheet, and (3) nch sheet is numbered and the number of sheets Is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.V. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement ___3_6_ _ _ _ _ _ _ _ _ _ _ Expiration Date _O_c_t_o_b_e--:r-F--'-'3--','---1..:.9...:9-=l:;;.__ _ __ Signed_'!:--~-'--Z'.'lr--:--:--:---M=*:-a,....n_a""'g'-e_r_-_s_t_a_t_i_o_n_""'Q'-A_ _ _ oate _ _ _ _ _ 7.......:fr_7/b _____ , 19 _~-- CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL have ~wected the components described in this Owner's Report during the period ,}:-(2....-J-? to t-..f'/oj , and state that to the best of my knowledge and belief, the Owner has performed 11xaminations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report, Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
-~()'--"""- h~--=-r=____.{:=.;....~Crl~_commissions--=-AJ---J-------..:37'--3-*---...,...---
rfn~lgnature National Boud, State, Province, end Endorsements oate._ _ _ -=-r_.,_3_0__19£.f *
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 . Owner Public Service Elect:ric & Gas Company Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ _ _ _ of _ _ _,.___ _ _ _ _ _ _ __
Address 2
- Plant Salem Nuclear Generating station Unit_...~~--------------~
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code .Tab Package # 889-139 Address Repair Organization ~.O. No., Job No:, etc,
- 3. Work Perfonned by __ P_S_E_&_G
__c_o_m_p_a-.,-,n_y_ _ _ _ _ _ __ Type Code Symbol Stamp _~N"'"'R~-------- Name Authorization No. ___3_6_ _ _ _ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Sample System (SS) Nuclear Class I I ASME DRAFT
- 5. (a) Applicable Construction Code PUMP & VALVE19...§.L Edition,_N~/'-A _ _ _ _ _ Addenda,~N~/~A~_ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19--"'8-=3'---
- 6. Identification of Components Repai_red or Replaced and Replacement Components
- Name of Component Name of Manufacturer
. Manufacturer Serial No.
National Board No. Other Identification Year Built Repaired, Replaced, ASME Code Stamped (Yes or Replacement or Nol Valve 11SS181 Masoneilan N-00247 .Q N/J\ None N/A Repaired N/A
- 7. Description of Work Replaced stem and plug in kind
~
B. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure Ovisual Leak Examination Other [21: Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is B~ in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Certificate of Authorization No. _ _ _...:3::..6~---------- Expiration Date --'=c===-=":r-=---.::1:..:9~9=1,_____--! Signed 1411.l/ Owne~signee, Title Mgr. -Station QA CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove,IL in this Owner's Report during the period, _ _ _..,$°---_......;/:......::),___~_1? __7'--_to to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
-----'-"~+--~~~,,,L-----Co~missions,LV#
ec:to Slgnmture 1
/JJ-G) fVT 6 /y A,; I National Board, State, Province, and Endorsements t
Date.__....:S::....--__..81__,. r__19,---1~fi--
..---.:.'?
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas co. Date June 28, 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_l=--_ _ of-,-__.._ _ _ _ _ _ _ _ _ __
Addre~
- 2. Plant Salem Nuclear Generating Station Unit__..~----------------~
Name Foot of Buttonwood Rd.,Hancocks Bridge.NJ Code Job Package # S89-141 Address Repair Org*nlzation ~.O. No., Job No,, etc.
- 3. Work Performed by PSE&G Company iype Code Symbol Stamp_.....:;N:.::R,:___ _ _ _ _ __
Name Authorization No._3_6_ _ _ _ _ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Control Air (CA) Nuclear Class II DRAFT 5.. (al Applicable Construction Code PUMP & VALVB9~Edition, ___N~/_A_ _ _ Addanda,_;;.;N._/-""A=--_ _ _ Code c8111 (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Coda National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol 11CA330 Valve Masoneilan NIA N/A Nnn<> N/A Pi:>n;:i i r<>il N/Zl.
- 7. Description of Work Replaced plug in kind
' .t
- 8. -rests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Other [] Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets *is recorded at the top of th is form.
l 12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) APPlicaole Manufacturer's Data Raports to ba attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. r*p*ir or r*plmc*m*nt Certificate of Authorization No. _ _...;3~6'-------------Expiration Date --'O""c;;;..:t:;.;o;.;b;;;..;:e;.::r=---=3'-' '--.:=l;.:;9;..;9:;..;;:l;___ __, Signed /A1/1... ~* Ownt'rorown*r'~signae, Titt* Mgr.-Station OA Date _ _ _ _ _._)....,,,_/r~/-'-f4----, 19.......,__._ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casua J ty Company of Long Grove,IL to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME. Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warrantY, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. _ _{)~;~=-<;R;z;w::..../-=~......::;'CJ.---"-=---Commissions_/lli._'J-'--37_'.J_ _ _ _ __ j=ln+~rsignmt~ N*tion*I So.rd, Stat*, Provine*, and Endorum*nt1 Date._ _ --LZ__,*-J'--"~-j'_ _1JY
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date _ _ _J_u_n_e_l_S~,_1_9_8_9 _ _ _ _ _ _ __
Name Foot of Buttonwood Rd. ,Hancocks Bridge,NJ Sheet_...:l=--__ of_ _-=l,___ _ _ _ _ _ _ __ Address
- 2. Plant Salem Nuclear Generating Station Unit # 1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package # S89-142 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_~N~R~------
Name Authorization No.--~---------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Main Steam (MS )
- 5. (a) Applicable Construction Code~I=I=I~_ _ _ _ 19--6.9._Edition,_1~9""'"""6"""9'--_ _ _ Addenda,~1~9~7~D~_ _ _ Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
#14 Steam r:!~...,,,,~,,.t-nr Westinghousi ! 1203 68-51 None h.969 R<=>n;:i i ..-~n v Handhole Coveis
- 7. Description of Work Repair indications in gasket area (Machine l B. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of l.ists, sketches, or drawings may be used, provided (1 I size is BY.. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
- (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforr:ns to the rules of the ASME Code, Section XI. repair or replacement _ _.,,...'-:,,,-----------Expiration Date __,_a..,c_t......._o...h_.e._...r_3__,_1...._.9...,9,._1.______ (' ~/". /7 19 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by. Lumbermens Mutual Casualty Co. of _L_o_n_g __G_r_o_v_e_,_I_L ___________"""_....,,,.,----.-....,.,.------* hav(i ~n~~te;{~e components described in this Owner's Report duFing the period---""'---'-....::.-.IL.-4'---to rf.... L 0 L , and state that to the best of my kn:iwledge and belief, the Owner has performed examinations and taken corrective measures descr.ibed in.this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer .shall be liable in any manner for any personal injury or property damage. or a loss of any kind arising from or connected with this inspection. oate_-¥-f_-_,_f_ _ _ 1s_r..__/_ _I
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1.
- Owner _P_u_b_l_i_c__ s_e_r_v_i_*_c_e_E_l_e_c_t_r_i_c__&_G_a_s
__C_o_._ Date ___J_u_n_e_2_1_*~,_1_9_8_9_ _ _ _ _ _ _ __ Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_l_ _ _ of _ _~l~--------- Address
- 2. Plant Salem Nuclear Generating Station Unit # 1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package # S89-147 Address Repair Organization P.O. No., Job No,, etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp _ __.....,,___ _ _ _ _ __
Name Authorization N o . - - - " ' - - - - - - - - - - - - Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, J 991 Address
- 4. Identification of System Waste Liquid Nuclear Class - 2 ASME DRAFT PUMP & VALVE CODE 1968
- 5. (a) Applicable Construction Code _ _ _ _ _ _ _ 19 _ _ Edition, _ _.N...,_/.._A.___ _ _ Addenda,_--'N""/""A _ _ _ _ Code Casa N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3~-
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve 1WL?"i8 T'TT'* r-,-; nnol 7q_i:;?nhLl 1 _, Nil\ Nil\ Nil\ Ro~~ i ~"rl NI n
- 7. DescriptionofWork Replaced bonnet diaphragm, studs, nuts
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to ba attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the repair or replacement ASME Code, Section XI. Certificate of A~utho~rizationN_o. _ _,3"-6"'------------Expiration Date _o=c'-"'t..,o..,b=e£""r~~--'3"""l.-...._2...-_.1""'9=9-=l,___F'5 Signed
- I . Mgr.-Station OA _ _ _ Date _ _ _ _ _ _ _ _ _ _ _ _ 19 o\l;f;er;: ~Designee, Title .
CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boile.r and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL have inspected the components described in this Owner's Report during the period <-LZ.. H to ,_ z..,.rt? . and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. at/'-----tZ,_,__.~~=---Commissions....:....:;,/......=;5--"'J--'-:-1)..:..___ _ _
----+-(}......._,_._,,,-.......
~flCtOrl. Signature
---=-=,- - -
National Board, State, Province, and *Endorsements Date_ _ _ _6~-~Z~; ___1s fr
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Company Date __J_u_l_y_2_5_,_1_9_8_9_ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd. ,Hancocks Bridge, NJ Sheet __1___ of _ _1_ _ _ _ _ _ _ _ __ Addreas 2 . Plant Salem Nuclear Generating Station Unit_#_l _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ N*me Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-152 Addr- Rep*lr Orv*nlz.tlon P.O. No., Job No.;*tc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp _ _N_R_ _ _ _ _ _ __
N*m* Authorization No. _ _ _ _..;3;;..6;:;.__ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration D1t11 October 3, 1991 Addr-
- 4. Identification of System Control Air Nuclear Class 2 ASME Draft
- 5. (al Applicable Construction Coda Pump & Valve19~Edition,_N_./_A _ _ _ _ Addenda, __N_/._A ______ Coda ea.
(b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19----""8"""3__
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Rep1ired, Stamped Name of Name of Manufacturer 801rd Other Ynr RepllCld, (Yes Component Manufacturer Seri1I No.. No. Identification Built or Repl1eement or Nol.
Valve ll-CA-330** Masoneilan N/A NIA NIA N/A Repaired N/A
\
- 7. D1teriptlon of Work __R_e-'p'-l_a_c_e__p_l_u_t__a_n_d_s_e_a_t_.- - - - - - - . , . . . . - - - - - - - . . . . , . . - - - - - - - - -
- 8. Teats Conducted: Hydrost1tic 0 Pneumatic 0 Nominal Operating Prwaur1 0 Visual Leak Examination Other 0 Pr9uur11 _ _ _ _ _ p1i Test Temp. *F NOTE: Supplamentll sheets In form of llltl, sketch*, or drawings m1v bl used, provided (1 I size is 8% in. x 11 ln., (2) infom111*
tion in items 1 t!'rough 6 on this report ii included on llCh sheet, and (3) nch sheet is numbered and the number of sheets i1
- recorded It the top of this form.
(12/82) This Form (E00030) m1V b11 obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10011
FORM NIS-2 (Backl Applicacle Manufacturer's Data Reports to ba ettached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are ~orrect and this Repair conforms to the rules of the ASME Code, Section XI. repeir or replacement _....:3:....6~------------Expiration Date ----"'O"'c'"'t._,o...b....,.e""'r_3..i,*-1-*-l1..9~9~J..____ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Compan¥ of Long Grove, IL in this Owner's Report during the period , and state that to the best of my knowledge afld belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate .neither the Inspector nor his empl.oyer makes any warranty,.axpressed or implied, concerning the examinations and corrective me&1Ures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shell be liable in any m1nner for 1ny penonel Injury or property damage or 1 loss of any kind arising from or connected with this inspection.
-~Q-"'--~'--==---=-~~fwt--~_commission1 t<JXJ J J
/ I n1Pec:tor'1 Slgn8Nre N11tlon11I Bo11rd, St*te, Provine*, end Endorsem11nt1
~r~ ?q Date*_ _ _ _ _.._°?/_ '-<-/_ _ _190 I
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1 . Owner Public Service Electric & Gas Co. Date June 16, 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge, NJ Sheet 1 of 1 Address 2
- Plant Salem Nuclear Generating Station Unit # 1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package # S89-154 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp __N""""'R.___ _ _ _ _ _ __
Name Authorization No. _ _,,3'"""6"------------- Foot of Buttonwood -Rd.,Hancocks Bridge,NJ Expiration Date October 3 , 1991 Address
- 4. Identification of System_P_r_e_s_s_u;;:.r'--i-"z_e_r_ _ _ _ _"""N'""'u::.cc::.cl""e=a-=r'--'C"'l=a-=s~s'-----=l.___ _ _ _ _ _ _ _ _ _ _ _ _ __
ASME DRAFT PUMP and VALVE
- 5. (a) Applicable Construction Code _ _ _ _ _ _ _ 19__fili_Edition,_N~/=A'--_ _ _ _ Addenda,_.N.._/._..Au__ _ _ _ Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_ _ __
- 6. Identification of Components Repaired or Replaced and Replacement Components
- Name of Component Name of Manufacturer Manufacturer Serial No.
National Board No. Other Identification Year Built Repaired, Replaced, ASME Code Stamped (Yes or Replacement or No) Valve M69878-1PR3 Crosby 01-0001 N/A N/A N/A Reoaired NIA
- 7. Description of Work Replace studs and nuts
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is BY. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is nu.mbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) 9; Remarks-~---------------------------------------------- Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Type Code Symbol Stamp_~~-----------------------------------
--,,,,..z:::::.._ _ _ _ _ _ _ _ _ _ _ _ Expiration Date ~O~c~t=o=b~e~r~~3~*-1~9_9~1______
Signed_=-M="'-.+-:;~--:--=---=------"~'-'---=-"'"""-"'-"'-"'""'---><"-"A~--Date ___ {_/;~5----, 19 f?J CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumberrnens Mutual Casualty Company of Lon Grove IL t<? the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with tl)e requirements of.the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connect.ed with this
*inspection.
Date
------------- 6~ 2Z 19r1
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Company Date~J~u=l.,,.y~l~4,__,_1~9~8~9~--------
Name Foot of Buttonwood Rd. ,Hancocks Bridge,NJ Sheet_...__ _ of_~---------- Address 2 P~m Salem Nuclear Generating Station Unit_-lt-.___ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Name Foot of Buttonwood Rd. ,Hancocks Bridqe,NJ ~C_,a""'a.......,e'---'-'1.._.a_._h..,_..p"'a..c....k....a'""'-fg....e~lf~S.,..=-...,8....9""-""'l....... 5....51----- Address Repair Organization P.O. No., Job No., etc. PSE&G Type Code Symbol Stamp _ _N_R_ _ _ _ _ _ _ __
- 3. Work Performed by _ _ _ _ _ _ ___,,-,-----------
Name Authorization No. _____3_6_ _ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Oct 3 1991 Expiration Date _ _ _ _ .------------ Address Main Steam Nu Cl 2
- 4. Identification of System _ _ _ _ _ _ _ _ _ _ _ _*___* - - - - - - - - - - - - - - - - - - - - - - - - - -
- 5. (a) Applicable Construction Code ASME 3 19~Edition, _ _N_A _____ Addenda, ___N_A_._ _ _ _ Code Case NA (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3_ __
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve ll-MS-10 Masoneilan N-OOllR-1 -1 NA NA NA Reoair NA
- 7. Description of work Repair valve internals in kind.
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is BY. in. x _11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Signed __3_6_ _ _ _ _ _ _ _ _ _~_Expiration Date ---'O=-c=t'-".__,3:...L..,-=l'-"9""'9'-'l=------- er-Station A Date CERTIFICATE OF INSERVICE INSPECTION 2/ lf ,19 B ** I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressur-: *,,sel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Co. of Long Grove, IL have inspec*'" 'he components described in this Owner's Report during the period f *If= - (;f 9 to / ~/ (') .,.. ff , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied,.concerning the examinati9ns and corrective measures described in this Owner's Report. Furthermor~. neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. f . -Id Date_ _ _ _ _ _ _ _ _ _19 . ,,y f P~ Q
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Company Date __J_u_l....:y,__l-=-3~,_l...;;9;_80...9:..__ _ _ _ _ _ __
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ _ l _ _ of _ _..:l=----------- Addrea
- 2. Ptam Salem Nuclear Generating Station Unit #1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-173 Addrna Repelr Orgenlzetlon P.O. No., Job No., etc.
- 3. Work Performed by __P_S_E_&_G_ _ _ _ _ _ _ _ _ _ __ Type Code.Symbol Stamp_N=R'----------
Ne me Authorization No. _ _ _.....:::3:..::6::.__ _ _ _ _ _ __ Foot of Buttonwood Rd. ,Hancocks Bridge,NJ Evpi'rati'on Dite Oct* 3 1991 Addr- ~ --==..:..*--=-"'--.::'""'-'::.=..-----
- 4. Identification of System ___ S_a_f_e""".t~y.___I_n~J...
- e_c--'t_i....;o'"'n---"'NJ.=c.=l"'e""a._.r.___,_r_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 5. (al Applicable Construction Code
- Bl6
- 5 19...lLEdition, NA Addenda, _ _..,N....A._____ Cod1 Case (bl Applicable Edition of Section XI Utilized for Repairs o.r Replecement1 19..=8""3'---
- 6. Identification of Components Rep1ired or Replaced and Replacement Components ASME Code National Rep1ired, Stamped Name of Name of M1nufactur1r 801n:I Other Yur RepllCed, (Ye1 Component Manufacturer Serial No. No. ldentificetion Built or Replecement or Nol
_J Valve 12SJ156 Velan 1\77\ l'J21
. ,___ l nt:;t:: Repaired NA
- 1. D1teriptlon of work Replaced cover (bonnet) studs in kind.
B. Te1t1 Conducted: Hydrostltlc 0 Pneumltic 0 Nominil Operating Pr111Ure O Visual Leak Examination Other 0 Pl'ltlUl"I p1i Test Temp. °F NOTE: Supplememll sheetl in form of llltl, 1katch111, or drawings mev be used, provided (1) size it 8% in. x 11 in., 121 informe-tion in items. 1 through 8 on this report It included on eech 1heet, and (3) uch sheet i1 numbered and the number of 1heeu is recorded at the top of this form.
- 112/821 Thi1 Form (E000301 may be obt1ined from th1 Order Depl:., ASME, 345 E. 47th St., New York, N.Y. 10017
---\! f
\
FORM NIS-2 (Backl ApplicaDle Manufacturer's D11t11 Reports to be anached CERTIFICATE OF.COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Cartificate of Au~thorization No, ____3_6____________ Expiration Date Oct. 3/ 1991 Signed Ownarorown.oe.i811 ... Title Manager-Station . QA Date --------<--1-.....;.. ) ft 'f _ __ 19~ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermans Mutual Casualty Company of Long Grove
- IL have ~ected the components described in this Owner's Report during the period ?zvf9 to t:;
- 2111'1 , and state that to the best of my knowledge and belief, the Owner hes performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certifie1tm neither the Inspector nor his employer mikes any warr11ntv, expl'ftled or implied, concerning the examinations and correctiw meaurs described In this Owner's Report. Furthermore, neither the Inspector nor his employer shill be lilbl* in eny m111ner for 111y pel'IOnll Injury or property damage or a lou of any kind arising from or connected with this in9P1ction. ~
--------~...._./_f.__._U---__._ ___._Commission1_M~V;._:;,.J_J_J _ _ _ _ _ _ _ _ __
Netlonel Boerd, Stet*, Province, end Endor111ment1 iftlP9Ctor'1 S&gn.wre Date r1r 19f'f'
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date __A_u-'--'g""u""s'"'t'--1_4-"-'-,-'-1""9_8'-9'---------
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_..=l'--'--- of 1 Address
- 2. Plant Salem Nuclear Generating Station Unit #1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-194 Address Repair Organization P.O. No., Job No.,_etc.
- 3. Work Performed by_.;;.P..::S..::E::..&::..G.:;__ _ _ _ _ _ _ _ _ _ __ Type Code Symbol Stamp_.....o;N:..:::R,,___ _ _ _ _ __
Name Authorization No. _ _ _ _. . ;3:::.. :::6_ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
~ ldentificationofSy~em _ _~C~h~e=m=i~c::..a=l~~V~o~l=u=m~e~C::..o~n~t=r~o~l~~N-=u~c~l=e~a=r~C~l=a~s-=s~I=I~-----------
- 5. (a) Applicable Construction Code Sect. III 19-11.....Edition,......::N~/..:A:=-_ _ _ _ Addenda,_..:.:N~/-"A"-----Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8=3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components
- Name of Component Name of Manufacturer Manufacturer Serial No.
National Board No. Other Identification Year Built Repaired, Replaced, ASME Code Stamped (Yes or Replacement or No)
#12 Boric Acid Pump Gould NIA NIA NIA NIA Ren laced N/A
- 7. DescriptionofWork Replaced #12 B.A.T. pump with rebuilt spare.
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure D *Visual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp, °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Replacementconforms to the rules of the ASME Code, Section XI. repair or replacement Signed _ _:_.:........-"'-----------Expiration Date _.....:::O_,,,c,_,,t.,o~b""e""fi=---"'3(".J'--~~1""'9.t..9,=t..""' Mana er-Station A CERTIFICATE OF INSERVICE INSPECTION Date '6_/!. 1 c;<--- rfJ___!_ I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL . ~ll~J.o_,.spected the components described in this Owner's Report during the period ff:!_ -ff9 to }~Z:*t? L , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XL By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
------~-. ~1-Ln. :~ =-ec=- t"'o"':J" ~-S-ig" f" a'-;-u-r~- _:r "'i-o~}£al-<?-o3:. a*r_d_,_S_t_at_e_,_P_r_o_vi_n_c_a_,
....o/...::;.__;l.-=/'----- Commissions --'pt'-N-- a_n_d_E_n_d_o-rs_a_m_a_n_t_S_
__J
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI 1._ Owner Public Service Electric & Gas Co. Date August 18, 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet _ _ 1 _ _ of _ _1_ _ _ _ _ _ _ _ _ __ Addrea
- 2. Plant _ Salem
____ Nuclear _____ Generating _ _ _ _ _ _Station _ _ _ _ __ Unit _#_l________________ N*me Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-040 Address Aep11lr Organization P.O. No .* Job No., ate.
- 3. Work Performed by __P_S_E_&_G____________ Type Code Symbol Stamp _ _ _N_R________
Name Authorization No. _ _ _ _ _ _3_6=-------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date ___ o_c_t_o_b_e_r_3_,_1_9_9_1____ Addraa
- 4. Identification of System Main Steam (MS) Nuclear Class II
- 5. (al Applicable Construction Code B31
- 7 19~Edition, __N.;./_A____ Addanda, ___N.;./_A_ _ _ Code Casa (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83 *:,
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Pipe Spool lMS-3017 PSE&G N/A N/A None N/A Repaired N
- 1. Description of work Removed pipe spool for inspection and rewelded into system.
- 8. Tests Conducted: Hydrostatic O Pneumatic 0 Nominal Operating Pressure []Visual Leak Examiantion.
Other 0 Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may tie used, provided (1 l size is SY.. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (12/821 This Form (E00030l may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Dat11 Reports to be 11tt11ched CERTIFICATE OF COMPLIANCE
- We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Certificate of Authorization No. __3_6_ _ _ _ _ _ _ _ _ _ _ _ Expiration Date _o_c_t_o_b_e_r_...,3~'i;___l_9_9_1 CERTIFICATE OF INSERVICE INSPECTION if:r
,19?7 I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of
__L_o_n_g__G_r_o_v_e_,__I_L______________...,..__,,__=------ have inspected the components described in this Owner's Report during the period _ _ _ _ _ _ ___,f._-"'1/._*_-.,..8Y._-..__to l-2-ff , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report i_n accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. _ _ _._O_....'~-=----....../_£=.;~;__~_,_,~___ commissions_.:l<;__-J./~u__,3:::...,-7..==7.J~~--,.----:-=---- j?=Pnsp;ct0;; si;r;11tur11 N11tlon11I Bo11rd, Stat11, Province, 11nd Endorsem11nts Date_ _ ___19 f1 ____,.f_,.._)_J
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date June 21 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_.=l"---- of 1 Address
- 2. Plant Salem Nuclear Generating Station Unit 1 Name Code Job Package # 889-057 Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Joh Package j! 889-085 Address Repair Organization P.O. No., Job No~, etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_---'"N""R"--------
Name Authorization No.__.3.,,6~---------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Main Steam (MS ) Nuclear Class I I 5, (a) Applicable Construction Code 19lci 1~~~. d-%9Al4 Addenda,_N...,._/.aA.___ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83 *
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Valve 11GB4 Masoneilan 00130-1-1 NIA None N/A Repaired N/A
- 7. DescriptionofWork Replaced seats. cage, stern and plug assembly, studs and nuts in kind
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other []: Pressure _ _ _ _ _ psi Test Temp. _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1 l size is 8% in. x 11 in., (2) informa-tion in items 1 t_hrough 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
( 12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State orProvinceof New Jersey andemployedby T.umbermens Mutual Casualty Cmnpari.y of Lon Grove IL have inspected the components described in this Owner's Report during the period to * -9~?} , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection.
----=(}~*,.,,.""""C4""-/__,(..__.-=~'""-"*
/7'15Pactor's Signature
"'-=--Commissions-'-':/f!~:f~J....,.2J'--------
National Board, State, Province, and Endorsements Date _ _ _ __,.b'---=l-"-j__19 f7 ./
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co.
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Address
- 2. Plant Salem Nuclear Generating Station Name Foot of Buttonwood Rd.,Hancocks Bridqe,NJ Address Repair Organization P.O. No., Job No:, etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_~N=R~-------
Ne me Authorization No. _ __,.3""6'----------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Containment Spray (CS) Nuclear Class I I Draft
- 5. (a) Applicable Construction CodePump & Valve19~Edition,_~N~/~A~_ _ _ Addenda,_N.,._/_A_ _ _ _ _ Code Case (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8=3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No) 12CS48 Valve Allovl"'n 70-A-629-t N/A None 1970 Repaired N/A
- 7. Description of Work Made cut on disc and then lapped finish B. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other Ci] Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in .. (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of th is form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and thi~eplacement conforms to the rules of the ASME Code, Section XI. repair or replacement
--"'"=------------Expiration Date _O=c_,,t"'o..,b""e=r--=3'-'-,._--'1=9_,,9-"l.___ _ __
b/vL ,19£7 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State
-~~~--'-,#----and employed by Lumbermens Mutual Casualty Company of to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. __ ()+,--th~--==--~....:;_-_C_~-'-------commissions_p';__'J_J1_J
-T Inspector'a Signature National Board, State, Province, and Endorsements Date'-----=t'---_.Z"'-'---3_ _ _19 if
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. owner Public Service Electric & Gas Co. Date __J~u.:..._n~e'---9'--'-,_1_9_8_9 Name Foot of Buttonwood Rd. , Hancocks Bridge, NJ Sheet_.=l,____ of 1 Address
- 2. Plant Salem Nuclear Generating Station Name Foot of Buttonwood Rd.,Hancocks Bridqe,NJ Code Job Package# S89-062 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp _ ___.N~R..,.___ _ _ _ _ _ __
Name Authorization No. _.;u;!...__ _ _ _ _ _ _ _ _ _ __ Foot of Buttonwood Rd. , Hancocks Bridge, NJ Expiration Date October 3, 199] Address
- 4. Identification of System _ _C=o"-'m""p"'o=n,.,,e,,,n"--t"'-_,,C,,,o""'o~l-=i,..n.._,g.,__ _ _ _
,,, UC... f'I 1v____..J.J-_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
- 5. (a) Applicable Construction Code xl 19~Edition,--'1=9...::8...::3=---_ _ _ Addenda, Summer Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8_3'---
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve 1CC280 Rockwell N/A N/A None N/A Repair N
- 7. Description of Work Replaced Bonnent - Stem and Plug in Kind
- 8. Tests Conducted: Hydrostatic D Pneumatic D Nominal Operating Pressure ~ViJ;ual Leak Examination Other D Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
- (12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to'the rules of the ASME Code, Section XI. repair or replacement __3_6 ____________ Expiration Date October 3' 1991 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lurnberrnens Mutual Casualty Co. of LG Grove, IL ected the components described in this Owner's Report during the period to , and state that to the best of my knowledge and belief, the Owner has performed examinations and\aken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By' signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. _____()'f'-'~.,._~~_/-(~"~~--nL~~-:
~s Signature .
___ Commissions AJT.J 7.J National Board, State, Province, and Endorsements Date Y,lo 19.~fC/_
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Servi!:;;e Ele!:;;tric & Gas Co Date July 11, 1989 Name Foot of Buttonwood Rd., Hg,ni;;Qcks Bridge,NJ Sheet of Address Salem Nuclear Generating Station #1
- 2. Plant Unit Name Foot of Buttonwood Rd., Hancocks Bridge,NJ Code Job Package #S-89-063 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by __P_S_E_&_G----.,..,,....--------- Type Code Symbol Stamp ____N_R_ _ _ _ _ __
Name Authorization No. _______3_6_ _ _ _ _ __ Expiration Date ___o_c_t_._3~,_1_9_9_1_ _ _ _ __ Address
- 4. Identification of System_.r-_I_a_i_n__s_t_e_a_m___N_u_._c_l_.__2_________________________
- 5. (a) Applicable Construction Code ASME 3 19~Edition, __1_m _ _ _ _ _ Addenda, _ _N_A_ _ _ _ _ Code Case NA (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Valve 11-MS-169 Fisher NA NA NA NA Repair NA
- 7. Description of Work Replace plug and seat.
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other 0 Pressure ______ psi Test Temp. ______°F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form .
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Type Code Symbol Stamp _ _ _ NR_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Certificate of ~u:h~ization No. _ _3_6_ _ _ _ _ _ _ _ _ _ _ _ _ Expiration Date Oct. 3, 1991 Signed ~ 1A ~ Owner or~. Title Mgr. -Sta t i on QA D t ) ( a e _ _ _ _ _ _ _,___~---
'{ 190 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Co. of Long Grove, IL have ~n~ec~f-,.e components described
,?-' * , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. Date_---'"'-~-*~~[_ _ _19 SJ L
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date _J_u_l.:o.y_3_1-"",_1_9_8_9_ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Shi!i!t _ _1 _ _ of---=----------- 1 Addrea 2 _ Plant Salem Nuclear Generating Station Unit #1 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-066 Addr . . Fl*P*lr Organlzstlon P.O. No., Job No., etc.
- 3. Work Performed by __P_S_E_&_G_ _ _ _ _ _ _ _ _.;___ _ Type Code Syrnbol Stitmp _ __.:;N:.:::R!.-------
Ne me Authorizetion No. _ _ _ _ _..,:3::.;6"-------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration D1te _ _o=c...:t:..::o:..:b:::.;e=r--=3:..J,~l:::..:::9..=9:..:l::......_ __ Addr-
- 4. Identification of System Safety Injection Nuclear Class I Draft
- 5. (al Applicable Construction Code Pump & Valvei9~Edition,_N:::..<../..._A.___ _ _ Addend1, __NUL/~Al--___ Cod1 C..
(bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced 11~d Replacement Compon1nu ASME
,' Code National Repaired, Stamped Name of Namaof Manuf!ICtUrer Bo1rd Other Y11r Replleed, (Yes Component Manufacturer Seri1I No. No. ldentific1tion Built or Repl1eement or Nol Valve 12SJ142 Rockwell N/A N/A None 1970 Replaced N/A
- 1. o..Crlptlon of Wortc Replaced Rockwell valve with a Yarway valve.
- 8. Tests Conducted: Hydrostltlc 0 Pneumatic 0 Nominal Operating Pl"lllUre 0 Visual Leak Examination Other 0 Pressure _ _ _ _ _ p1i Test Temp, _ _ _ _ _* F NOTE: Supplementll lheett in form of lists, 1ketch11, or drewing1 ,,,.y bl used, provided (1 I size i1 8% in. x 11 in., 121 infortn1*
tion in items 1*through 6 on thil report ii includld on 11eh sheet, end (31 llCh lheet i1 numbered and th1 number of sheets 11 recorded It the top of this form. (12/82) This Form (E00030) m1Y be obtained from th~ Ordlr D~t., ASME, 345 E. 47th St., Nciw Yorlt, N.Y. 10017
\*
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached
.CERTIFICATE OF COMPLIANCE We certify that the statements mede in the report are correct and this Replacemen~onforms to the rules of the ASME Code, Section XI. rap*ir or repl*c*m*nt
- - - - - - - - - - - - - - - E x p i r a t i o n Date __o=c'-'t.,,o,..b=e"'"r___,3"':"'-"'1""9~9..,1~----,
Signed er-Station A Date _ _ _ _ _ _ ~..._."'-/_._._ _ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid.commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Co. of Long Grove, IL have i~sp~t:_d [-h.K components described in th_is Owner's Report during the period G/ ' - d- tJ - p 9 to if= ~ ~ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied,.concerning the examinations and corrective measur* described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be *liable in arw manner for any pel'IOnal injury or property damage or* 1011 of any kind arising from or connected with this
~
____t-,,~~~~ in1P9Ction.
...YL-=*
-=------Comm.ission1__,_,v_a_f'._"'l-_6_.J_._/V_'J,;;;,__*_@_
1Ptli:t01"'9Sitnature 1 _9.,,...-'-N-J-)_ __ N*tlon*I Bo*ra, State, Province, *nd Endor111menta oate._--"-S_-~7_ _ _ _,s ?,/'
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date __J_u_n_e_l~9~*~1~9~8~9_ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd. , Hancocks Bridge, NJ Sheet 1 Address -=---- of 1
- 2. Plant Salem Nuclear Generating Station Unit...._~l~----------------
Name
- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package j 889-067 Address Repair Organization P.O. No., Job No,;etc.
- 3. Work Performed by_P_S_E_&_G_C_o_m~p_a~n~Y,--------- Type Code Symbol Stamp_*_,,,.a.._ _ _ _ _ _ __
Name Authorization No._1.l..1..------------ Foot of Buttonwood Rd.,Hancocks Bridge.NJ Expiration DatEOctoher 3, 1 991 Address
- 4. Identification of System Chemical Volume Control (CVC) Nuclear Class TT Draft P. &
- 5. (a) Applicable Construction Code Ya l ve Code 19~ Edition,__..l...;;9...6....8.,___ _ _ Addenda,_N=-/""A'------Code Casa (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19_8~3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Valve 6910-95001-1CV3 Copes Vulcan 156-15 N/A N/A N/A Repaired N/A
- 7. Description of Work Installed new stem, plug and seats in kind
- 8. Tests Conducted: Hydrostatic 0 Pneumatic D Nominal Operating Pressure 0 Visual Leak Examination Other~ Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (11 size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. '
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E, 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement Type Code Symbol Stamp _ _N_R_*- - - - - - - - - - - - - - - - - - - - - - - - - - - -
- ~:cate of ;;/:)on No, _ _..::3__6:___ _ _ _ _ _ _Q_A ____ Expi:a:::n Date October 3, 1991 Owner or Own
'~ ,19 0 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of
_L_o_n_g~_G_r_o_v_e~'~-I_L___________-,---,~-,.---..----..,_----havp.insJJected}--tty components described in this Owner's Report during the period _ _ _ _</~_-_/_P __-_Y_~/__ to _ _ _ _ _-_/_tJ_ _.______, and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures describiid in this Owner's Report in accordance with, the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a Joss of any kind arising from or connected with this '""'"""* /,, ~ iflSPaetor'1 Signature Co;;,mlalo** ,U 8 f'°.,). ,,:- S- ~J ? /"t /"' I National Board, State, Province, and Endorsements Date_ _~f_,._/,_"t:J_ _ _ _ _19 f'" Y
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Company Date_J_u_l=y_l_8~,_1_9_8_9_ _ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet __l ___ of __l = - - - - - - - - - - - - Address 2 . Plant Salem Nuclear Generating Station Unit #1 Ne me Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package #S-89-068 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp _ _--:N"""R:::--------
Name Authorization No. ______ 3 _6_ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks. Bridge,NJ Expiration Date _ _...o:;.;:c"'"t=-o=b"'e""ro.....3"'-.L,-"1""'9""'9"""'1_ _ __ Address
- 4. Identification of System _ _c_h_e_m_i_c_a_l_V_o_l_u_m_e__C_o_n_t_r_o_l__N_u_.;.c..;:l;_;e;_;a;;;;r=--..;:C..;:l::.:a;;;;s=.=s_-__,2=------------
ASME Draft **~*1
- 5. (al Applicable Construction Code Pump & ValVE:!Jg~Edition,_~N.._/..:;.A=-----Addenda,__.N,../'-'A=-_ _ _ _ Code CaseN/A (bl Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Coda National Repaired, Stamped Name of Name of Manufacturer Board Other Veer Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or Nol Valve Copes 6910-9500 -
l-CV-5 Vulcan 15647 N/A N/A N/A Repaired N/A
- 7. Description of Work Replaced valve seat and plug 8, Tests Co.nducted: HydrOstatic 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., 121 informa-tion in items 1 through 6 on this repon is included on each sheet, and (3) eech sheet is numbered and the number of sheets is recorded at the top of this form.
112/821 This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.V. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be anached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI.
- repair or replacement
-----,,.-------------Expiration Date __O,;;__c..;;t;...;o;;..:b.:..e=r;......c3:;..:..,.-::l::.:9::...::.9-=l'------
Signed Mariager-Station QA Date _ _ _ _ _ _ _...,~ :__/_ _ _ _ , 19 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New *Jersey and employed by Luinbermens Mutual Casualty Company of Long Grove, IL have inspecte<}- !~ components described in this Owner's Report during the period--'-~-Q',,____~-_/'-"J?'--_-.....:...Y.....:...f___ to _ ____.t?.,__..._/_tJ_-_ _V:...:.7____ , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warrantV, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this t,,-{!...~ inspection. Comm;g;oo*N.6' J'.)CF /VT tf /t_ /._./ ( l~or'1 Slgnmtune Natlonal Board, State, Provine*, and Endorsamants Oate,_ t'?.-~/o __,tr~ _ _ _ _ _ _19 ff t--y
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date _ _ J_u_n_e_l_9__,_,_1_9_8_9_ _ _ _ _ _ _ __
Name Foot of Buttonwood Rd.,Hancocks Bridqe,NJ Sheet_..~-- of_..___ _ _ _ _ _ _ _ _ __ Address 2~ Plant Salem Nuclear Generating Station . Unit--'.._.-__ _ _ _ _ _ _ _ _ _ _ _ _ __ Name Foot of Buttonwood Rd.,Hancocks Bridge.NJ Code Joh Package # 889-069 Address Repair Organization P.O. No., Job No:* etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp~IA----------
Name Authorization No._.,,.,_ _ _ _ _ _ _ _ _ _ _ __ Foot of Buttonwood Rd ** Hancocks Bridge.NJ Expiration Date October 3, 1991 Address
- 4. Identification of System Chemical Volume Cont:r'.'Ol ( CVC) Nuclear Class II Draft p. &
- 5. (al Applicable Construction Code Valve Code 1s__§_§_Edition,__,l=-9=-6=8'-----Addenda,:.:N,,_/_..A...__ _ _ _ Code Casa (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19,_,.8~3,__
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced*, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve 6910-9500 - 1CV4 Cones Vulro= In 1 "ifi-1 t:; l\1/:zl l>.lr.na NIA Reoaired N/A
- 7. Description of Work Installed new plug and seats 8, Tests Conducted: . Hydrostatic D Pneumatic D Nominal Operating Pressure D Visual Leak Examination Other Qg Pressure _ _ _ _ _ psi Test Temp, _ _ _ _ _° F NOTE: Supplemental sheets in form of lists, sk~ches, or drawings may be used, provided (1 l size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ~SME Code, Section XI. repair or replacement CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State qr Province of New Jersey and employed byLumbermens Mutual Casualty Company of Lon Grove IL ected the components described to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ~ ____ * +-""'~=-o:;;/?;:r""'/--~=---L_,fu.....~.....__---Commissions_M'---0=-~}-J_.J fi'llPector'1 Signature National Board, State, Province, and Endorsements
- FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code* Section XI 1 . Owner Public Service Electric & Gas Co. Date _ _::.Jc=u:::n::.::e=--:l::.:5:::o..L,-=l,_.9""8~9"----------
Name Foot of Buttonwood Rd. ,Hancocks Bridge, NJ Sheet _ _l _ _ of _ _~l=--------- Address
- 2. Plant Salem Nuclear Generating Station Unit ~.__-=l'-----------------
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package # 889-075 Address Repair Organization P.O. No., Job No., etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp_.,~--------
Name Authorization No.~.Ll..L----------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3 l 991 Address
- 4. Identification of System Main Steam (MS ) Nu. CL I I
- 5. (a) Applicable Construction Code.-=B"'3""1=.:.._,,7_ _ _ _ 19___Q2_ Edition,__..1~9"-7,,__.,.J_ _ _ _ Addenda,Wi n t er Code CaseN/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19~8-3_ _
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No. Identification Built or Replacement or No)
Valve 12GB4 Masoneilan N00130-l-2 N/A None N/A Repaired NIA
- 7. Description ofWorkReplaced seats,plug and stem assembly in kind
.. 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure []visual Leak Examination Other§ Pressure _ _ _ _ _ psi TestTemp. _ _ _ _ _°F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is BY. in. x 11 in., (2) informa-tion in items 1. through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form. (12/82) This Form (E00030) may be obtained from the Order Dept,, ASME, 345 E. 47th St., New York, N.Y. 10017 I
FORM NIS-2 (Back)
*Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement
--"-~------------Expiration Date ~O~c~t=o=b~e=r=-.-=3~/~"'1-"9~9~1~-----
Signed_=-[/!!.~~':J_~'t:::;;~::::::::::~~~~~~!:..Q!~~A~ ___ Date-----~~,_.__5 _ _ _ _ , 19 f1 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Lon Grove, IL have inspected t~ components described
£..-/if .- :f' , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. -
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. J
-----=v-¥-:-l~~-==--------Commissions ' µtff P;; ?;- /VJ & / r /(../°I National Board, State, Province, and Endorsements Date_ _____19 Y
_,f'--,.._/CJ f
FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date June 19 1989 Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Sheet_=l_ _ _ of_~-----------
Address
- 2. Plant Salem Nuclear Generating Station Unit_~~l~-------------~
Name Foot of Buttonwood Rd.,Hancocks Bridge,NJ Code Job Package fS89-0BO Address Repair Organization P.O. No., Job No:, etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp _ _ N_R_ _ _ _ _ _ __
Name Authorization No. --"3~6"------------- Foot of Buttonwood Rd.,Hancocks Bridge,NJ Expiration Date October 3, 1989 Address
- 4. Identification of System Component Cooling
- Nuclear Class - 2 ASME DRAFT PUMP & VALVE
- 5. (a) Applicable Construction Code 19~Edition,_1_9_6_8_ _ _ _ Addenda,_,N,..._/A....__ _ _ _ Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components
- Name of Component Name of Manufacturer Manufacturer Serial No.
National Board No. Other Identification Year Built Repaired, Replaced, ASME or Replacement or No) Code Stamped (Yes Valve 1CC113 Masoneilan H47968-2-2 NIA NIA NIA Rpn:oi rf'>n Nill.
- 7. Description of Work Replaced valve plug, stem and seat ring
.. 8. Tests Conducted: Hydrostatic Other 0 0 Pneumatic 0 Nominal Operating Pressure Pressure _ _ _ _ _ psi Test Temp. 0
°F Visual Leak Examination NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1 l size is SY. in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
(12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 10017
FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and this Repair conforms to the rules of the ASME Code, Section XI. repair or replacement _ __,.""------------Expiration Date -=Oc.=c~t=-o=b'-"e"""'r,,__"'3'"----'1"""""'9_,,9'""1,,_______ t;f! .i2 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Company of Long Grove, IL hav:_ ~cted the components described It'-) "' , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, .expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or connected with this inspection. ___fo~/*4. ,. , °,'1-., .,./'- - - <-{~.u""'-"-""'- Inspector's Signature
!...=....._ _ commissions----<-.:.,M~J"~,J_'7-=-J---------,-.,,-------
National Board, State, Province, and Endorsements Date_ _ _ ~r._r_t_l,,__19 rr
~ ll ll FORM NIS-2 OWNER'S REPORT FOR REPAIRS OR REPLACEMENTS As Required by the Provisions of the ASME Code Section XI
- 1. Owner Public Service Electric & Gas Co. Date June 21, 1989 Name Foot of Buttonwood Rd. , Hancocks Bridge, Nj Sheet 1 of 1 Address ---"'-- ---==-----------~
- 2. Plant Salem Nuclear Generating Station Unit # 1 Name Foot of Buttonwood Rd.,Hancocks Bridge, NJ Code Job Package # S89-081 Address Repair Organization P.O. No., Job No:, etc.
- 3. Work Performed by PSE&G Company Type Code Symbol Stamp~N~R~---------
Name Authorization No. --'3""6,.___ _ _ _ _ _ _ _ _ __ Foot of Buttonwood Rd.,Hancocks Bridqe,NJ Expiration Date October 3. 1991 Address
- 4. Identification of System Safety Injection ASME DRAFT PUMP AND VALVE CODE 1968
- 5. (a) Applicable Construction Code _ _ _ _ _ _ _ 19 _ _ Edition,_~N--1~A~_ _ Addenda,_....N'l-/-"'A,___ _ _ _ Code Case N/A (b) Applicable Edition of Section XI Utilized for Repairs or Replacements 19 83
- 6. Identification of Components Repaired or Replaced and Replacement Components ASME Code National Repaired, Stamped Name of Name of Manufacturer Board Other Year Replaced, (Yes Component Manufacturer Serial No. No, Identification Built or Replacement or Nol Valve Anchor llSJll3 Valve NIA NIA NIA 1 q70 Ri:>n-"li r Nill.
- 1. Description of Work Replace bonnet studs and Dllts
- 8. Tests Conducted: Hydrostatic 0 Pneumatic 0 Nominal Operating Pressure 0 Visual Leak Examination Other 0 Pressure _ _ _ _ _ psi Test Temp. °F NOTE: Supplemental sheets in form of lists, sketches, or drawings may be used, provided (1) size is 8% in. x 11 in., (2) informa-tion in items 1 through 6 on this report is included on each sheet, and (3) each sheet is numbered and the number of sheets is recorded at the top of this form.
{12/82) This Form (E00030) may be obtained from the Order Dept., ASME, 345 E. 47th St., New York, N.Y. 1.0017
I *~- FORM NIS-2 (Back) Applicable Manufacturer's Data Reports to be attached CERTIFICATE OF COMPLIANCE We certify that the statements made in the report are correct and.this Repair conforms to the rules of the ASME Code, Section XI. *
- repair or.replacement
-~'------*------Expiration Date October 3 * :L9...9l______
Signed_"="'""""-=-::-""s.-~-::--:---:::~=-r_._._-_,,S,_,T..,a"'-t.._,,_i"""o""n~"'A"----Date _ _ _ _ _ _ _(._,ft'--VL----. 19 -~ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of New Jersey and employed by Lumbermens Mutual Casualty Campany of Long_Qrove, IL ,hav1t insRected the components .described in this Owner's Report during the period 'f--Zy cf?t'o /6- .) "flj . , and state that to the best of my knowledge and belief, the Owner has performed examinations and taken corrective measures described in this Owner's Report in accordance with the requirements of the ASME Code, Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal Injury or property damage o*r a loss of any kind arising from or connected with this inspection.
~-0~,IL-"~..:.=.-----'-(:-~
/ lnSP6CtOr'i Signature
....... _ _ Commissions_;(/._:J__,,Jo....L.J_'J______
.J.----=-=-* ~--:---
National Board, State, Province, and Endorsements Date._ _ _ _ =t'---'l~>- 1er{
SOUTHWEST RESEARCH INSTITUTE Post Office Drawer 28510 6220 Culebra Road San Antonio, Texas 78284
**-..... ~ ,
. *. -~ t'" ;,/;~~:'*r
- flc,1 ~\,)~ ~*~;,*e SPRING 1989 NONDESTRUCTIVE EXAl\JljPJ'&.~lONS OF SELECTED CLASS 1 AND CLASS 2 c;cJMeoN;ENTS ' ....,;: .
OF.THE SALEM GENERATING STATION, U~IT:-.J VOLUME II APPENDICES (CONT'D) SwRI Project 2735 ..... Prepared for Publ~c Service Electric a~.d Gas Company 80 Park Place P.O. Box 570 Newark, New Jersey 07101~** - June 1989 Written by Approved by hn R. lngamells David F. Resow . *=:er*_.\c:~s reject Engineer Director *. ,_,. : ":,:::~*)f\
* -.::***'-~'-
*****~(*.*.~*~
Engineering and Analysis Section Department *of N DE Services*:**'*"*;;, Department of NDE Services Nondestructive Evaruation Soiepi:e and Technology.Divisio.r,. :. ::: .. *** ..:
* ~ ** '\ ** : '* *
- j
APPENDIXD SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TESTING PROCEDURES
- APPENDIXD SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE TE§TING PROCEDURES Table of Contents Procedure No./Rev.
SwRI-NDT-200-1/70 Solvent-Removable Liquid Penetrant Color Contrast Exam-Dev. 4 ination SwRI-NDT-200-3/8 Visible Water-Washable Liquid Penetrant Examinations Devs. 2 and 3 SwRI-NDT-300-1/35 Dry Powder Magnetic Particle Examination Dev. 3 SwRI-NDT-300-2/42 Fluorescent Magnetic Particle Examination Dev. 4 SwRI-NDT-600-6/25 Manual Ultrasonic Examination of Reactor Coolant Pump Dev. 2 Flywheels SwRI-NDT-600-14 /19 Manual Ultrasonic Examination of Studs and Bolts Devs. 2 and 3 SwRI-NDT-600-15 /72 Manual Ultrasonic Examination of Pressure Vessel Welds Dev. 2 SwRI-NDT-600-16/31 Manual Ultrasonic Examination of Vessel Support Skirt Dev. 1 Attachment Welds SwRI-NDT-600-18/42 Manual Ultrasonic Examination of Pressure-Retaining Studs Dev.*2 and Bolts Greater Than 2 Inches in Diameter Containing Access Holes SwRI-NDT-600-26/12
- Manual Ultrasonic Examination of Thin Wall Vessel Welds Dev. 1 (0.1 to 0.4 Inch Thick)
SwRI-NDT-600-31/23 Manual Ultrasonic Examination of Austenitic Pressure Piping Dev. 1 Welds SwRI-NDT-600-33/11 . Manual Ultrasonic Examination of Pressure Vessel Welds Dev. 1 Greater Than 0.4 to 2.0 Inches in Thickness SwRI-NDT-600-39/9 Manual Ultrasonic Examination of Small-Diameter Piping Devs. 1and2 Welds
- SwRI-NDT-600-41/16 Dev. 2 Manual Ultrasonic Examination of Ferritic Pressure Piping Welds D-i
~ ... _ .......... _ . _____ 1._. - - - ; * *
**--*--*~~-.-- **--
APPENDIXD I ~' .. '
**--*~---- . .:::A... - ......._ ~ ---- -
,..J,
' '* - SOUTHWEST RESEARCH* INSTITUTE
'_N.ONR:E,STRUCTIVE TES11NG PROCEDURES
>.Procedure No./Rev.
Manual Ultrasonic Examination_of Pressure Vessel Welds in Sw RI-NDT-600-48/1 Accordance with Regulatory -Guide .i 150* * *-\:.. * *------ ~ Dev. 1 * :;. ! : * -: :. *. : .:..: Manual Ultrasonic Examination Using Longitudgi,ai:'Wave
' SwRI-NDT-600-49/1 Straight-Beam Techniques . * * * ., 0
*..:. r..i 2 * :.-..*
Dev. 1 . :::v~'*JI1c>>J . :.-- . :£9: ~;cl :r-.---: *~:::: *-;, *:** . . . Inner Surface Examfri.ation of the Access Holes m* Pressure-- SwRI-NDT-800-104 /2 Retaining Studs 2-Jnche~-and"dreater in Diame~er . _..*--~--.:::'
..." * .... '. ~ **-~**, r.- . ..
. ,. :;~ -~--. - . - - . . ..... - . ' ( ' -~- - . . ,*
Calibration and Ultrasoriic Thickness Measurement .of F.erritic:* *' SwRI-NDT-800-122/2 Piping, Vessels, and Components Using tl,le SwRI Tuickhess* Dev. 1 Data Acquisition System
- Visual Examination of Nuclear Power Plant Components SwRI-NDT-900-7 /14 )
Dev.1
, ~---*"*-- --*
-**-- ----** ~----... ..._..,...__.,.-~-----* ----~- ...
*----..--------- ~ ..ir*:: ;:.;: .,1~ ~- '!:;*
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PROCEDURE DEVIATlQN Page 1 of 2 Pages Procedure SwRl-NDT- 200-1
,:,*I ~eviation No. 4 The following examination areas are affected by this deviation:
. ~-Q~~-.f.!lL]~i~~~- ~ .1 .* - ; .
Liquid penetrant examinations to be performed in aceordance witlltliiiqn:*ocedure.
<.J *.
- The following paragraphs shall be deviated frbm.as .iriqic<(;e~~' 1 .-~~;.* ... ..;,:..... ,..::":
~ .~*.- _.
D ~ ....t -1 r* r; :..l~ r,., , '('\ r ' T .' * ,. - .. 5.3 Materials and Eqtiipi'neilt ;~ ** .:u nniisri.r*-:Li._..,,(~'-' r, :::;'" ; :
. ,,,::r:.:~',',~'
ebrn*; nr:c.o:.., Change the follo,wiJlg subparagraphs to read as follows: * ., *::; *
' *,, ")':! 'l *. ,L..; .*";:* '.:> ';1;h k' r;::;i1r*-:.~ .. -
(1) Precleaner-Spotcheck, type S.KC..NF or :cype SKC-S .:::; ~- . (3) Pene~t Remover-Spotcheck, Type skc-NF1tii-'type;SKC-S (4) D"ey~~pe~:.:Spotcheck.; type SKD~¥J? or*typ~ SKD-~ .
' * ~ "~ .L.. /J , ... *":;t 1
.... , ";(.L...~} ~* :~: .-; ~, f .
. ;1(. t .;:~* -:) l.
- r
.( ..
\ . ..::
Rationale for deviation: To allow use of nonflammable materials and incorporate recording criteria as requested by Public Service Electric and Gas Company. If the deviation is determined to affect tne procedure Deviation Affects Qualification YES (] NO 0 qualification, the deviation shall be qualified in accordance with Procedure IX-FE-107 . APPROVALS . SA ,CtJJ
!.;.,1 ,
Written by:
;1 -**1 1:'
Date: Technical Revie~/.*.__ t,..,.(J.. 1
)£ ,* /-!,.fl/J -:-""
- /, I //
_,. z*- . Date*
~........ ._,.
/,, ,/ - ."" _/,/./.c/,i/1 !( .~ ,...J II I/ I Date:
'* .. *'{_,*/////- - .......... Verbal Appro-(il Given? 0 Yes l2J No Manager of Q.A.: fr,~ Date: Cognizant Director: Date:
Sc~ ~ /}Juj( ~-~ 2/11/31 SwAI FORM FE-4-G
Proeedur-e.Deviation SwRI Procedure 200-1
~eviSion :No. 10 .... ~":: :::: ~:- 4** **
I*
..... *.,,,;,' t Deviation N-0 *. 4
.Page 2 of2 tChange Section 8, RECORDING CRITERIA. to read as.fq_llows:
' * * '*, _! *_ 1'. **--'""::?/~ t :.~-,:-:1_ . . *] ;
- 8. RECORDING CRITERIA *
~.,n.,. ..... ~ .... ~ ','****N,..,,
- 0 .... , .0-.
Indications shall be recorded in accordance with:the-~~hztlq~es outllnecrfn "tlie"app1icable revision of SwRI Nuclear Projects Operating l>;-ocedure'.IXaFE~I16: T 8.1 ;Ll~eai!nfileations Linear indications shall be recorded on the SwRI Liquid Penetrant Examination Record and reported to the customer for disposition in accordance with the recording criteria table below: Overall Indication Length
;~~-"*-=-,., Nominal Wall Thickness as defined in Attached Figure 7
' . ~
<Inches)
-\.
(Inches) Less than 1.0 1/8 LO to less than 2.5 3/16 2.5 and greater 1/4
! ( ...... '.: ~ " l
,.---, ...,.,,_..... _ . . . . . ,., ..........,. . ._____ --..**---* - *- ~ ~NOTE-. - ------- ....~~.**:
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s:c~~ ~. i ---- _. -*-*-*
........ ~--*-~*-
I -. : .*' ****. -
~ . ' ,, '** Fpr preservice examination, indications with a length ofJ/16 inch~l1i"f'erretic piping less ~~~:!!t~?-~~--~ches in thickness shall be recorded. , * '-' *.
i Rounded indications shall be recorded based on diameters corresponding to the llnear indi~tl~n r~cording i;-'"="'4~---criteria and reported to the customer for disposition. *
. . . .,,,, .............,. - - . ,,. ... ~---"*' -.. . - ...
When conditions limit the Jea of exami~~~~~~J;~"li;i~ti6~~-~hitli *b*~ ~e~~~d~d.' ** * *------*~---*-*-*** *
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SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-2'oo..:.1:c: '1 E
. i ~ -.., , .... .1 n Revision 70 '"' * ,;
NUCLEAR PROJECTS June 1987' :*~t;.!*.f".1
. OPERATING PROCEDURE Page 1 of 16 Title '~ . ,l : . : -
~ ('~ ~~
SOLVENT-RE...'10VABLE LIQl[ID PENETRANT -Cbto*R CONTRAST EXA.'1INATION .
!"(:.. .-:: r.~~ ':._ . . * ;~:-. :-,.~.* ::~ -. .' .
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EFFECTIVITY..AND .APPRQVAL r~ ""~ :::..'.;j'.1 .' '* ~;~~"7.N~; Revision 70 of this procedure became effective on June 22
- 1987. Other revisions of the base document may
.. '. ~-- ~ **- 7 ,; ~." :-::. :.:i .. ,J :~l be effective concurrently_ .
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Date Technical Review d 1~--~ Manager of Q.A. --. _ .,: (7% Date Co'}l/.~nt Director
~~-- .. /~~;; / '-11(/-y.
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~ I The following into*rmation may be u~ed for convenience .. ~plet1on of this portion. is not *mand3to~y~;-,:. -
- J~""
.. ::***.~::. 11~"19Jh.:-
Deviation No. Date Effective Procedure Section (s) Affected Notes: SwRI Form QA-40A-O
SwRI-NDT-200-1 SOUTHWEST RESEARCH INSTITUTE . *--- -- --
' . ~ .,_ ___ Revision 70
.... June 1987
_, **.*. ,'", f .- NUCLEAR PROJECTS OPERATING PROCEDURE Page-2 of 16 SOLVENT-REMOVABLE LIQUID PENETRANT coiQR CONTRAST EXAMINATION
- ~.: - ' ..... . .-.. ... ......_. ,., ____ ..
( _,
. ~- *- --~ .
SwRI-NDT-200-1**
- 1. PURPOSE This procedu+e provides the technical information and detailed s t*eps required to ensure proper liquid penetrant examination of nonporous austenitic or carbon steel materials in accordance with' the: applicable American Society of Mechanical En~ineers (ASME) Boiler and Pressure~ Vessel Codes.
- 2. SCOPE AND APPLICATION (1) The color contrast method of solvent-removable liquid penetrant examination shall be employed as specified in this procedure for d~tection of surface discontinuities in austenitic or carbon steel
~aterial. * -l . ~
I (2) CompOJ.'\ents and welds to be examined are. spe_s.ified in, the applicable Southwest Research Institute (SwRI) Examination Plan.
- 3. APPLICABLE DOeUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, *"R~les* fgr Inservice Inspection_ of
. ~~ :; .
Nuclear Power Plant Components". : _*...- , "' .. (2) ASME Boiler and Pressure Vessel Code, Section V, 1983 Ed:i.tfon.with Addenda through Summer 1983, "Noµdes.u*.J.l~ti ve Examination" *'~ ~ :* -~.: ~ ,.
.. ;:, ~ .
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(3) ! SwRI Nuclear Quality Assurance Program }1cinual (NQAPM) .... - -~,-- - : .. :: ~
- ..... .II., \P(
3.1 Applicable Examination*Record I i .. *-. - . -~ .=* r ... Swi;{.I-NDTR Form No. 17-11, revision*date_c;i:*J.-3"'.".79 -------
... . . *.. - - , ._ -r.
- 4. RESPONSIBILITY '- :~ :.. '3. .... .
(1) The Director of the Departnieni-_.~-f~Ertgi~~~-~ln'g Services s *Nondestruc-tive Evaluation Science and ~~~hnology.: D-iv.isfo_n, shall be resp_onsible for the* preparation, review~ *app*r.ova~,,- '!.Il~ *;c::ontrol of this procedure.
-i: - = s.::.. :_. ~:: :_ - - *- .. . ,. . : ":. *.. ~ 1,.
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- SwRI Form QA 3-2
**-* ,. -*~-----........._ .
SOUTHWEST RESl;ARCH INSTITUTE SwRI-NDT-200..,.1 Revision 70
.'"';__.iJ2 !'
~ .:i ' ~ - -* - .
June 1987 ~ .. - "~.:>;._ ...--~;:, {
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NU.CLEAR PROJECTS-0P-Ef.!AJJryG PROCEDURE
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- Page 3 of 16 - ~i.(,~~Jt ........* t '
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a_g_e_r_sh_a_l_l_b_e_r_e_s_p_o_n_s_i..,b~l~e~- .. -f-o_'t___-t_h_e-im_p_..le_m_e_n_t_a_t_i_*o_n_o_f__--t*-- *:** ..*-- *---*-----.. *-~--i this procedure in accordance with the NQAPM *specified in the appli- :*?_~__[_{ :: ' I cable SwRI Proje~t Plan. ! I { (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Support and:Admin;i.~tratiqn Section, Nondestructive Evaluation Science* and Technology Divi~ion, *shall be responsible for* - I storage of records generated in accordance with this procedure. * :,.:"'~~::n~~-~~-~;::~~ PERSONNEL A.i'ID EQUIPMENT .:...s~ ..... n,,r._:}e':': I s.1 Personnel Certification .. .." I
*----*- ' .. ~ [
Personnel performing examinations shall be certified in accordance ith SwRI. NQAP 11.:.1, "Special Process Control." 5.2 Material/Equipment Certification i The penetrant materials used *shall be certified for residual sulfur:-c-.. !" i' \ I ntent and total residual halogens in accordance with SD-129 and SD-808 of * *:-* ~'c. I I rticle 24, Section V. J Certified. reports for all surface contact materials to be used for . ~- j netrant examinations, giving batch numbers and analysis results, shall be tained from- the supplier. Copies of the certifi'ed: reports shall be retained ith the examination r~cords. I I J
~ . ~
-' j Equipment used to measure ~i:idaceL and* p~n-~trant temperature shall I
ve been calibrated and certified, -~nd_ ,,shall display a valid calibration tag I j required by NQAP 10-1. ._,, ""**- ':J':-:*:2.:.-:-.c 50:-:,::_* 5.3 Materials and Equipment (,...
\ .:_)
\
I j I j The following materials and* equlj,pment ~ shall be used for exaniirui..,_.__::_:_*
* ** * , ~- ..J. .*"f .-, .::.
.. - C* I ons performed in accordance with this procedure: - * . > :. ;:- __
;_- - ~*;.;,.:
j (1) c-.::. Precleaner - Spo~check, Type SKC-S j (2) **
- Penetrant - SpotcheC.k-~;;Type ..-sKL~l:lF/SKL-s or SKL-HF/S ~~:s*-~0~~ ~'..:.:.t.: "I (3) Penetrant. Remove~-----* Spotcll~~k, Type SKC-S * : - !'... ~** ..*. j
( 4) Developer ~. Spotcneck~ .cT.y_p_e: SKb-S (5) A thermometer, certified as.*described' in Paragraph: s.2;- 9 ':..::.:.*
'- ".:_ *:c ;* I I
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-~--
f I I ' Form QA 3-2
. -----------_/.
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~ .
_SwRI-NDT-200-1 SOUTHWEST RESEARCH INSTITUTE_**~ Revision 70
' . *- -- June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 16
* **** ~-: * '* J
-~* *-*~**
i 5 .4 *Safety Precautions * -* .... - **** - u ...
, . Safety precautions in accordance with instructions furnished with each mariufacturer's penetrant material shall be observed. Eighly volatile sol-ven~s shall be used cautiously since the vapors may be toxic and the liquids may irritate.,the skin. Extreme care should be exercised in handling highly flam-mab:le solvents.
i
- 6. I EXAMINATION METHOD j
1 6.1 - ,Surface Condition Unless otherwise specified by the customer, all penetrant examina-tions shall be performed on components in their final surf ace condition.
- The surface to be examined and all adjacent areas within 1 inch stiall be dry_ and free from dirt, grease, lint; scale, welding flux, weld spatter, oil, paint, or any other extraneous matter to the extent that it shall not obscure surface openings or otherwise interfere with the examination.
i I
! CAUTION I
Btasting with shot or dull sand may peen discontinuities on the surf ace and
~hall not be used.
NOTE Where surface conditions are not in accordance with Paragraph 6.1 and correction is not.feasible, SwRI will conduct the examination only *at the request of the cus*eomer. The specific surface condition and its probable effect on the exami-
'nation shall be noted on the SwRI Liquid l~n.~t;ant Examination Recor~.
I 6.2 Preexamination Cleaning
- i .......:.:..:_ !l'he surface to be examined and ~-d,'jilcent:areas within at least 1 incn
'shal1 ba.th9roughly washed with precleaner Jn .such a manner that foreign mate- ! rial and contaminants are removed. , :
**( ,-,,,The examination surface shall then be wiped dry with a lint-free cloiti:or ~bsor~ent paper, allowing a minimum ?f.5 minutes for complete evaporatiop._*.- ., -.
~.
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SwRI Form QA 3-2
SwRI-NDT-20~1-m*--~* **-*~.. *--1 SOUTHWEST RESEARCH INSTITUTE Revision 70 ... -..) June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 16.:_'.
.- -... *~*-***~- .... i i
6.3 Temperature Readings .i i
'- I After preexamination cleaning and before application of penetrant, the temperature of the examination surface and penetrant shall be measured and recorded on the SwRI Liquid Pe_netrant ~xamination .Record. The serial numbar 'of..~: * ::,'>:;
the thermometer used shall also be recorded. The temperature of the penetrant - '* , . ,. ""
- and the surface shall not be below 60°F nor above 125°F throughout the examina-;:,?.;~ :;:;*~ i tion period. -~\~0~ ~.'ds~ I 6.4 Application of Penetrant The penetrant shall be taken from a pr~ssurized container to *,ensu*re:*
its purity. It shall be applied by brushing or spraying and shall evenly cover all areas of the surface being examined.
*- '* '\. ; ~- :: ~ *- -*
The allowable minimum and maximum penetrant dwell times shall be as i follows:
,7:~ ~ :-; ~ ~: *11.
- Component Temperature (°F) 60-70 71-90 91-100 101-125 Dwell Time (Minutes) . -
20-30 10-3.0 10-20 10-15
. -:*-tL:.e;Qc
<; : . *: .i2.!;;,.'.
~ *n
- i I I
'..! .::.S: I
. When examinations are to be performed on components whose tempera- [
ture is below 60°F or above 125°F, this procedure shall be qualified in accor- / dance with .the requirements of Section V, Article 6, .Subarticle T-647. . The penetrant shall riot be allowed to dry. If drying occurs, the_,, . 1 penetrant shall be removed and the process repeated, starting with the preexam:i,_'.'";,_:.;~, JI nation cleaning of Paragraph 6.2. ~ nc .::.sJ: Removal of Excess Penetrant Initially, the excess. pe:rtefrant shall be removed by wiping the sur-f ace with clean,* dry, lint-free cloths or absorbent paper until most' tt'aces- o~}~:.r. 2 excess penetrant have been removed.
-~- ~* ,_ .
*-- * *. - , Lr:F L*..:;
I A clean, dry, lint-fr~ii cloth or absorbent paper shall'-then be moistened with penetrant remover, and the surface shall be wiped lightly unt~!c*~ all remaining traces of. excess penetrant have been removed. Extreme c;;tre~ sh!a.J.J.-~; be employed to avoid the use of an excessive amount of remover in order to pre-clude the removal of penetrant from discontinuities. i i The surface shall not be flushed nor receive direct application of remover prior to* the application of the developer. I SwRI Form QA 3-2 ....._.---------...J....i
SwRI-NDT-200-1 SOUTHWEST RESEARCH 1Nsr1TUTE Revision 70 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 16 6.6 Drying The surface shall be .completely dry prior to the application of th,e developer. Drying time shall be a minimum of S minutes to a maximum of 30 min-utes a,fter the excess penetrant has been removed. 6.7 Aoplication of Developer After sufficient agitation of the pressurized container to ensure that the particles in suspension are dispersed, a smoo.th, uniform layer of the suspended powder shall be sprayed onto the surface. The developer shall be used sparingly. The proper developer thick-ness will dry to a thin, translucent layer. 'If the coating is too thick, it may mask indications. The examination surface shall be observed during the applica-tion of' the developer to monitor the behavior of indications which tend to bleed-out profusely. i
/ Final interpretation of indications shall be made a minimum of 7 minutes to a maximum of 30 minutes after the developer has been applied.
7* EXAMINATION
.&.1 Examination Areas (1) The examination area for-Class 1 and 2 longitudinal and cir-cumferential welds shall be the weld and adjacent base mate-rial for a distance of 1/2 inch on each side of the weld as shown in attached Figure 1.
(2) Class 1 longitudinal welds shall be examined along the entire length of the weld during the preservice examination and for at least one pipe-diameter length or 12 inches, whichever is less, from the fusion line of the intersecting circumferen-tial weld during inservice examinations.
,_ - ._ ~~ ...
(3) Class 2 longitudinal welds shall be examined for at least 2-l/2t length from the fusion line of the intersecting circum-ferential weld during preservice and inservice examinations *
-*--~----- .........
SwRI Form QA 3-2
- SwRI-NDT-200-1 SOUTHWEST RESEARCH INSTITUTE Revision 70 June 1987 NUCLEAR PROJECTS OPERATINGPRQCEDURE Page 7 of 16 .-*-*-~
(4) The examination area.for Class 2 branch connections shall be the weld and 1/2 inch of base material on each side of the
.;..?::-.. (
**--*-..,___****-.. I weld fusion line, and for Class 1 branch connections the '-* ,_. . .I examination area shall be as shown in Figure 2.
EXCEPTION the Class 2 branch connection is a set-in type, the examination area shall the weld, 1/2 inch of base material on the main run pipe side from the weld sion line, and.the base material on the branch pipe side from the weld fusion 2'.S::~i I ne to the end of the radius section.
. . r:*. i I
(5) The examination area for Class 1 and 2 support attachments, ; I
*integral attachment welds, and support circumferential weld .:..t~ . ~J.; I joints shall be the weld and 1/2 inch of base material on :.. *. **:- ::;2i./f:l each side of the weld fusion line as shown in Fig~re 3 or Figure 4, as applicable.
(6) *The examination area fa~ Class 1 socket welds in piping shall be the weld, 1/2 inch of base material on the pipe side, and 1.0 inch of base material on the fitting side as shown in attached Figure 1. (7) The examination area for control rod drive housing welds shall be as shown in attached Figure s. (8) The Examination areas for vessel head-to-flange weld joints shall be as shown in Figure 4. (9) The examination areas for Class 2 nozzles shall be as shown in Figure 6. 7.2 Examination Methods Examinations shall be performed by placing the eye within 24 inches the surface to be examined and at an angle no less than 30 degrees with the rface to be examined. A mirror may be used to improve the angle. In addition general lighting, additional illumination of the examination area shall be ovided at right and oblique angles to expose indications. The illumination all be adequate to ensure no loss of sensitivity
- Form QA 3*2
-**-*~
.. .: ~: ri1< 1 =1 -
iRv~*2 I
SwRI-NDT-200-1 SOUTHWEST RESEARCH INSTITUTE Revision 70 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 16 If the examination surface is sufficiently large to preclude com-plete examination within the prescribed times, the surface shall be examined in* suitable increments. 7.3 Postexamination Cleaning The developer and penetrant shall be removed by wiping the surface thoroughly* with cloths saturated with a suitable solvent. Spraying directly on the examination areas with pressurized containers shall be allowed for postexam-ination cleaning. The surface shall then be wiped dry with clean, lint-free cloths or absorbent paper. 7.4 Reexamination Indications that are believed to be nonrelevant shall be reexamined to verify whether actual defects are present. Surface conditioning may precede the reexamination. Nonrelevant indications and broad areas of pigmentation that would mask indications are unacceptable. NOTE Indications that are obviously nonrelevant such as stamp marks or radiograph punch marks, shall only be recorded as a general remark on the SwRI Liquid Pene-trant Examination Record.
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the 'applicable revision of SwRI Nuclear Projects Operating Procedure IX-FE-116.
I
, 8.1 Linear Indications (Class 1 and Class 2) r'
._ Linear indications in welds, base material, and support attachments sh~l be recorded on the SwRI Liquid Penetrant Examination Record and reported to;' the customer in accordance with the recording criteria table below:
) Overall Indication Length Nam. Wall Thickness As Defined in Attached Figure 7 (Inches) (Inches) .
Less than 1.0 1/8 1.0 to less than 2.5 3/16 I 2.5 and greater 1/4 i L .___, _,,,_ ... ~*- SwRI Form QA 3-2
SwRI-NDT-200-1 SOUTHWEST RESEARCH INSTITUTE Revision 70 June 1987 ****~~-- ......,.._
- "'\ ,.
NUCLEAR PROJECTS OPERATING PROCEDURE . Page 9 of *16 *,' :: EXCEPTION In Class 2 nozzles, the following linear-.indications shall be recorded:. any linear indication greater than 1/16 inch lo.ng for materials less than 5/8 inch thick, greater than 1/8 inch long for materials from 5/8 inch to less than -:: *-:.~} S 7 E .~ .:; 2 inches thick, and 3/16 inch long for material 2 inches and greater in . S.; --:f'_s_.:;- .!' .:::.. i thickness. I I 8.2 Rounded Indications (Class 2)
*Rounded indications shall be recorded as follows:
I (1) Rounded indication with dimensions greater than 1/8 inch for thicknesses less than 5/8 inch and dimensions greater than 3/16 inch for thicknesses 5/8 inch and greater. r t I I (2). Four or more rounded indications in a line separated by I 1/16 inch or less. (3) Ten or more indications in any six square inches of area whose major dimension is no more than 6 inches with the . ...: "";. .5 v* o:; I I dimensions taken in the most unfavorable locatio'n relative ~ :'c'!O'J Drfj to the indications being evaluated. When conditions limit the area of examination, the limitations _,,Cc,:;: bluow I j shall be recorded. j
- .:.fi."':I I j
- 9. EVALUATION r:.:, D1J c- I
- t*:.,**~-j ' I J Initial evaluation.of reportable indications shall be performed by SwRI per- I :i sonnel, and shall be conducted in accordance with the applicable ASME Boiler and .
Pressure Vessel Code, Section XI, Article IWA-3000. Final evaluation and dispo-
,s I j
""' II sition of reportable indications shall be the responsibility of the customer. .,:~::. j
- 10. RECORDS j
_* *, E j Documents generated in accordance with this procedure shall be stored as / j specified in the SwRI Project Plan. The customer shall receive copies of these j documents in the Examination Report, unless specified otherwise in the SwRI ** '-"c -1 rfe f Project Plan. ** c ~,,, °" I j j j I J j j j j RI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE ~ ~ NUCl.EAR PROJECTS OPERATING PROCEDURE SwRI-NDT-200-1 Revision 70 June 1987 Page 10 of 16 FIGURE l Exam. surface~
! A- B 1 in.
- I l
Profile of valve body, vessel nozzle, or pump connection _ ___,,_....,:;.._ _ Weld end buttering (where applied) B A Inner surface (a) Soc:ka: we.ld Profile of valve body. Exam. surface A- B .
*Sl ,(\*
~ ( vessel nozzle, or
. pump connection
_. 1/2in. I~ 1/2 in. .._
- y
--.+o-/""',__ __ Weld end buttering A * ,,.,... B (where applied) ... -------------++-----~
Inner surface (b) 3u:: W' eld SIMILAR AND DISSIMILAR METAL WELDS IN COMPONENTS AND PIPING
SwRI-NDT-200-1 OUTHWES.T RESEARCH INSTITUTE Revision 70 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 11 of 16 . -
* - TltE USSltR OF I/at OR l =re; i H t - o..MINATIONS\IRFACE A-a r: - UDI!1S SZc=IO!l
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c:..i\SS l BRANCH CONNECTION WE!.DS ( sur:a.ce exami:c.a:icn requirement:s) I i I I
.........~.-~ _ .._J wRI Form QA 3*2
SOUTHWEST RE.SEARCH INSTITUTE NUC!.EAR PROJECTS OPE!iATING PROCEDURE SwRI-NDT-200-1 Revision 70 June 1987 Page 12 of 16 112; *. F :..i 1/2 ;.. ..:. Surf. **mn.,., T
--A-8 l/2in.
' A 0 INTEGRAL ATTACHMENT rwa-........
n:~J,
- 112 ;.. SU::ace e."ta::ii:at:ion a:-sa~:
A-a and C-0 !OT Cl.a.ss l 1/2 in. e:m;:ioueut:s; A-a :o~ c:.ass : CO~OUl!!l'CS
~ '"'..,., 111acn,....,
'-------.1 INTEGRAL ATTACHMENT WELD
EST RESEARCH INSTITUTE SwRI-NDT-200-1 Revision 70 June 1987 ; .. ,,,,;
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NUCLEAR PROJECTS OPERATlNG PROCEDURE Page 13 of 16 I
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*~' ' ...... ~-..-... ~,*
ni::m:s: 4 HEAD-TO-FUNG£ WELD JOINT
~'
112 in.
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--+--.-
_J i U21n. SUPPORT CIRCUMFERENTIAL WELO JOINT
SOUTHWEST RESEARCH INSTITUTE NUCl..EAR PROJECTS OPERATING PROCEDURE SwRI-NDT-200-1 Revision 70 June 1987. Page 14 of 16 lal J (di 1/2 In. 8 lbl lei _J 1.i 112 in. _I ill Surta E.xaminauan A,.. A-a CONTROL ROD DRIVE HOUSING WELDS n:cmu: 5
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-200-1 Revision 70 June 1987 NUCl..EAR PROJECTS OPc~A TING ?ROCEOURc Paa:e 15 of 16 Exam. surf. A - !3 A 1/2 in. __l 112 in. I 9
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l*J I I Exam. surf. A - B 1/2 in. B I
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--------111""-----....}-1.. I lb)
I REQUIREMENTS FOR CLASS 2 NOZZLE-TO-VESSEi. WELDS I
--***-~.,-._ I
30UTHWEST RESEARCH INSTlTUTE NUCl..EAR PROJECTS OPERATING PROCEDURE SwRI-NDT-200-1 Revision 70 June 1987 Page 16 of 16
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I LINEAR SURFAC~ INDil:.'i.TIONS IllUSD'lllivie Flaw CQmlqurations and Jetemnnman at ~ e m QA J..2
PROCEDURE DEVIATJON .. 2 Page 1 of Pages ocedure 200-3 Revision No. 8 Deviation N9. 2 Rl-NDT-e following examination areas are affected by this deviation: viation 2 supersedes Deviation 1. uid penetrant examinations to be performed in accordance with this procedure. following paragraphs shall be deviated from as indicated: ange Section 8 Recording Criteria to Read as follows: RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision SwRI Nuclear Projects Operating Procedure IX-FE-116.
- 8.1 Linear Indications Linear indications shall be recorded on the SwRI Liquid Penetrant Examination Record and orted to the customer for di,sposition in accordance with the recording criteria table below: *
- Nominal Wall Thickness (Inches)
Less than 1.0 1.0 to less than 2.5 Overall Indication Length as Defined in Attached Figure 1 (Inches) 1/8 3/16 2.5 and greater 1/4 ontinued ori Page 2) onale for deviation: is deviation incorporates recording criteria as requested by Public Seryice Electric and Gas Company. iation Affects If the deviation is determined to affect the prcced4'~ lification YES D . NO ~ qualification. the deviation shall be qualified in accordance wi1h Procedure IX*FE-107. APPROVALS ten by: Date: Date: ** * -
/}7!". )?. 7 {" -'f '?"
I
*1 Is f£/3. '28 Verbal Appro Date: * * *' ;:.
ager of Q.A.~f1i>7'f"f Date: Cognizant Director: Date: yc.J~ FORM FE-4-6
---*--~
PROCEDURE DEVIATION Procedure SwRI-NDT-200-3 Revision No. 8 Deviation No. 2 Page 2 of2 The following paragraphs shall be deviated from as indicated (Cont.): For Preservi.ce examination, indications with a length of 1/16 inc~ ih ferritic piping less than .312 inches in thickness shall be recorded. Rounded indications shall be recorded based on diameters corresponding to the linear indication recording criteria and reported to the customer for disposition. When conditions limit the area of examination, the limitations shall be recorded.
PROCEDU~E D.EVIATJON Page 1 of
- 1 Pages Revision No. Deviation No.
200-3 8 3 llowing examination areas are affected by this deviation: s examined in accordance with this procedure using water washable liquid trant materials. supplied in bulk. . llowing paragraphs shall be deviated from as indicated: to the end of first paragraph of 6.4: Bulk materials may be used provided precautions are taken to ensure the purity of the materials and application ces. to the end of first paragraph 6.7: Bulk materials may be used provided all autions are taken to ensure the purity of the materials and application ces . ale for deviation: llow the use of bulk materials. If mo deviation is determined to affect tho procedure on Affects cation YES 0 NO Gg qualification, tne dl!Yiation shall be qualified in xcordanca with Procedure IX*Fe-107. APPROVALS SA ,,Cl.dJ n by: Date: Date: May 9, 198 Ingam~ls
- 5/9/89 Verbal Approval Given? rs:;! Yes 0No IMav Date:
- 9. 198 er of Q.A.: k;ftJ
- Date: Cognizant Director: Date: .
J.0.J~ !Jud ~1<~- AM FE-4-6
SwRI-NDT- 200-3. SOUTHWEST RESEARCH INSTITUTE Revision 8 ~ NUCLEAR PROJECTS December 1987 ~ OPERATING PROCEDURE Page 1 of 15 VISIBLE WATER-WASHABLE LIQUID PENETRANT EXAMINATIONS EFFECTIVITY AND APPROVAL 8 of this procedure became effective on Dec 11
- 1987. Other revisions of the base document may ve concurrently.
5 - - - - - - - - - - - - - - fLJ) Technical Review dr/a Date fl" :v ec.- 17<1J
~ Date Date
'1,1 /
.._.,,Jll I :: -
4..-~
*t1 j
// Dec i 'ii7 I. {7;//IJ Ir..-?
I he following information may be used for convenience. clpletion of this portion is not mandatory. o. ve ection(s) A-40A*O
SwRI.:NDT-200-3 SOUTHWEST RESEARCH INSTJTUTE Revi~ion 8 NUCLEAR PROJECTS OPERATING PROCEDURE December 1987 Page 2 of 15 VISIBLE WATER-WASHABLE LIQUID PENETRANT EXAMINATIONS SwRI-NDT-200-3
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure a proper water-washable liquid penetrant examination of nonporous austenitic or carbon steel materials in accordance with the applicable American *society of Mechanical Engineers. (ASME) Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION (1) The water-washable method of liquid penetrant examination shall be employed as specified in the procedure for the detection of ~urf ace discontinuities in austenitic or.carbon steel material.
(2) Components and welds to be examined are specified in the applicable Southwest Research Institute (SwRI) Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Applicable Examination Record SwRI-NDTR Form No. 17-11, revision dated 1-3-79
- 4. RESPONSIBILITY (1) The Director o~ the Department of Engineering Services, Nondestruc-tive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of "this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan. SwRI Form QA 3-2
SwRI-NDT-200-3 Revision 8 December 1987 Page 3 of 15 (3) The examiner shall be responsible for implementing the requirements of.this procedure. (4) The Manager of the Support and Administration Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control.. "
5.2 Material/Eguipment Certification The penetrant materials used shall be certified for sulfur content and total halogens in accordance with SD-129 and SD-808 of Article 24, Sec-tion V. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Certified reports for all surface contact materials to be used for penetrant examinations, giving batch numbers and analysis results, shall be obtained from the supplier. Copies of the certified reports shall be retained I with the examination records. I
*I Equipment used to measure surface temperature shall have been cali-brated and certified, and shall display a valid calibration tag as required by NQAP 10-1.
5.3 Materials and Eouinrnent The following materials and equipment shall be used for examinations performed in accordance with this procedure: (1) Precleaner - Uresco Type K-410C, or MET-L-CHEK Type E-59 (2) Penetrant - Uresco Type P-303A, or MET-L-CHEK Type VP-30 (3) Penetrant Remover - Reactor Grade Yater (4) Developer - Uresco Type D-495A, or MET-L-CHEK Type D-70 (5) A thermometer, certified as described in Paragraph 5.2 SwAI Form QA 3-2
SwRI-NDT-200-3 SOUTHWEST RESEARCH INSTITUTE Revision 8
. December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page *4 of 15 5.4 Safety Precautions Safety precautions in accordance with instructions furnished with each manufacturer's penetrant material shall be observed. Highly volatile solvents shall be used cautiously since the vapors may be toxic and _the liquids may *irritate the skin. Extreme care should be exercised in handling highly flammable solvents.
- 6. EXAMINATION METHOD 6.1 Surface Condition Unless otherwise specified in the contract, all penetrant examina-tions shall be pe~formed on components in the final surface condition.
The surface to be examined shall be free of scale, slag, dirt, grease, weld spatter, oil, paint, or any other extraneous matter that 'lotOuld obscure surface openings or otherwise interfere with the examination. ( CAUTION Blasting with shot or dull sand may peen discontinuities on the surface and shall not be used. Where surface conditions are not in accordance with Paragraph 6.1 and correction is not feasible, SwRI will conduct the examination only at the request of the customer. The specific surface condition and its probable effect on the exam-ination shall be.noted on the SwRI Liquid Penetrant Examination Record. 6.2 Preexamination Cleaning The surface to be examined and adjacent areas within 1 inch shall be thoroughly washed with precleaner in such a manner that foreign material and contaminants are removed. The examination surface shall then be wiped dry with a lint-free cloth or absorbent paper, allowfng a minimum of 5 minutes for complete evaporation. 6.3 Temperature Readings The ser~al number of the thermometer used and the examination surface temperature (after the preexamination cleaning and before application of the I penetrant) shall be recorded on the SwRI Liquid Penetrant Examination Record . SwRI Form QA 3-2
SwRI-NDT-200-3 SOUTHWEST RESEARCH INSTITUTE Revision 8 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 15 6.4 Application of Penetrant The penetrant shall be taken from a pressurized container to ensure its purity. It shall be applied by brushing or spraying and shall evenly cover all areas of the surf ace .being examined. The allowable minimum and maximum penetrant dwell times shall be as follows: Component Temperature (°F) Dwell Time (Minutes) 60-70 20-30 71-90 10-30 91-100 10-20 101-125* 10-15
'When examinations are to be performed on components whose temperature is below 60°F or above 125°F, this procedure shall be qualified in accordance with*the requirements of Section V, Article 6, Subarticle T-680.
The penetrant shall not be allowed to dry. If drying occurs, the penetrant shall be removed and the application process repeated. 6.5 Removal of Excess Penetrant Excess penetrant shall be removed with a coarse water spray. Water pressures over 50 psi or water temperatures over ll0°F shall not be employed. Water pressure and temperature shall be recorded on the SwRI Liquid Penetrant Examination Record. Extreme care shall be exercised to preclude the removal of penetrant from discontinuities. In situations where controlled water rinsing facilities are not available or water rinsing operations are not appropriate, the excess penetrant shall be removed by wiping the surface with a lint-free cloth or absorbent paper dampened with reactor grade water. 6.6 Drying The surface shall be dried by blotting with clean lint-free cloth or absorbent paper. The surface shall be completely dry prior to application of the developer . Drying.time shall be a minimum of 5 minutes to a maximum of 30 min-utes after the excess penetrant has been removed. SwAI Form QA 3*2
SOUTHWEST RESEARCH INS.TITUTE SwRI-NDT-200-3 Revision 8 NUCLEAR PROJECTS OPERATING PROCEDURE December 1987 Page 6 of 15 6.7 Apulication of Developer The wet developer shall be applie~ by spraying from a pressurized container. After sufficient agitation of *the pressurized container to.ensure that the particles in the suspension are dispersed, a smooth, uniform layer of the suspended powder shall be sprayed onto the surface. The developer shall be used sparingly. The proper developer thick-ness will dry to a thin, translucent layer. If the coating is too thick, it may mask indications. *The examination surface shall be observed during the application of the developer to monitor the behavior of indications that tend to bleed-out profusely. Final interpretation of indications shall be made a minimum of 0 7 minutes to a maximum of 30 minutes after the developer has been appl i_ed.
- 7. EXAMINATION 7.1 Examination Areas Components, parts, and methods of examination shall be as specified in ASME Boiler and Pressure Vessel Code, Section XI, Tables IWB-2500 and IWC-2500.
(1) The examination area for Class 1 and 2 longitudinal and circum-ferential welds shall be the weld and adjacent base material for a distance of 1/2 inch on each side of the weld as shown in attached Figure 2. (2) Class 1 longitudinal welds shall be examined along the entire length of the weld during the preservice examination and for at least one pipe-diameter length or 12 inches, whichever is less, from the fusion line of the intersecting circumferential weld during inservice examinations. (3) Class 2 longitudinal welds shall be examined for at least 2-l/2t length from the fusion line of the intersecting circum-ferential weld during preservice and inservice examinations. (4) The examination area for Class 2 branch connections shall be the weld and 1/2 inch of base material on each side of the weld fusion line, and for Class 1 branch connections the examination area shall be as shown in Figure 3. SwRI Form QA 3-2
UTHWEST RESEARCH INSTITUTE SwRI-NDT-200-3 Revision 8 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 15 EXCEPTION If the Class 2 branch connection is a set-in type, the examination area sh~ll be the weld, 1/2 inch of 'base material on the main run pipe side from the weld fusion line, and the base material on the branch pipe side from the weld fusion line to the end of the radius section. (5) The examination area for Class 1 and 2 support attachments, integral attachment welds, and support circumferential weld joints shall be the weld and 1/2 inch of ~ase material on each side of the weld fusion line as *shown in Figure 4 or Figure 5, as applicable. (6) The examination area for Class 1 socket welds in piping shall
,be the weld, 1/2 inch of base material on the pip~ side, and
- 1. 0 inch of base material on the fitting side as shown in attached Figure 2 .
- (7)
(8) The examination areas for vessel head-to-flange weld joints shall be *as shown in Figure 5. The examination areas for Class 2 nozzles shall be as shown in Figure 6. 7.2 Examination Methods Examinations shall be performed by placing the eye within 24 inches of, and at an angle no less than 30 degrees with the surface to be *examined. A mirror may be used to improve the angle. In addition to general lighting, additional illumination of the examination area shall be provided at right and oblique angles to expose indications. The illumination shall be adequate to ensure no loss of sensitivity. If the examination surface is sufficiently large to preclude complete examination within the prescribed times, the surface shall be examined in suitable increments. 7.3 Postexamination Cleaning The developer and penetrant shall be. removed by wiping the surface thoroughly with cloths saturated with a suitable solvent or by spraying the surface thoroughly with* reactor-grade water. 7.4 Reexamination Indications that are believed to be nonrelevant shall be reexamined to verify whether actual defects are present. Surface conditioning may precede I Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-200-3 Revision 8 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 15 the reexamination. Nonrelevant indications and broad areas of pigmentation that would mask indications are unacceptable. Indications. that are obviously nonrelevant, such as' stamp marks or radiograph punch marks, shall be recorded only as a general ~emark on the SwRI Liquid Penetrant Examination Record.
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-116. Overall indication length shall.be recorded as defined in attached Figure 1.
The following indications shall be recorded on the appropriate SwRI Liquid Penetrant Examination Record and reported to the customer: 8.1 Base Material Indications (1) Linear Indications greater than 1/16-inch long for materials less than 5/8-inch thick, greater than 1/8-inch long for materials from 5/8-inch thick to under 2 inches thick, and 3/16-inch long for materials 2 inches thick and greater (2) Rounded indications with dimensions greater than 1/8 inch for thicknesses less than 5/8 inch, and greater than 3/16 inch for thicknesses 5/8 inch and greater (3) Four or more indications in a line separated by 1/16 inch or less, edge-to-edge (4) Ten or more indications in any 6 square inches of area that has a major dimension of no more than 6 inches, with the dimensions taken in the most unfavorable lo~ation relati~1e to the indications being evaluated 8.2 ~eld Indications (1) Cracks or linear indications (2) Rounded indications with dimensions greater than 3/16 inch (3) Four or more indications in a line separated by 1/16 inch or less, edge-to-edge I Form QA 3-2
SwRI-NDT-200-.3 D.WEST RESEARCH INSTITUTE Revision 8 December 1987
~ NUCLEAR PROJECTS OPERATlf'.:IG PROCEDURE ~15)
IV7 /7 Page 9 of 15 (4) Ten or more rounded indications in any 6 square inches of surface, with the major dimension of the area not to exceed 6 inches when the area is taken in the most unfavorable loca-tion relative to the indications being evaluated EVALUATION Initial evaluation of reportable indications shall be performed by SwRI onnel. Final evaluation and disposition of reportable indications shall be responsibility of the customer and shall be conducted in accordance with pplicable ASME Boiler*and Pressure Vessel Code, Section XI, Article 3000. RECORDS Documents generated in accordance with this procedure shall be stored as ified in the SwRI Project Plan. The customer shall receive copies ~f these
~s in the Examination Report, unless specified otherwise in the SwRI ~Plant .
A 3-2
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SwRI-*NDT- 200- 3 .OUTHWEST RESEARCH INSTITUTE Revision 8* December 1987
~. NUCLEAR PROJECTS OPERATING PROCEDURE Page 11 of 15 I
Exam. suriac:t! ~ Profile of valve bOdV, A-B I vMSl!ll nozzle, or I ( . pumP connection 1 in.
\ 1
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"' \wnere applied!
B A 1nn1r surface Profile of valve bodV
- vessel nozzle. or SIMILAR AND DISSIMILAR METAL WELDS IN COMPONENTS AND PIPING
- . sUR.FACE EXAMINATION SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-200-3 Revision 8 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 12 of 15 F!GU'R~ 3
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SwRI-NDT-200-3 Revision 8 NUCLEAR PROJECTS OPERATlNG PROCEDURE December 1987 Page 13 of 15 8
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IWll~ INTEGRAL ATTACHMENT urface e..~aminacion areas: -3 and C-iJ 1/2 'in. 1/2 ln. l.nte9fal &ttlC:fUT_,.t IWB Bounoarv S..rt. S.-.-A-s-c-o INTEGRAL ATTACHM£14T WELD m QA 3-2
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-200-3 NUCLEAR PROJECTS OPERATING PROCEDURE Revision 8 December 1987 Page 14 of 15
- FIG"u~ S
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UTHWESTRESEARCH.INSTITUTE SwRI-NDT-200-3 Revision 8 December 1987
. NUCLEAR PROJECTS OPERATING PROCEDURE Page 15 of 15 Exam. surf. A - 8 A
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!bl SURFACE EXAMINATION REQU1REME1'41S FOR CLASS 2 NOZZLE-TO-VESSEL WELDS SwRI Form QA 3-2
00-1 PROCEDURE OEViATJON* xamination areas are affected by this deviation: Revision No. 35 Page 1 of 2 I Deviation No. 3 Pages nt magnetic particle examinations to be performed in accordance with this procedure. ragraphs shall be deviated from as indicated: ragraph 7.3 Examination Method to read as follows: mination Method ble electromagnetic yoke pole spacing shall be a maximum of 9.0 inches, measured on the rial surface between the centerline of the poles. The straight ~ne distance measured between enterline of the poles shall be no greater than 6.0 inches and shall not exceed the distance during calibration verification. dry magnetic particles used shall be applied by lightly dusting a small quantity over the i.on ~- If a pneumatic applicator is used, the excess shall be removed with a gentle
~f air: .
AC electromagnetic yoke shall remain activated during the application and removal of excess rial. , d on Page 2) ation: tion incorporates examination technique and recording criteria as requested by Public Service d Gas Company. If the deviation is determined :o affect :he procedure , YES 0 NO liJ qualification. the deviation shall ce oua!if:ed in acccrdance with Procedure IX*FE-107. 1 APPROVALS SA .A.J) Date: Technical Review: /L ~ -/& ~ Verbal Approval Given? 0Yes
~No Date: ~ Date:
1 Cognizant Director: Date: c.J~ M l/Uw1tkpW
PROCEDURE DEVIATION
- Procedure SwRI-NDT-300-1 l I Revis~on No. 35
- Deviation No. 3 Page2 of2 The AC electromagnetic yoke shall be applied twice in each examination area with the lines of flux at right angles (in the case of welds, the magnetic flux will be induced when component configuration permits, parallel and transverse to the weld). Sufficient overlap shall ensure the entire examination area is covered.
Broad areas of particle accumulation which might mask indications from discontinuities are unacceptable, and shall be cleaned and reexamined. Change Section 8, RECORDING CRITERIA. to read as follows:
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Nuclear Projects Operating Procedure IX-FE-116.
8.1 Linear Indications Linear indications shall be recorded on the SwRl Magnetic Particle Examination Record and reported to the customer for disposition in accordance with the recording criteria table below: Nominal Wall Thickness Overall. Indication Length as defined in Attached Figure 5
<Inches) <Inches)
Less than 1.0 1/8 1.0 to less than 2.5 3/16 2.5 and greater 1/4 For preservice examination, indicntions with a length of 1/16 inch in ferritic piping less than .312 inches in thickness shall be recorded. Rounded indications shall be recorded based on diameters corresponding to the linear indication recording criteria and reported to the customer for disposition. When conditions limit the area of examination, the limitations shall be recorded.
SwRI - NDT - 3 OO*- 1 SOUTHWEST RESEARCH INSTITUTE Revision 35 NUCLEAR PROJECTS December 1987 OPERATING PROCEDURE Page 1 of 13 DRY POWDER MAGNETIC PARTICLE EXAMINATION EFFECTIVITY AND APPROVAL on 35 of this procedure became effective on Dec 11 ' 1987. Other revisions of the base document may ective concurrently. SA ls fLJ) c.fY. Date Date 1;7./i 6/1 l The following information may be used for convenience. Co pletion of this portion is not mandatory. n No. ective re Section(s) m QA*40A*O
SOUTHWEST.RESEARCH INSTITUTE SwRI-NDT-300-1 Revision 35
~ NUCLEAR PROJECTS OPERATING PROCEDURE December 1987 Page 2 of 13 DRY POWDER MAGNETIC PARTICLE EXAMINATION SwRI-NDT-300-1
- 1. PURPOSE This procedure.provides the technical information and detailed steps required to ensure a proper dry powder magnetic particle examination of ferro-magnetic material in accordance with the applicable American Society of Mechan-ical Engineers (ASME) Boiler and Pressure Vessel C~des.
- 2. SCOPE AND APPLICATION (1) This procedure shall be utilized for the dry powder magneti~ particle examination of ferromagnetic materials employing alternating current (AC) yoke techniques.
(2) Areas to be examined shall be ferritic components, longitudinal and circumferential welds, support attachments, and butt and fillet welds of branch connections as specified in the applicable Southwest Research Institute (SwRI) Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Applicable Examination Reco~d
_ SwRI-NDTR Form No. 17-12, revision dated 11-26-79
- 4. RESPONSIBILITY (1) The Director of th~ Department of Engineering Services, Nondestruc-tive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure .
wRI Form QA 3-2
- rwEsT RESEARCH INSTITUTE SwRI-NDT-300-1 Revision*3~
p NUCLEAR PROJECTS OPERATING PROCEDURE December 1987 Page 3 of 13 The Project.Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified .in the appli-cable SwRI Project Plan. The examiner shall be responsible for implementing the requirements of this procedure. The Manager of the Support and Administration Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with this procedure. NNEL AND EnUIPMENT Personnel Certification Personnel shall be certified in accordance with SwRI NQAP ll-1, P . s s Control."
- Eauipment (1) AC electromagnetic yokes to be utilized shall have a lifting power of 10 pounds or greater at a pole spacing of 3 to 6 inches. Each yoke shall be calibrated at least once a year, or whenever the yoke has been subjected to any repair, periodic overhaul, or damage, or has not been used for a year or more.
(2) A calibration block of a ferromagnetic material weighing a minimum of 10 pounds shall be used to confirm the lifting power of AC yokes. (3) Dry magnetic particles shall be utilized as the examination medium. The color selected shall provide adequate contrast with the examination area. (4) Dry magnetic particles shall be selected from the following: (a) Magnaflux Red No. SA Powder (b) Magnaflux. Grey No. 1 Powder (c) Magnaflu.~ Black No. 3A Powder (d) Dry magnetic particles equivalent to those specified above may also be used.
SOUTHWEST RES.EARCH IN.STITUTE SwRI-NDT-300-1 Revision 35 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 13 (5). Devices normally used for applic~~ion of dry magnetic particles are listed below: (a) Magnetic Particle Puffer Bottle, Model PB-1 (b) Magnaflux Pneumatic Applicator
- 6. CALIBRATION The applicable calibration block described in Paragraph 5.2 of this proce-dure shall be used to verify the proper operation of the AC electromagnetic yoke:
(1) Prior to a series of examinations (2) With any substitution of examinatio~ personnel (3) With any substitution of the AC power source (4) (5) (6) At least every 4 hours during the examination At the completion of a series of examinations
\.lhen the proper operation of the yoke is in doubt (7) At the maximum pole spacing to be used during the examination All electromagnetic yoke verification times shall be entered on the SwRI Magnetic Particle Examination Record.
- 7.
- EXAMINATION 7.1 Examination Area Components, parts, and methods of examination shall be as specified in ASME Boiler and Pressure Vessel Code, Section XI, Tables IWB-2500 and IWC-2500.
(1) , The e~amination area for Class 1 and Class 2 longitudinal and circumferential ~elds and support attachments shall be the weld and adjacent base material for a distance of 1/2 inch on each side of the weld.
- SwRI Form QA 3*2
THWEST RESEARCH INSTITUTE SwRI-NDT-300-1 Revision 35 ~ December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 13 I (2) Class 1 longitudinal welds shall be examined along.the entire length of the weld during the preservice examinatfon and for* at least one pipe-diameter length or 12 inches, whichever is less, from the fusion line of the intersecting circumferential weld during inservice examinations. (3). Class 2 longitudinal welds shall be examined for at least 2-l/2t length from the fusion line of the intersecting circum-ferential weld during preservice and inservice examinations. (4) The examination area for Class 1 branch connections shall be as
~hown on attached Figure 1.
(5) The examination area for Class 2 branch connections shall be the weld and 1/2 inch of base material on each side of the weld fusion line . EXCEPTION the Class 2 branch connection is a set-in type, the examination area shall the weld, 1/2 inch of base material on the main ru,n pipe side from the weld sion line, and the base material on the branch pip~ side from the weld fusion ne to the end of the radius section. (6) The examination .area for Class 1 and 2 support attachments, integral attachment welds, and support skirt circumferential I weld joints shall be the weld and 1/2 inch of base material on each side of the weld fusion line as shown in Figures 2 and 3. I (7) The examination area for Class 1 socket welds in piping shall I I be the weld, 1/2 inch of base material on the pipe side, and I 1.0 inch of base material on the fitting side. I (8) The examination areas for vessel head-to-flange weld joints shall be as shown in Figure 3. I (9) The examination areas for Class 2 nozzles shall be as shown in Figure 4. 7.2 Surface Preparation Examination shall be performed on components in the final surface ndition. orm CA 3-2
OUTHWEST RESEARCH INSTITUTE SwRI-NDT-300-1 Revision 35 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 13 The examination area of welds and adjacent base materials shall be of sh_arp surface irregularities such as deep valleys between stringer The examination area and a minimum of 1 inch on each side of the ination area shall be clean, dry, and free of oil, sand, rust, grease, g, °loose scale, or other surface conditions to the extent that they shall. mask indications of unacceptable discontinuities. After slag removal, as-welded surfaces shall be considered suitable, grinding, if the weld contour blends into the base material without ercutting.
- n surface conditions are not in "accordance with the above and correction is feasible, SwRI will conduct the examination only at the request of the tamer. The specific surface condition and its effect on ~he examination )
ll be noted on the SwRI Magnetic Particle Examination Record. At the iner's option, without precluding the requirements of Section 7.2 of this ocedure, a magnetic particle indicator as desc;ribed in Paragraph T- 754 of E Section V may be used to verify the adequacy of the magnetizing field. 7.3 Examination Method Variable electromagnetic yoke pole spacing shall be a maximum of inches, measured on the material surface between the centerline of the . les. The straight line distance measured between the centerline of the poles all be no greater than 6.0 inches and shall not exceed the distance used ring calibration verification. The dry magnetic particles used shall be applied by lightly dusting mall quantity over the examination ar~a. If a pneumatic applicator is used, excess shall be removed with a gentle stream of air. The AC electromagnetic yoke shall remain activated during the appli-ion and removal of excess material. The AC electromagnetic yoke shall be applied twice in the examination
- a. The second examination shall be conducted with the lines of magnetic flux roximately at right angles to the first application. Overlap shall be suffi-nt to ensure the entire examination area is covered.
ad areas of particle accumulation which might mask indications from discon-rm QA3-2
HWEST RESEARCH INSTITUTE SwRI-NDT-300-1 Revision 35 December ~987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 13 7.4 Postexamination Cleanin~ Arrangements shall be made with the customer for postexamination val of dry magnetic particles. Demagnetization of the examination area is not required. RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined e applicable revision of SwRI Procedure IX-FE-116. 8.1 Linear Indications (Class l and Class 2) Linear indications shall b~ recorded on the SwRI Magnetic Particle ation Record in accordance with the following table and reported -to the er: Overall Indication Length Nom. Wall Thickness As Defined in Attached Figure 5 (Inches) (Inches) Less than 1.0 1/8 1.0 to less than 2.5 3/16 2.5 and greater 1/4 8.2 Rounded Indications (Class 2) Rounded indications shall be recorded as follows: (1) Rounded indication with dimensions greater than 1/8 inch for thicknesses less than 5/8 inch and dimensions greater than 3/16 inch for thicknesses 5/8 inch and greater (2) Four or more rounded indications in a line separated by 1/16 inch or less (3) Ten or more indications in any six square inches of area whose major dimension is no more than 6 inches with the dimensions taken in.the most unfavorable location relative to the indica-tions being evaluated When conditions limit the area of examination, the limitations shall corded. QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-300-1 Revision 35 December 1987 Page* 8 of 13'
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI pe~sonnel, and shall be conducted in accordance with the applicable ASME Boiler and Pressure Vessel Code, Section XI, Article IWA-3000. Final evaluation and disposition of reportable indications shall be the responsibility of the customer.
- 10. RECORDS Documents generated in accordance with this procedure shall be stored as specified'in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan.
Swi'll Form QA 3*2
WEST RESEARCH INSTITUTE SwRI-NDT-300-1 Revision 35 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 13 FIGURE l Ito - rttE USS£R OF' l/2 t OR l :::m~:
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I I SwAl Form QA 3-2 I I
**~ PROCEDURE DEVIATION Page 1 of 2 Pages Revision No. I Procedure SwRl-NDT- 300-2 The following examination areas are affected by this deviation:
I 42 Deviation No. 4 Fluorescent magnetic particle examinations to be performed in accordance with this procedure. The following paragraphs shall be_ deviated from as indicated: Change Paragraph 5.3. Magnetic Particles to read as follows: 5.3 Magnetic Particles (1) A Fluorescent magnetic SUsi>ension shall be utilized as the examnation medium. It shall fluoresce with a color that will provide adequate contrast with the area being examined when illuminated by an ultravio~~t lamp of suitable characteristics. (2) Magnetic particles shall be suspended in a suitable liqnid medium in the concentration recommended in SE-709, "Standard Recommended Practice for Magnetic Particle Examination." Certified reports for magnetic particles, giving batch numbers and analysis results, shall be obtained from the supplier or by sample analysis of the batch to be used. Copies of the certified reports shall be retained with the examination record~. : (3) *Examination shall be performed utilizing Magnaglo No. 14.Ai.\1: aerosol-packaged fluorescent* magnetic particle material. Rationale for deviation: This deviation changes the material list and incorporates examination technique and recording criteria as requested by Public Service Electric and Gas Company, and clarifies the temperature requirements of the Code. If the deviation is determined to affect the ~rocedure Deviation Affects Qualification YES 0 NO. g qualification, the deviation shall be Qualified. in accordance with Procedure IX-FE-107. APPROVALS SA .PL-D Writ~en by: Date: Technical Revie;W1 /' ~-' /./.' //!:'
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Verbal Appr4 Givei I0 !SJ No Man~er of Q.A.:k~**/* - Date: Cognizant Director: Date: _i(1J~ :;./10//19 ~ ;/~~ ;f/'Jnef SwRI FORM FE-4-6
PROCEDURE DEVIATION Procedure SwRI-NDT-300-2 Revision No. 42 Deviation No. 4 Page 2 of2 Change 5.6 to read as follows: 5.6 Thermometer The thermometer to be used for measuring the component temperature shall be calibrated and certified and shall display a Valid calibration tag as required by NQAP 10-~. Change 7.3(4) under 7.3 Examination Method to read as follows: The AC electromagnetic yoke shall be applied twice in each examination area with the lines of flux at right angles (in the case of welds, the magnetic flux will be induced when component
- configuration permits, parallel and transverse to the weld). Sufficient overlap shall ensure the entire examination area is covered.
Change Section 8, RECORDING CRITERIA. to read as follows:
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Nuclear Projects Operating Procedure IX-FE-116.
8.1 Linear Indications Linear indications shall be recorded on the SwRI Magnetic Particle Examination Record and reported to the customer for disposition in accordance with the recording criteria table below: . Overall Indication Length Nominal Wall Thickness as defined in Attached Figure
<Inches) <Inches)
Less than 1.0 1/8 1.0 to less than 2.5 3/16 2.5 and greater 1/4 For preservice examination, indications with a length of 1/16 inch in ferritic piping less than .312 inches in thickness shall be recorded. Rounded indications shall be recorded based on diameters corresponding to the linear indication recording criteria and reported to the customer for disposition. When conditions limit tlie area of examination, the limitations shall be recorded.
SwR.I-N""DT-300-2
- SOUTHWEST RESEARCH INSTITUTE Revision 42
. . NUCLEAR PROJECTS June 1987 OPERATING PROCEDURE Page_ 1 of 9 Title FLUORESCENT MAGNETIC PARTICLE EXAMINATION EFFECTIVITY AND APPROVAL Revision 4 2 of this procedure became effective on June 22
- 1987_ Other revisions of the base document may be effective concurrently.
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The following information may be used for convenience. Cfompletion of this portion is not mandatory. Deviation No. Date Effective Pro.cedure Section(s) Affected Notes: I SwRI Form QA*40A-0 I
SwRI-NDT-300-2 SOUTHWEST RESEARCH INSTITUTE Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 9 FLUORESCENT MAGNETIC PARTICLE EXAMINATION SwRI-NDT-300-2
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure proper fluorescent magnetic particle examinations of ferro-magnetic materials in accordance with the applicable American Society of Mechan-ical Engineers (ASME) Boi.ler and Pressure Vessel Codes.
2* SCOPE AND APPLICATION This procedure shall be utilized for the fluorescent magnetic particle examination of ferromagnetic materials, employing, alternating current (AC) yoke techniques. Areas to be examined shall be studs, nuts, cap screws, and other ferritic components specified in the applicable Southwest Research Institute (SwRI) Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code~ Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) NRC Regulatory Guide 1. 65, entitled "Materials and Inspections for Reactor Vessel Closure Studs" (4) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Applicable Examination Record SwRI-NDTR Form No. 17-12, revision dated 11-26-79
- 4. RESPONSIBILITY (1) The Director of the Department of Engineering Services, Nondestruc-tive Evaluation Science and Technology Division, shall be responsible f~r the preparation, review, approval, and control of this procedure
- SwRI Form QA 3-2
SwRI-NDT-300-2 SOUTHWEST RESEARCH INSTITUTE Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 9 (2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan. (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Support and Administration Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control."
s.2 Yokes AC electromagnetic yokes to be utilized shall have a lifting power of 10 pounds or greater at the maximum pole spacing that will be used. Each yoke shall be calibrated at least once a year or whenever the yoke has been sub-jected to any repair, periodic overhaul, damage, or has not been used for a year or more. 5.3 Magnetic Particles (1) A fluorescent magnetic suspension shall be utilized as the examination medium. It shall fluoresce with a color that will provide adequate contrast with the area being examined when illuminated by an ultraviolet lamp of suitable characteristics. (2) Magnetic particles shall be suspended in a suitable liquid medium in the concentration recommended in SE-709, "Standard Recommended Practice for. Magnetic Particle Examination." I Certified reports for magnetic particles, giving batch num- I bers and analysis results, shall be obtained from the supplier or by sample analysis of the batch to be used. Copies of the certified reports shall be retained with the I examination records. I (3) Examinations shall be performed by utilizing one of the mate-rials from the following list: I I I SwRI Form QA 3-2 I I
SwRI-NDT-300-2 SOUTHWEST RESEARCH INSTITUTE Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 9 (a) Magnaglo No. 20A fluorescent powder concentrate in a deionized water suspension (b) Magnaglo No. 14A fluorescent powder concentrate in a deionized water suspension with water conditioner WA-2A (c) Magnaglo No. 14AM aerosol-packaged fluorescent magnetic particle material (4) If not premixed, the magnetic particle suspension shall be mixed in accordance ~'"ith the manufacturer's instructions. 5.4 Lighting A black light shall be used when conducting examinations in accor-dance with this procedure. The black light intensity shall be measured at the examination surface at least every 8 hours and whenever the work location is changed and whenever the power is interrupted. These measurements shall be in accordance with the applicable revision of SwRI Procedure IX-FE-110. The time of the black light intensity measurements shall be entered on the SwRI Magnetic Particle Examination Record. 5.5 Calibration Block A calibration block of a ferromagnetic material weighing a minimum* cf 10 pounds shall be used to confirm the lifting power of AC yokes in accor-dance with Section V, Article 7, Subparagraph T-733.
- 5.6 Thermometer The thermometer to be used for measuring the calibration block and component temperatures shall be calibrated and certified and shall display a valid calibration tag as ~equired by NQAP 10-1.
- 6. . CALIBRATION 6.1 Calibration (1) The applicable calibration block described in Paragraph 5.5 shall be used to verify proper operation of the magnetic par-ticle yoke when any of the following occurs:
(a) Prior to a series of examinations (b) With any substitution of examination personnel SwRI Form QA 3-2
SwRI-NDT-300-2 UTHWEST RESEARCH INSTITUTE Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 9 (c). With any substitution of the AC power source (d) At least .every 4 hours during the examination (e) At the completion of a series of examinations (f) When the proper operation of the yoke is in doubt. (g) At the maximum pole spacing to be used for examination (2) All magnetic particle yoke verification times shall be entered on the SwRI Magnetic Particle Examination Record. NATION Examination Areas Examinations shall be performed on materials in their completed n. The entire surface of studs and bolts or cap screws and the entire rface of nuts shall be examined. Ihe examination area for components other than threaded components, as described in the applicable SwRI Examination Plan. Surface Preparation It shall be the responsibility of the customer to ensure that the ion area and, where required, a minimum of one inch on each side shall
, dry, free from oil, .sand, rust, grease, paint, slag, loose scale or onditions to the extent that it shall not mas~ the indication of unaccept-continuities.
NOTE face conditions are not in acco*rdance with the above and correction is sible, SwRI will conduct the examination only at the request of the cus-The specific surface condition and its effect on the examination shall on the SwRI Examination Record
- 3*2
SwRI-NDT-300-2 SOUTHWEST RESEARCH INSTITUTE Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 9 CAUTION Extreme care should be exercised to prevent damage to t~readed components during handling and examination. 7.3 Examination Method The fluorescent magnetic particle examination shall be conducted as follows: (1) Examinations shall be made in a darkened area and shall com-mence approximately 5 minutes after the space is darkened, in order for the examiner's eyes to adjust. (2) A black light, as described in Paragraph 5.4 of this proce-dure, shall be used to illuminate the examination area. A minimum of 5 minutes shall be allowed for warm-up. (3) The examination surface temperature, which shall be no.higher (4) than 135°F, shall be measured and recorded on the SwRI'Mag-netic Particle Examination Record. The AC electromagnetic yoke shall be applied twice in each examination area. The second application shall be conducted with the lines of magnetic flux approximately at right angles to those used in the first application. Sufficient overlap shall ensure the entire examination area is covered. (5) The magnetizing current shall.remain on continuously during application of the magnetic suspension medium, while the excess is being drained, and during the observation. (6) The magnetic particl~ suspension shall be applied by flooding the surface of the examination area and then allowing the excess to drain off. (7) After draining, the area being examined shall be observed for indications of discontinuities while the fluorescent lamp is directed fr~m various angles so that the entire surface of the examination area is illuminated. NOTE Broad areas of particle accumulation which might mask indications from discon-tinuities are unacceptable, and shall be cleaned and reexamined. SwRI Form QA 3-2
SwRI-NDT-300-2 SOUTHWEST RESEARCH INSTiTUTE Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCED\,JRE Page 7 of 9 (8) Variable electromagnetic yoke spacing shall not exceed the distance used during calibration verification. (9) Demagnetization of the examination area is not required. 7.4 Postexamination cieaning Arrangements shall be made with the customer for postexamination removal of fluorescent magnetic particle materials.
- 8. RECORDING CRITERIA Indications s~all be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-116.
8.1 Pressure Retaining Bolting Greater Than 2 Inches in Diameter
- ~gnetic The following indications shall be recorded on the appropriate SwRI Particle Examination Record and reported to the customer:
(l) (2) Nonaxial linear indications greater than 1/4 inch in length Axial indications greater than l inch in length 8.2 Components Other Than Pressure Retaining Bolting s.2.1 Linear Indications (Class 1 and Class 2) Linear indications shall be recorded on the SwRI Magnetic Particle Examination Record in accordance with the following table and reported to the customer: Overall Indication Length Nom. Wall Thickness As Defined in Attached Figure l (Inches) (Inches)
. Less than 1.0 1/8 1.0 to less than 2.5 3/16 2.5 and greater 1/4 SwRI Form QA 3-2
SwRI-NDT-300-2 SOUTHWEST RESEARCH INSTITUTE Revision 42 June 1987 SJ~
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1Rll,1-... ,...c::-\. NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 9 I I [*I ffi1117J.._).h
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8.2.2 Rounded Indications (Class 2) Rounded indications shall be recorded as follows: (l) Rounded indication with dimensions grea.ter than 1/8 inch for thicknesses less than 5/8 inch and dimensions greater than 3/16 inch for thicknesses 5/8 inch and greater (2) Four or more rounded indications in a line separated by 1/16 inch or less (3) Ten or more indications in any 6 square inches of area whose major dimension is no more than 6 inches with the dimensions taken in the most unfavorable location relative to the indi-cations being evaluated When conditions limit the area of examination, the limitations shall be recorded.
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI per-sonnel, and shall be conducted in accordance with the applicable ASME Boiler and Pressure Vessei Code, Section XI, Article IWA-3000. Final evaluation-and dispo-sition of reportable indications shall be the responsibility of the customer.
- 10. RECORDS Documents generated in accordance with this procedure shall be stored as specified in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan.
SwAI Form aA 3-2
SwRI-NDT-300-2 HWEST RESEARCH INSTlTUTE Revision 42 June 1987 NUCLEAR PROJECTS OPERATlNG PROCEDURE Page 9 of 9
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PROCEDURE DEVIATION Page 1 of 3 Pages ocedure I Revision No_. Deviation No. vAl-NDT- 600-6 25 I ' 2 e following examination areas are affected by this deviation: All calibrations performed in accordance with this procedure using clad calibration blocks. e following paragraphs shall be deviated from as indicated: Replace paragraphs 6.1.2 and 6.1.3 with the following: 6.1.2 Angle-Beam Distance Amplitude Correction (1/2 Vee-Path) Distance amplitude correction (DAC) curves shall be established by obtaining the ma.itimum response from the basic calibration holes. The 1/2 vee-path calibration shall be performed from the unclad side of clad basic calibration blocks. A 1/2 vee-path calibration shall be constructed as follows:
- * (1) Position the 45-degree sear~ unit to obtain maximum response from the hole and vee-path position, selected from the following, that produces the highest amplitude:
Vee-Path Positions 1/4T 1/8 1/2T 2/8 3/4T 3/8 1-------------------------------------------1 onale for deviation: These changes are necessary to reflect the customer's technical requirements to verify the presence of the calibration reflectors under procedural scanning conditions, and to allow accomplishment of a full-vee calibration using a clad calibration block. If the deviation is determined to affect :he crccedure ation Affects lification YES 0 NO g} qualification, the deviation shall be qualified in accordance with Procedure IX*F=* 107. APPROVALS SAFL-LJ
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PROCEDURE DEVIATION Procedure SwRI-NDT-600-6 Revision No. 25 Deviation No. 2 Page 2 of3 (2) Set this signal to 75% +/- 5% of full screen height (FSH) and mark this amplitude on the instrument screen. (3) From the clad side of the block, determine the dB change in amplitude between the 3/8 and 5/8 hole positions. Record the metal path location of the 5/8 hole position. (4) From the unclad side, position the search unit for maximum amplitude from the 3/8 hole position. Decrease the signal amplitude by the number of dB determined in (3) above. Mark this signal amplitude at the 5/8 hole position on the CRT. (5) Without changing the gain controls, mark and join all amplitude points with a smooth curved line. 6.1.3 Angle-Beam Distance Amplitude Correction (Full Vee-Path) The full vee-path calibration shall be performed from the clad side of clad basic calibration blocks. (1) Position the 45~degree search unit to obtain maximum response from the hole and vee-path position, selected from tlie following, that produces the highest amplitude: Vee-Path Positions 3/4T 5/8 1/2T 6/8 1/4T 7/8 (2) Set this signal to 75% +/- 5% of FSH and mark this amplitude on the screen. (3) Without changing the gain controls, obtain maximum response from the remaining calibration holes; mark and join all amplitude points with a smooth curved line extrapolated from the 7/8 vee-path position to the 8/8 vee-path position. The screen size used for this calibration should be the same as that used for the 1/2 vee-path calibration. For this purpose, the DAC curve can be delayed to the left side of the screen, provided the 5/8 to 8/8 DAC is encompassed on the instrument screen.
PROCEDURE DEVIATION
*Procedure SwRI-NDT-600-6 evision No. 25 ** Deviation No. 2 Page3 of3 Add the second note in paragraph 6.1.3 to read as follows:
Verification of Calibration Reflectors The Exani.iner shall verify the presence of the calibration reflector at scanning speed. It is not necessary to assure that this check confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the signal from the calibration reflectors are readily observable at scanning speed. The following statement shall be documented on the SwRI Calibration Record Sheet and initialed: "Calibration reflectors have been verified at scanning speed.* Add the following as the fifth paragraph under Section 8: The end points of the indication as determined by 100% DAC shall be recorded for indications with a response 100% or greater of the reference level.
SwRI-NDT-600-6
- SOUTHWEST RESEARCH INSTITUTE Revision 25
. - NUCLEAR PROJECTS April 1988 OPERATING PROCEDURE
' Page 1 of 9 Title MANUAL ULTRASONIC EXAMINATION OF REACTOR COOLANT PUMP FLYWHEELS EFFECTIVITY AND APPROVAL Revision 25 of this procedure became effective on Apr* 19, 1988. Other revisions of the base document may be effective concurrently.
SA fl.1) Approvals i::~-to/~z Teo2-~ Date Date i ~ / t/-l't-j'(
µ ..Pf1r er of O.A.17-fv"" o"ate Cognizant Director Date I
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Tne following information may be used for convenience. Completion of this portion is riot mandatory. Deviation No. Date Effective Procedure Section(s) AHec~ed Notes: wRI F~rm QA*.10A*O
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SOUTHWEST RESEARCH INSTITUTE I~'~ I c;i'li':D l_ .J, IV,? / / NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-6 Revision* 25 April 1988 Page 2 of 9 MANUAL ULTRASONIC EXAMINATION OF REACTOR COOLANT PUMP FLYWHEELS SwRI-NDT-600-6
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure an accurate ultrasonic examination of reactor coolant pump motor flywheels in accordance with the applicable documents stated herein.
- 2. SCOPE AND APPLICATION (1) Reactor coolant pump motor flywheels in the thickness range of 3 to 9 inches shall be examined utilizing angle-beam shear-wave, manual, contact, pulse-echo ultrasonic techniques.
(2) Reactor coolant pump motor flywheels to be examined shall be as 3. (1) specified in the applicable SwRI Examination Plan. APPLICABLE DOCUMENTS ASME Boiler and Pressure Vessel Code, Section V, 1980 Edition with Addenda through Winter 1981 and 1983 Edition with Addenda through Summer 1983 (2) NRC Regulatory Guide 1.14, Revision l, dated August 1975, "Reactor Coolant Pump Flywheel Integrity" (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Applicable Calibration and Examination Records SwRI NDTR Form No. Revision Date 17-19 12-1-83 17-23 7-31-75
- 4. RESPONSIBILITY (1) The Director of the Department of NDE Services, Nondestructive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-
- cable SwRI Project Plan.
Swfll Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-6.
Revision 25 April 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 9 (3) The examiner shall be responsible for implementing the require~ents of this procedure. (4) The Manager. of Quality Assurance shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EOUIPMENT 5.1 Personnel Personnel performing ultrasonic examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control."
5.2 Reference Block The reference blocks used for screen distance calibration and verification shall be of the same material as the production material, carbon
- . I steel, and shall be one of the following: (1) SwRI Half-Round, (2) AWS Type DC , ( 3) IIW, or ( 4) Rompas .
5.3 Basic Calibration Block The material from which the basic calibration block is fabricated shall be material of the same material specification, product form, and heat
~reatment as the flywheel being examined.
Side-drilled holes shall be used as calibration reflectors. The diameter of the holes shall be based on the actual flywheel thickness and Figure T-546.1 of ASME Section V, Article 5. 5.4 Search Units (1) Search units shall be 1/2" x l", l" x l", or l" round. (2) The exit point of the sound beam and the actual refracted beam angle of shear-wave units shall b~ determined on an IIw or Rompas block. The exit point of the sound beam shall be marked on the search unit wedge. (3) Search unit wedges shall be fabricated to produce 45° +/-2° refracted shear-waves as demonstrated on an IIW or Rompas block. Other angles, as necessary, may be used to a~gment the examinations . (4) The nominal search unit frequency shall be 2.25 MHz. SwRI Form QA 3*2
SwRI-NDT-600-6 SOUTHWEST RESEARCH INSTITUTE Revision 25 April 1988
. NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 9 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1.
5.6 Couplant (1) USP-grade glycerine or deionized water shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure. (2) USP-grade glycerine shall be certified for sulfur content and total halogens. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Deionized water, when used, shall be supplied by the* customer. (3) Couplant ~aterials used for examinations shall be the same as used for the *calibration.
)
- 6. CALIBRATION 6.1 examination.
Calibration Method The ultrasonic calibration shall be completed prior to the All information blocks on the SwRI Sonic Instrument Calibration Record shall be filled in. The FREQ.MHZ control shall be turned to 2. The REJECT cont~ol shall be maintained in the 0 position du~ing calibration and examination. 6.1.l Distance Calibration
- "ne screen distance calibration chosen shall be the shortest applicable size to include at least 1/8 vee-path past the anticipated examina-tion range.
Observing the radius echoes from the applicable reference block, set up the required linear sound path distance along the instrument screen baseline. 3wAI Form QA 3*2
SwRI-NDT-600-6 SOUTHWEST RESEARCH INSTITUTE Revision 25 April 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page S of 9 6.1.2 Distance Amplitude Correction (1/2 Vee--Path) Distance amplitude correction (DAG) curves shall be established by btaining the maximum response from the basic calibration holes. A search unit with a 1/2 vee-path calibration shall be utilized examine one-piece flywheels. This examination shall be conducted from both des of the flywheel, if possible. If only one side of the flywheel is accessible or the flywheel is minated, an additional examination shall be conducted on the flywheel with a
° search unit utilizing a full vee-path calibration.
(1) Position the search unit to obtain maximum response from the hole and vee-path position selected from the following, that produces the highest amplitude: Vee-Path Positions l/4T. 1/8 l/2T 2/8 3/4T. 3/8 (2) Set this signal to 80% +/-5% of full screen height (FSH) and mark this amplitude on the instrument screen. (3) Without changing the gain controls, obtain maximum response from the remaining calibration holes; mark and join all amplitude points with a smooth curved line extrapolated to the 4/8 vee-path position. Extrapolation prior to the 1/8 vee-path shall be horizontal from the 1/8 vee-path position. 6.1.3 Distance Amplitude Correction (Full Vee-Path) (1) Position the search unit to obtain maximUI!l response from the hole and vee-path position, selected from the following, that produces the highest amplitude: Vee-Path Positions 3/4T 5/8 l/2T 6/8 l/4T 7/8 (2) Set this signal to 80% +/-5% of FSH and mark this amplitude on the screen. Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-6 Revision 25 April 1988 Page 6 of 9 (3) Without changing the gain controls, obtain maximum response - from. the remaining calibration holes; mark and join all amplitude points with a smooth curved line extrapolated to the 8/8 vee-path position. The screen size used for this calibration should be the same as that used for the 1/2 vee-path calibration. For this purpose, the DAG curve can be delayed to the left side of the screen, provided the 5/8 to 8/8 DAC curve is encompassed on the instrument screen. 6.2 Calibration Verification 6.2.1 Frequency of Instrument Calibration Ve~ification Sweep range calibration.shall be verified on the appropriate reference block, and DAC curve calibration shall be verified on the appropriate basic calibration block: (1) At the start of a series of examinations (2) With any substitution of the same type and length of search unit cable (3) With any substitution of the same type of power source; e.g., a change of batteries (4) At least every 4 hours during the examination (5) At the completion of a series of examinations (6) Whenever the validity of the cal~bration is in doubt 6.2.2 Calibration Changes (1) Perform the following if any point on the DAC cur~e has decreased more than 2Qi.or 2 dB in amplitude, or any point on the sweep line has moved more than 5% of full screen width: (a) Void all examinations referring to the calibration in question and performed after the last valid calibration verification. (b) Conduct a new calibration. ~wR I Form QA 3-2
SwRI-NDT-600-6 UTHWEST RESEARCH INSTITUTE Revision 25 April 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 9 (c) Reexamine the areas for which examinations have been voided. (2) Perform the following if any point on the DAG curve has increased in amplitude more than 20% or 2 dB: (a) Correct the calibration. (b) Reexamine all indications recorded since the last valid calibration verification. (c) Enter proper values on a new SwRI Flywheel Ultrasonic Examination Record. 6.2.3 Recalibration e.bration;l) Substitution of any of the following shall be cause for Search unit wedge or transducer (2) Couplant (3) Ultrasonic instrument (4) Examination personnel (5) Change in type of power source; e.g., a change from direct to alternating current
. EXAMINATION 7.1 Examination Areas The examination shall assure 100% coverage of the b.ore area or ny portion that is accessible and shall be conducted from both sides of the lywheel, if possible. Determination of accessibility for examination ~ill epend on each particular flywheel installation.
7.2 Surface Condition The contact surfaces must be free from roughness or other condi-ions which interfere with free movement of the search unit or impair the ransmission of ultrasound . Form QA 3*2
SwRI-NDT-600-6 SOUTHWEST RESEARCH INSTITUTE Revision 25 April 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 9 7.3 Scanning Parameters When practicable, scanning shall be performed at a minimum gain _setting of 2 times the reference level sensitivity. The search unit movement rate for scanning shall not exceed 6 inches per second. Instrument gain setting for scanning shall be determined on the calibration block as follows for each primary reference level utilized: (1) With the.instrument at the primary reference level manipulate the search unit on the calibration block to obtain a signal from a reflector_(machined notch) of 40% FSH. (2) Add 6 dB of gain by utilizing the 6 dB switch (if present), the fine gain control, or a combination of the fine and coarse gain controls and choose any method which yields a signal response within +/-2 dB of 80% FSH. (3) This amplitude and method shall be recorded on the SwRI Sonic Ins~:ument Calibration Record and shall be used during the valid calibration period of all scanning at 2 times the reference level sensitivity. (4) Scanning shall be performed with the sound beam directed tangential to the flywheel bore in a clockwise and counter-clock-wise direction. The search unit shall be manipulated so that the maximum practical volume adjacent to the bore is examined. Scanning overlap shall be a minimum of 10% of the search unit piezoelectric element dimens~on perpendicular to the direction of scan.
- 7. 4 Poste:rnmination Cleaning Arrangements shall be made with the customer for postexamination removal of couplant materials.
- 8. RECORDING CRITERIA Ultrasonic reflectors producing a response 50% or greater of the reference level shall be recorded.
wAI Form QA 3-2
- SwRI-NDT-600-6 HWEST RESEARCH INSTITUTE Revision 25 April 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 9 A Wo arid a Lo shall be established, and their locations shall.be described e appropriate SwRI Flywheel Ultrasonic Examination Record. Indications ded shall be referenced to the established Wo and Lo locations. L and W rementsJshall be recorded in inches and common fractions to the nearest inch.
Indications producing a response 100% or greater of the reference level be investigated by a Level II or a Level III examiner to determine the
, identity, and location of the reflector (i.e., plot, profile, review of ings, etc.).
Indications 100% or greater of the reference level investigated and found other than geometrical in nature shall be reported to the customer for ation. Scanning limitations shall be recorded. ~* 111111 evaluation and disposition of reportable indications shall be the onsibility of the customer. RECORDS Documents generated in accordance with this procedure shall be stored as ified in the SwRI Project Plan. The customer shall receive copies of these ments in the Examination Report, unless specified otherwise in the SwRI ct Plan . QA 3*2
PROCEDURE DEVIATION Page 1 of 2 Pages Procedure Revision No. Deviation No. SwRl-NDT-600-14 19 2 The following examination areas are affected by this deviation: Ultrasonic examinations performed with this procedure shall be affected by this deviation. The following parag~aphs shall be deviated from as indicated: Change Section 3. to read:
- 3. APPLICABLE DOCUMENTS (1) American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) .
3.1 Calibration. and Examination Records SwRI NDTR Form No. Revision Date 17-19 12-01-83 17-27 02-03-82 17-37 02-18-80 Rationale for deviation: This deviation incorporates the latest Code required instrument linearity verification methods, changes Code reference, data sheet revision, and complies with the customers request to verify calibration reflectors at scanning speed. If the deviation is determined to affect the procedure Deviation Affects Qualification YES D NO [31 qualification, the deviation shall be qualified in accordance with Procedure IX*FE* 107. APPROVALS Date: Technical Review:
.:1 I I' I I I?. Verbal Approval Given?
Cognizan.t Director: *Date: z /11 / ir wRI FCRM FE-4-6
PROCEDuRE DEVIATION Procedure SwRI-NDT-600-14 Revision No. 19 DeViation No. 2 Page 2 of2 Add the following Note under Paragraph 6.1.2(2): The primary reference level sensitivity should be within the highest and lowest gain settings used during amplitude control linearity verifications. The highest and lowest gain settings used during the amplitude control linearicy verifications shall be recorded in the Remarks column of the applicable SwRi Linearity verification records. AdQ. to Paragraph 6.3: Verification of Calibration Reflectors at Scanning Speed The examiner shall verify the presence of the calibration reflector at scaniiing speed. It is not necessal'Y to assure that this check confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the signal from the calibration reflectors are readily observable at scanning speed. The following statement shall be documented on the SwRI Calibration Record and initialed: "Calibration reflectors have been verified at scanning speed."
600-i4 PROCEDURE DEVIATION examination areas are affected by this deviation: Revision No. 19 Page 1 of Deviation No. 3 1 Pages ations performed in accordance with this procedure. paragraphs shall be deviated from as indicated.: the last sentence of 5.4 to read as follows: m1nal search unit frequency shall be 2.25, 5.0, 7.5, or 10.0 MHz. 6.1 to read as follows:
- onic instrument linearity shall be verified on site as a minimum within one day before and one er examining all components during an outage or every three months, whichever is less, in ance with paragraphs 6.1.1 and 6.1.2. Data required shall be recorded on the SwRI Instrument ity Verification Record and the sheet number shall be referenced on each applicable SwRI ment Calibration Record.
a p . change second sentence under NOTES to read as follows: R~z control shall be set as follows: uencv Select Search Unit Frequency 2 2.25 MHz 5 5.0 MHz oadband 7.5MHz 10 10.0 MHz eviation: e of higher frequencies will reduce beam spread and eliminate geometric ret1ections. allow instrument linearity checks in compliance with current ASME Code requirements. I If ~r:e deviauon is cetermined to atiect :r-.e proc~cure cts YES 0 NO Q qualif:caticn. :rie deviation shail be auaiified in ac:orCance with Procedure IX-i=E* 107. APPROVALS Date: ells 5/5/89 A.: Date:
/C'T
- Title SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-14 R~vis ion 19 September 1985 Page 1 of 11 MANUAL ULTRASONIC EXANINATION OF STUDS AND BOLTS EFFECTlVITY AND APPROVAL Revision 19 of this proc2dure be1:3me effective on 9- 18-85 . Other revisions of the base document may be effective concurrently.
SA' rl
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Approvals 1 Written By Technical Review Date Dyate 0~~ t7S4'fT
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- Manager of Q.A.
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Date L?!/o:;f5 The following information may be used for convenience. qjmpletion of this pol'1:ion is not mandatory. Deviation No. Da.:e Effec:ive
?rocadure Sec-:ion(s)
Affec~ed NotP.s:
SOUTHWEST RESEARCH INSTITUTE Revision 19 Septemoer 19.85 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 11 PURPOSE MANUAL ULTRASONIC EXAi.'1INATIONS OF STUDS AND BOLTS SwRI-NDT-600-14 This procedure provides the technical information and detailed steps cessary to ensure a complete and accurate manual ultrasonic examination of'- essure-retaining studs and bolts in accordance with the applicable ASHE iler and Pressure Vessel Codes. SCOPE AND APPLICATION Pressure-retaining studs and bolts greater than 2 inches in diameter, tha.t nnot be examined with angle-beam techniques from access holes shall be exam-d with this procedure. Manual, contact, pulse-echo, straight-beam longitudinal-wave ultrasonic hniques shall be utilized for the examination of pressure-retaining studs d bolts as specified in the applicable SwRI Examination Plan. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1980 Edition, with Addenda through Winter 1981, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1980 Edition, with Addenda through Winter 1981, "Nondestructive Examination" (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Applicable Calibration and Examination Records SwRI-NDTR Form No. Revision Date 17-19 7-10-80 17-27 2-03-82 17-37 2-18-80 orm QA 3-2
SwRI-NDT-600-14 SOUTHWEST RESEARCH INSTITUTE Revision 19 September 1985 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 11
- 4. RESPONSIBILITY (1) The Director of the Department of Engineering Services, Nondestructive Evaluation Science and Technology Division., shall be responsible for the preparation, review, approval, and control of this procedure.'
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the.NQAPM specified in the applicable *swRI Project Plan. (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Support and Administration Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with this procedure *
- s. PERSONNEL AND EQUIPMENT S.l Personnel Certification Personnel performing ultrasonic examinations shall pe certified in accordance with SwRI NQAP-11-1, "Special Process Control."
S.2 Reference Block Reference blocks used for screen dist~nce calibration and verifica-tion shall be of the same basic material as the pressure-retaining studs and bolts, carbon steel, and shall be one of the following: (1) SwRI Half-Round, (2) AWS Type DC, or (3) IIW. S.3 Basic Calibration Block The calibration block and examination surface finish shall be the same as.or equivalent to the bolting being examined. The basic calibration block shall be threaded as the component. The basic calibration reflectors* shall be notches machined one thread deep, or 1/8-inch deep, whichever is smaller. Notches shall be measured from the base of the thread root and shall follow the pitch angle of the threads. The depth location of these reflectors shall be such that a distance amplitude correction (DAC) curve can be estab-lished covering the full examination distance. Approved drawings of the basic calibration block are contained in the applicable SwRI Examination Plan
- SwRI Form QA 3-2
SwRI-NDT-600-14 SOUTHWEST .RESEARCH INSTITUTE Revision 19 September 1985
. NUCLEAR PROJECTS OPERATING PROCEDURE Page 4*of 11 5.4 Search Units The size of the .straight-beam longitudinal-wave search units shall be selected from the following:
- 1/4" Round 3/8" Round 1/2" Round 3/4" Round The nominal search unit frequency shall be 2.25 MHz.
S.S Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display an alignment calibration tag as required by NQAP ia-1~. - S *6 Couplant (1) USP-grade glycerine or deionized water (witl:i or without (2) wetting agent) shall be. u~ed when performing ultrasonic calibrations and examinations in accordance with this procedure. USP-grade glycerine shall be ~ertified: for sulfur content. and total halogens in accordance with ASTI1 D-129-64 and ASTI1 D-808-63. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Deionized water, when used, shall be supplied by the customer. (3) Couplant materials used for examinations shall ~ the same as used for the calibration. 5.7 Thermometer The thermometer to be used for measuring the calibration block and component temperatures shall be calibrated and certified and shall display a valid calibration tag as required by NQAP 10-1
- SwRI Form QA 3-2
SwRI..:.NDT-600-14
- so*uTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE Revision 19 September 1985 Page 5 of 11
- 6. CALIBRATION METHOD 6.1 Instrument Linearity The* ultrasonic instrument shall be verified. at the beginning of each day for amplitude linearity and amplitude control linearity in accordance with Paragraphs 6.1.1 and 6.1.2. Data required shall be recorded on the SwRI Instrument Linearity Verification Record and the sheet number referenced on the ap.plicable SwRI Sonic Instrum,ent Calibration Record.
6 .1.1 Amplitude Linearity (1) Position a shear-wave search unit on a calibration block to* obtain indications from the l/2T and 3/4T holes (the calibra-tion block for.amplitude linearity verification may not be the basic calibration block specified for calibrating dis-tance amplitude correction curves in accoi:dance with this procedure).
- (2)
(3) Adjust the search unit* position to give a 2:1 ratio between the two indications with the larger indication (l/2T hole) set at 80% of full screen height (FSH) and the small indica-tion (3/4T hole) set at 40% of FSH. Without moving the search unit, adjust the instrument sensi-tivity (gain) to set the larger indication to 100% of FSH. (4) With the larger indication at 100%, record the amplitude of the sma~ler indication, estimated to the nearest 1% of FSH. (5) Successively set the larger indication from 100% to 20% of FSH in 10% increments (or 2 dB steps if a fine control is not available), observe and record the smaller indication estimated to the nearest 1% of FSH at each setting. The reading must be 50% of the larger amplitude within 5% of FSH. 6 .1.2 Amplitude Control Linearity (1) Position a shear-~ave unit on a calibration block to obtain maximum amplitude from the 1/2 hole. (2) Without moving ~he search unit and according to the follow-ing table, set the indication to the required percent of FSH and increase or decrease the dB as specified. The signal shall be estimated and recorded to the nearest 1% of FSH and shall fall within the limits of the following table: SwRI Form QA 3-2
-SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-14 Revision 19 September 1985 NUCLEAR PROJECTS OPERATING PROCEDURE Indication Set at % of dB Control Page 6 of 11 Indication Limits, % of Full Screen Change* Full Screen 80% -6dB 32 to 48%
80% -12dB 16 to 24% 40% +6dB 64 to 96% 20% +12dB 64 to 96%
*Minus denotes decrease in amplitude; plus denotes increase.
6.2 Calibration The complete ultrasonic calibration shall be performed prior to the examination. NOTES The REJECT control shall be maintained in the 0 position during calibration and ,/ examination. The FREQ MHz control shall be turned to 2. The type and length of the search unit cable used shall be documented on the SwRI Sonic Instrument Calibration Record. All applicable spaces on the SwRI Sonic Instrument Calibration Record shall be filled in. 6.2.1 Temperature Requirements The temperature of the calibration block shall be within 25°? of the component temperature and shall be recorded on the SwRI Sonic Instrument Calibration Record for the initial calibration and each verification. The surface temperature of the component to be examined shall be taken prior.to performing an examiantion and shall be recorded on the appli-cable SwRI Examination Record. 6.2.2 Straight-Beam Distance Calibration Observing the back reflection from the applicable reference block, adjust the MAT'L CAL, RANGE, and DELAY controls of the instrument to obtain a linear sound path distance displayed along the screen baseline. The screen distance chosen shall be the smallest applicable size to include at least 10% of the screen distance past the last calibration point. SwRI Form QA 3-2
SwRI-NDT-600-14 SOUTHWEST RESEARCH* INSTITUTE Revision 19 September 1985 NUCLEA~ PROJECTS OPERATING PROCEDURE Page 7 of 11 6.2.3 Straight-Beam Distance Amplitude Correction (1) A search unit selected in accordance with *Paragraph 5.4 shall be positioned on the appropriate face of the pressure-retaining stud (or bolt) basic calibration ~lock to obt_ain the maximum response from the reflector producing the highest amplitude. (2) The instrument gain controls shall be adjusted to set this signal at the primary reference response at 75% +/-% of" full screen height (FSH). This signal shall be marked on the instrument screen. (3) Without changing the instrument gain controls, the maximum responses from the other reflectors shall be obtained to establish a DAC curve covering the anticipated examination distance. These joints shall be marked on the instrument screen and joined with a smooth curved' line, extended to cover the examination range.
- 6.3 Secondary DAC Calibration If all points on the DAC curve do not appear at 20% of FSH or greater, a secondary DAG curve shall be constructed as follows:
(1) All secondary DAC curves shall contain at least 2 points. (2) The DAC point at 2_0% of FSH or greater and adjacent to a DAC point that falls below 20% of FSH shall be brought to the primary reference level by manipulating the gain control of the instrument. This point shall then be marked on the instrument screen. The adjacent point(s), previously at less than 20% of FSH, shall then be marked on -the screen and connected with a smooth curved line. The instrument gain setting for this secondary DAC curve shall be recorded on the applicable SwRI Sonic Instrument Calibration Record. EXCEPTION When the first DAC point is the only point above 20% of FSH, the next highest point shall be brought to the primary reference level. This point shall be marked on the instrument screen. The other points, previously at less than 20% of FSH, shall be marked on the screen and connected with a smooth curved line. The instrument gain setting for this secondary DAC curve shall be recorded on the ap.plicable SwRI Sonic Instrument Calibration Record
- SwRI Form QA 3-2
__ _L__.
SwRI-NDT-600-14 SOUTHWEST RESEARCH INSTITUTE Revision 19 6.4 NUCLEAR PROJECTS OPERATING PROCEDURE Sweep Range and DAC Curve Verification September 1985 Page 8 of 11 Sweep range calibration and DAC curve shall be verified on the appropriate reference and basic calibration block when any of the following occurs: (1) At the start of a series of exmainations (2) Substitution of the same type and length of search unit cable (3) Substitution of the same type of power source; e.g., a change from one direct current to another direct current source (4) At least every 4 hours during the examinations (5) At the finish of a series of examinations (6) Whenever the validity of the calibration is in doubt 6.4.1 Calibration Changes (1) Perform the following if any point on the DAC curve has decreased more than 20% or 2 dB in amplitude, or if any point on the DAC has moved on the sweep line more than 10% of the screen reading or 5% of full sweep, whichever is g.reater: (a) Void all examinations referring to the calibration in question and performed after the last valid calibra-tion .verificaiton. (b) Conduct a new calibration (c) Reexamine the areas for which examinations have been voided. (2) . Perform the following if any point on the DAC curve has increased in amplitude more than 20% or 2 dB: (a) Correct the calibration. (b) Reexamine all indications recorded since the last valid calibration verification. " SwRI Form QA 3-2 (c) Enter proper values on a new SwRI Ultrasonic Examination Record for Bolting.
SwRI-NDT-600-14 . SOUTHWEST RESEARCH INSTITUTE Revision 19 September 1985 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 11 6.4.2 Recalibr3tion Substitution of any of the following shall be cause for recalibration: (1) Search unit transducer (2) Search unit cable type or length (3) Ultrasonic instrument (4) Examination personnel (5) Couplant (6) Change in type of power source; e.g., a change from alternating to direct current
- 7. Examination 7.1 Examination Areas Forged pressure-retaining studs and bolts greater than 2 inches in diameter shall be examined ultrasonically from the accessible end or ends of the stud or bolt. The examination surface and the calibration surface shall be geometrically similar. The examination shall be conducted in a manner to assure 100 percent coverage of the stud (with the exception of the nonload-bearing portion beyond the nut) to detect flaws in an orientation perpendicular to the axis of the stud.
7.2 Surface Conditions The contact surfaces of the pressure-retaining studs or bolts shall be free from roughness or foreign particles which interfere with free movement of the search unit or impair the transmission of ultrasound. 7.3 Examination of Pressure-Retaining Studs and Bolts A straight-beam longitudinal wave search unit shall be applied to the accessible end of the installed pressure-retaining stud or bolt. The entire accessible end shall be scanned. Studs and bolts that are not installed may be examined from either or both ends
- SwRI Form QA 3-2
. SwRI-NDT-600-14 SOUTHWEST RESEARCH INSTITUTE Revision 19 .
September 1985 7.4 NUCLEAR. PROJECTS OPERATJNG PROCEDURE Scanning Page 10 of 11 When practicable, scanning shall be performed at a minimum gain setting of 2 times the reference level sensitivity. *If 2 times reference level is not practicable, the limitation shall be recorded and the customer shall be notified on a case by case basis. Instrument gain setting for scanning shall be determined on the basic calibration block as follows for each primary reference level utilized: (1) With the instrument at the primary reference level, manipulate the search unit on the basic calibration block to obtain a signal of 40% of FSH from a calibration reflector (machined notch). (2) Add 6 dB gain by utilizing the 6 dB switch (if present), the fine gain control, or a combination of the fine and coarse gain controls and choose the metpod which yields a signal response closest to 80% FSH. (3) The signal response of the method chosen shall be within +/-2 dB of 80% FSH. This amplitude and method shall be recorded on the Ultrasonic Instrument Calibration Record. The method chosen shall be used during the valid calibration period for all scanning at 2 t~mes the reference level sensitivity. The search unit movement rate for scanning shall not exceed 6 inches per second. Scanr.ing overlap shall be a minimum of 10% of the search unit piezoelectric e.lemen t dimension perpendicular to the direction of scan. Attenuation measurements shall not be taken. 7.5. Postexamination Cleaning Arrangements shall be made with the customer for postexamination removal of couplant materials.
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the applicable revision of SwRI Nuclear Projects Operating Procedure IX-FE-117.
SwAI Form QA 3-2
SwRI-NDT-600-14 .
- OUTHWEST R.ESEARCH INSTITUTE Revision 19 September 1985 NUCLEAR PROJECTS OPERATING PROCEDURE Page 11 of lf Ultrasonic reflectors producing a response greater than 50% of the reference level shall .be recorded on the appropriate SwRI Examination Record.
The end poists of the indication determined by 100% DAC shall be recorded (100%-to-100% peaks).
~ndications producing a response greater than 100% of the reference level shall be investigated by a Level II or a Level III examiner to the extent necessary to determine the shape, identity, and location of the reflector.
Indications greater than 100% of the reference level that are investigated and found to be other than geometrical in nature shall be reported to the customer for evaluation. Scanning limitations shall be recorded.
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI personnel. Final evaluation and disposition of reportable indications shall be the responsibility of the customer and shall be conducted in accordance with Article D~A-3000, Section XI, of the.applicable ASME Boiler and Pressure Vessel Gode.
I
- 10. RECORDS I
I The customer shall receive copies of documents generated in accordance with this procedure in the examination report. .I Documents generated in accordance with this procedure shall be stored and
.1 retained as a portion of the examination report. The examination report shall be stored by the Manager of the Support and Administration Section, Quality I
Assurance Systems and Engineering Division, in the Data Storage Facility for the period specified by the contractual agreement with the customer. I I I I I I I I I wAI Form QA 3-2 I J
PROCEDURE DEVJATJON Page 1 of 1 Pages Revision No. Deviation No.
-600-15 72 2 ng examination areas are affected by this deviation: "nations performed in accordance with this procedure.
ng paragraphs shall be deviated from as indicated: s Paragraph 6.1(9) Verification of Calibration Reflectors at Scanning Speed and Notch Comparison The examiner shall verify the presence of the calibration reflector at scanning speed. It is not necessary to assure that this check confirms the signal amplitade at 100% of reference level, but merely to demonstrate that the signals from the calibration reflectors are readily observable at scanning speed. e~g statement shall be documented on the SwRI Sonic Instrument Calibration Record and WJ "Calibration reflectors have been verified at scanning speed." deviation: eviation incorporates the NRC request to verify the presence of calibration reflectors under dural scanning conditions. If the deviation is cetenr.ined to ar.ect the procecure ec!s YES 0 NO [El qualification. the ceviaticn shall be qualified in accordance with ?*ccedura IX*FE*107. APPROVALS Date: Technical Review: Verbal Approval Given? Date: Cognizant Director: Date:
. I 6
SwRI-NDT-600~15 SOUTHWEST RE$EARCH INSTITUTE Revision 72 NUCLEAR PROJECTS August 1988 . OPERATING PROCEDURE Page 1 of 16 Title
.MANUAL ULTRASONIC EXAMINATION OF PRESSURE VESSEL WELDS EFFECTIVITY AND APPROVAL Revision 72 of this procedure beca:ne effective on Aug. 25' .1988 . Other revisions of the base document may be effective concurrently.
SA t:=i..-D i Approvals Date *dognizant Director Date M.~vtkv The following information may be used for convenience. Completion of this portion is not mandatory.
- Deviation No.
Date Effective Procedure Section(s) Affected Notes: SwRI Form QA*40A*O
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-15 Revision 72 _August 1988 Page 2 of 16 MANUAL ULTRASONIC EXAMINATION OF PRESSURE VESSEL WELDS SwRI-NDT-600-15
- 1. PURPOSE This procedure provides the information and detailed steps necessary to ensure a proper manual ultrasonic examination of welds and adjacent base mate-rial in.Class l and Class 2 fetritic pressure vessels other than reactor pres-sure vessels, in accordance with the applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION This procedure has been prepared for the manual, contact, pulse-echo, shear-wave angle-beam ultrasonic examination of pressure vessel welds and adjacent base material.
Class 1 and Class 2 ferritic pressure vessel welds and adjacent base material from greater than 2.0 to 12.0 inches nominal wall thickness shall be examined. Welds to be examined shall be as specified in the applicable South-west Research Institute (SwRI) Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ~SME Boiler and Pressure Vessel Code, Section XI, 1980 Edition with Addenda through Winter 1981and1983,Edition with Addenda through Summer* 1983, "Rules for Inservice Inspection '!f Nuclear Power. Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1980 edition with Addenda through Winter 1981 and 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Calibration and Examination Records SwRI NDTR Form No. Revision Date 17-17 09-04-84 17-19 12-01-83 17-135 03-24-88 SwRI Form QA 3*2
SwRI-NDT-600-15 SOUTHWEST RESEARCH INSTITUTE Revision 72 August 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 16
- 4. RESPONSIBILITY (1) The Director of the Department of NDE Services, Nondestructive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli- . cable SwRI Project Plan. (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Quality Assurance Section, Nondestructive Evalu-ation Science and Technology Division, shall be responsible for storage of records generated in accordance with.this procedure. PERSONNEL AND EQUIPMENT 5.1 Personnel Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control." 5.2 Reference Block Reference blocks used for screen distance calibration and verifi-cation shall be of the same material as the production material; carbon steel, and shall be one of the following: (1) SwRI Half-round, (2) AWS-type oc*, or (3) IIW. 5.2.1 Reference Block Selection Reference blocks shall be used as follows for screen distance calibration: SwRI Form QA 3-2
,SOUTHWEST RESEARCH INSTITUTE rs,.i ,.._.,,,___ NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-15 Revision. 72 August.1988 Page 4 of 16 Angle-Beam Screen Block Distance BlOck Type Dimension 5.0" SwRI Half-Round, 1.0" Radius AWS-Type DC 1.0" and 2.0" Radii 10.0" SwRI Half-Round, 1.0" Radius AWS-Type DC 1.0" and 2.0" Radii IIW 4.0" Radius
- 20. 0", 40. 0" IIW 4.0" Radius 5.3 Basic Calibration Block Where the component material is clad, the basic calibration block all be clad to the component clad nominal thickness of +/-1/8 inch. Deposition clad shall be by the automatic method used on the component. .IJhere the*
tomatic method is impractical, deposition of clad shall be by the manual thod used to cover the circumferential welds of the component. Side-drilled basic calibration hole reflectors in accprdance with gure T-434.l, Article 4, Section V, of the ASME Boiler and Pressure Vessel de shall be placed in a block manufactured from one of the following: (1) the mponent nozzle dropout; (2) the component prolongation; or (3) material of e same specification, product form, and heat treatment as one of the materials ing joined. The basic calibration block thickness shall be determined by the erage thickness of the weld. The requirements for basic calibration block rvature limits, heat treatment, surface condition, and scribe lines shall be accordance with Article 4, Section V. Notches 2%T deep shall be machined in the basic calibration block rface, in accordance with Article 4, Section V. A flat basic calibratiOn block or block of essentially the same rvature as the examination contact surface shall be used for the examination welds with a contact surface curvature greater than 20 inches in diameter. A single curved basic calibration block may be used to establish stance amplitude correction (DAG) curves for examinations on contact surfaces the range of curvature from 0.9 to 1.5 times the basic calibration block ameter, when contact surface curvature is 20 inches in diameter or less. The finish on the surface of the block shall be representative of e surface finish of the component. Form QAJ-2
SwRI -NDT- 600-' 15 SOUTHWEST RESEARCH INSTITUTE Revision 72 August 1988 NUCLEAR PROJECTS OPERATING PROCEDURE* Page 5 of 16 Approved drawings of the basic calibration blocks are contained in the applicable SwRI-Examination Plan. 5.4 Search Units Search units shall be selected from the following: Angle-Beam Average Weld Thickness Nominal Search Unit Size Greater than 2.0" to 4.0" 1/2" x 1/2", 1/2" Round Greater. than 2.0" to 7.0" 1/2" x l", 3/4" Round 5.0" to 12.0" 1 11 x l", 1 11 Round, 1-1/8" Round The exit point of the sound beam and the actual refracted beam of shear-wave search units shall be deterµiined on an IIW block. The exit
- of the sound beam shall be marke~ on.the search unit wedge.
Search unit wedges shall be fabricated to produce 45° +/-2° and 60° +/-2° refracted shear-waves. The nominal search unit frequency shall be 2.25 MHz. 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS:Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1. 5.6 Couplant (1) USP-grade glycerine or reactor-grade water shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure. (2) Couplant materials used, except for reactor-grade water, shall be certified for sulfur content and total halogens. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Reactor-grade water, when used, shall be supplied by the customer. (3) Couplant materials used for examinations shall be the same as used for the calibration. AI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE. NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT~600-15 Revision 72 August 1988 Page 6 of 16 5.7 Thermometer
. The thermometer to be used for measuring the calibration block and mponent t;empera.tures shall be calibrated and certified and shall display a lid calibration tag as required by NQAP 10-1.
CALIBRATION METHOD 6.1 Calibration The ultrasonic calibration shall be completed prior to the amination. The REJECT control shall be maintained in the 0 position during libration and examination. The FREQ MHz control shall be turned to 2. The centerline of the* search unit shall be.at least 1-1/2 inches m the nearest side of the calibration block. Rotating the beam into the rner formed by the hole and the side of the block may produce a higher ampli-de at a longer beam path. This beam path shall not be: used for calibration. e SwRI SonicTheInstrument type and length of the search unit cable shall be recorded on Calibration Record and all information blocks on this m shall- be filled in.
'IJhen the examination is to: be performed from the outside surface a clad vessel, the calibration shall be accomplished from the unclad surface the basic calibration block. \Jhen the examination is to be performed from e inside surface of a clad vessel, the calibration shall be accomplished from e clad surface of the basic calibration block.
6.1.1 Temperature Requirements The basic calibration block temperature shall be within 25°F of e component temperature and shall be recorded on the SwRI .Sonic Instrument alibration Record for the initial calibration and each verification. The rface temperature of the component to be examined shall be taken prior to and ter each examination and shall be recorded on the applicable SwRI Examination cord. 6.1.2 Angle-Beam Distance Calibration (1) Select the shortest screen distance size that includes at least 1/8 vee-path beyond the anticipated examination range. Form QA 3*2
SwRI-NDT-600-15 SOUTHWEST RESEARCH INSTITUTE Revision 72 August 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 16 (2) Position the search unit on an appropriate reference block,
*observe radius .echoes and set up a linear sound path distance along the screen baseline.
6.1.3 Screen Distance Calibration for 45° and 60° Examinations Using the Same Instrument (1) The screen distance size shall be determined by the angle-beam search unit requiring the longer examination range. (2) Position the 45° search unit on the appropriate reference block and observe the radius echoes. (3) Construct a linear screen as required in Paragraph 6.1.2. (4) Record reference block data required on the applicable SwRI Sonic Instrument Calibration Record. Do not change the calibrated scr~en distance during the next step or compensate for any difference observed between the 45° and 60° screen distance calibrations. (5) Position the 60° search unit on the appropriate reference ./ block and observe the maximum amplitudes and locations of the radius echoes. (6) Record reference block data required on the SwRI Sonic Instrume~t Calibration Record. I 6.1.4 Angle-Beam Distance Amplitude Correction from the Clad Side or on J Nonclad Blocks I (1) Position the 45° search unit on the basic calibration block to obtain maximum response from the calibration vee-path I position selected from the following, that produces the highest amplitude: Vee-Path Positions l/4T 1/8, 7/8 l/2T 2/8, 6/8 3/4T 3/8, 5/8 (2) Set this response to the primary reference level of 80% +/-5% of FSH and mark its amplitude on the instrument screen. Form QA 3*2
SOUTHWEST RESEARCH.INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-15 Revision 72 August 1988 Page 8 of 16 (3) Without changing the gain controls, obtain maximum response from the remaining vee-path positions; mark and join all amplitude points with a smooth curved line that shall extend 1/8 vee-path beyond the last qualified calibration point. (4) Obtain maximum amplitude from the square notch on the oppo-site surface (4/8 vee-path), and from the square notch on the same surface (8/8 vee-path). Mark each amplitude with an X. The indications from these notches must be considered when evaluating refiectors at the respective surfaces. (5) Repeat steps (1) through (4) using a 60° search unit utiliz'- ing the following vee-path positions: Vee~Path Positions l/4T l/2T 3/4T EXCEPTION 1/8 2/8 3/8, 5/8
- The amplitude from the square notch on the same surface (8/8 vee-path) is not required for 60°, and shall not be marked on the screen.
6.1. 5 Angle-Beam Distance Amplitude Correction from the Unclad Side of Clad Blocks First Half-Vee (1) Position the 45° search unit on the basic calibration block to obtain maximum response from the calibration vee-path position selected from the following, th.at produces the highest amplHude: Vee-Path Positions l/4T 1/8 l/2T 2/8 3/4T 3/8 (2) Set this response to the primary reference level of 80% +/-5% of FSH and mark its amplitude on the screen. S:wR I Form QA 3-2
SwRI-NDT-600-15 EST RESEARCH INSTITUTE Revision 72 August 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Pa_ge 9 of 16 (3) Yithout changing the gain controls, obtain maximum response from the remaining vee-path positions and mark these ampli-tudes on the instrument screen . (4) Position the 45° search unit on the clad side of the block. Determine the dB difference between the 3/8 and 5/8 vee-paths. Mark the location of the 5/8 vee-path on the baseline of the instrument screen. (5) Position the appropriate search unit on the unclad side of the block. Adjust the instrument gain controls to the primary reference level established in step (2) and obtain the maximum response from the 3/8 vee-path.
' (6) Decrease the signal from the 3/8 vee-path by the dB dif-ference determined in step (4). Mark the amplitude of this signal at the location of the 5/8 vee-path determined in step (4). Join the marks on the instrument screen to con-struct the DAC curve.
(7) Yith the instrument gain set at the primary reference level, obtain maximum amplitude from the square notch on the oppo-site surface. Mark this signal amplitude with an X The indication from this notch must be considered when evaluating reflectors at the opposite surface. (8) Repeat steps (1) through (7) using a 60° search unit. Beam Spread and Beam An~le Determination
- Each search unit used for vessel examinations shall be measured pread and beam angle prior to weld examinations performed on a vessel outage as follows:
(1) With the instrument at the primary reference level sensiti-vity, position the search unit for maximum amplitude from the l/4T hole (Y max). Measure and record the distance from the incident point of the search unit to the scribe line above the l/4T hole. (2) Repeat step (2) recording the distance to the scribe line for both the l/2T and 3/4T maximum amplitudes. (3) Increase the instrument gain 2 times the primary reference
- level sensitivity (6 dB) so the curve marked on the instru-ment screen represents the 50% DAC curve.
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-15 Revision 72. August 1988 Page 1.0 of 16 (4) Position the search unit for maximum amplitude from the l/4T hole. Move the search unit toward the hole until the indi-cation equals the 50% DAC line. Measure and record the distance from the incident point of the search unit to the scribe line above the l/4T hole (W1).
~5) Move the search unit away from the hole until the indication equals the 50% DAC line. Measure and record the distance from the incident point of the search unit to the l/4T scribe line (Wz).
(6) Repeat steps (4) and (5), recording the measurements for the 0 l/2T and 3/4T holes. (7) Plot these points on.a 1:1 or 2:1 scale drawing of the basic calibration block thickness or on the graph on the back of the SwRI Beam Spread Record, placing the po~nts at _the appropriate depth (l/4T, l/2T, or 3/4T). (8) (9) Draw a separate line to each of the W max points from the incident point of the search unit. The angle to each of the points shall be measured with a protractor. The beam angle, which shall be established by determining the average of the three W max angles measured, shall be recorded on the SwRI Beam Spread Record and con-sidered during resolution of indications. (10) Connect the W1 and Wz points extending the lines to the search unit drawn at the top of the graph. If the three W1 or Wz points do not form a straight line, then a line repre-senting the average of the l/2T and 3/4T holes only shall be drawn and extended until they cross, unless one of the points is obviously misplaced due to the cladding effect (these points must be projected along the same beam path on the block drawing to complete this task). (11) Measure the angle between the W1 line and the Wz line. This is the angle of beam spread. 6.3 Sweep Range and DAC Curve Verification Sweep range calibration shall be verified on the appropriate reference block and DAC curve calibration shall be verified on the appropriate basic calibration block: (1) Prior to a series of examinations SwAI Form QA 3-2
- - SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-15 Revision 72 August 1988 Page 11 of 16 (2) With any subs.titution of the same type and length of search unit cable (3) With any substitution utilizing the same type of power source; e.g., a change of batteries (4) At least every 4 hours during the examination *
(5) At the completion of a series of examinations (6) Whenever the validity of the calibration is in doubt 6.4 Calibration Changes (1) Perform the following if any point on the DAC curve has decreased more than 20% or 2 dB in amplitude, or any point on the sweep line has moved more than 10% of the sweep division reading:
- (a)
(b) Void all examinations referring to the calibration in question and performed after the last valid calibration verification. Conduct a new calibration. (c) Reexamine the areas for which examinations have been
- voided.
(2) Perform the following if any point on the DAG curve has increased more than 20% or 2 dB in amplitude: (a) Correct the calibration and record the change on the SwRI Sonic Ins*trument Calibration Record. (b) Reexamine any indications recorded since the last valid calibration verification. (c) If any point on the DAG curve has decreased 20% or 2 dB or more in amplitude*, all applicable data sheets shall be voided, a new calibration performed and the area for which examinations have been voided reexamined. 6.5 Recalibration Substitution of any of the following shall be cause for recalibration: (1) Search unit transducer or wedge SwRI Form QA 3-2
SwRI-NDT-600-15 SOUTHWEST RESEARCH INSTITUTE (2) NUCLEAR PROJECTS OPERATING PROCEDURE Search unit cable type or length Revision 72 August 1988 Page 12 of 16 * (3) Ultrasonic instrument (4) Examination personnel (5) Couplant (6) Change in type of power source; e.g.' a change from direct to alternating current
- 7. EXAMINATION 7.1 Surface Condition The contact surfaces must be free from weld spatter, roughness, or other conditions which interfere with free movement of the search unit or impair the.transmission
. of ultrasound.
)
7.2 Reference Points for Physical Measurements 7.3 Reference points for physical measurements shall be in accordance with the applicable revision of SwRI Procedure IX-FE-118. Scanning Parameters When-practicable, scanning shall be performed at a minimum gain setting of 2 times the reference level sensitivity. Instrument gain setting for scanning shall be determined as follows on the basic calibration block for each primary reference level utilized: (1) With the instrument at the primary reference level, position the search unit on the basic calibration block to obtain a signal from a calibration reflector (side-drilled hole) of 40% of FSH. (2) Add 6 dB of gain by utilizing the 6 dB switch (if present), the fine gain c~ntrol, or a combination of the fine and coarse gain controls and choose any method which yields a signal response within +/-2 dB of 80% FSH. (3) This amplitude and method shall be recorded on the SwRI Sonic Instrument Calibration Record and shall be used during the valid calibration period for all scanning at 2 times the reference level sensitivity. SwRI Form QA 3-2 *
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-15 Revision 72 August 1988 Page 13 of 16 7.3.l Scanning Speed and Overlap The search unit movement rate for scanning shall not exceed 6 inches per second. Scanning overlap shall be a minimum of 50% of the search unit piezoelectric element dimension perpendicular to the direction of scan.
7.4 Examination Areas 7.4.1 Detailed scale drawings shall be obtained to determine the exact weld configuration for circumferential and meridional welds in spherical Class 1 vessel heads. In cases where the weld crown is on the inside surface and the examination is to be performed from the outside surface, the examiner shall determine the examination area based upon the distance measured on.the inside surface. 7.4.2 If necessary to determine the required examination volume for vessel weld examination, inside surface and outside surface profiles shall be takeri on each weld at the Lo location as a minimum . Profiles shall consist of ultrasonic thickness measurements and outside surface contours using a contour gage. Thickness measurements shall be taken at a maximum interval of 1/4 inch and shall cover the material volume for a minimum distance of lt from the weld fusion line on each side of the weld. The "t" dimension shall be the nominal vessel wall thickness. Outside surface profiles shall cover the same distance as the thickness measurements. Weld profiles shall be documented on the SwRI Profile and Thickness Information Record. 7.4.3 Class 1 Vessels (1) The examination area for circumferential, longitudinal, and nozzle welds shall be the weld and adjacent sheli base material for a distance of l/2t from the fusion line of the weld crown. 7.4.4 Class 2 Vessels (1) The examination area for circumferential and longitudinal welds shall be the weld and adjacent shell base material for a distance of 1/2 inch from the fusion line of the weld crown. (2) The examination area for nozzle welds shall be the weld and adjacent base material for l/3t from the inside surface including 1/4 inch of base material on both sides of the weld (see Figure 1). SwAI Form QA 3-2
SOUTHWEST.HESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-15 Revision 72 August 1988 Page_ 14 of 16 7.5 Examinations 7.5.1 Examination for Indications Parallel with the Weld First half-vee angle-beam examinations shall be accomplished using 45° and 60° search units from both sides of the circumferential and longitudinal welds, and from the vessel side of the weld for nozzle-to-vessel welds. This examination shall be performed by directing the sound beam perpendicularly into the weld to detect indications parallel with the weld. 7.5.2 Examination for Indications Perpendicular to the Weld Angle-beam examination shall be conducted using 45° and 60° search unit. This examination shall be conducted by placing the search unit as required so that the sound beam is directed parallel with the weld axis. Scan-ning shall be accomplished so that the beam is directed in two opposing direc-tions, through the entire examination volume. 7.6 Postexamination Cleaning Arrangements shall be made with the customer for postexamination removal of couplant materials.
- 8. RECORDING AND SIZING CRITERIA It is recognized that not all ultrasonic reflectors indicate flaws; certain metallurgical discontinuities and geometric conditions may produce indications that are not relevant. Included in this category are plate segregates in the heat-affected zone, clad interface, and backwall reflections. These indica-tions shall not be considered reportable conditions.
Indications shall be recorded utilizing the techniques outlined in the applicable revision of SwRI Procedure IX-FE-118*. 8,1 Record all reflectors that produce a response equal to or greater than 50% of the DAG, and all surface reflectors that produce a response equal to or greater than the amplitude of the notch reflector in the basic calibration block. 8.1.1 The following data shall be recorded for reflectors less than 100% DAC:
% 50% DAG w MAX 50% DAC Ll L Lz Search Search of DAC SwRI Form QA 3-2 W1IMP WIMP Wz!MP 50%
DAC MAX 50% DAC Unit Loe a-tion. Unit Angle
- ,., SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-15 Revision 72 August 1988 Page 15 of 16 8 .1.2 The following data shall be recorded for reflectors equal to or greater than 100% DAC:
% 1/2 MAX W MAX 1/2. MAX Ll L L2 s.u. s.u.
of W1IMP WIMP W2! MP 50% DAC MAX 50% DAC Location Angle DAC 8.2 Recordable indications not*attributable to geometry shall be compared with the flaw indication characterization rules of IWA-3000 and the acceptance standards of IWB-3511 or IWB-3512 as applicable, and shall be reported to the customer. 8.3 When an examination is performed from the unclad side.of a clad vessel, indications observed past the 4/8 vee-path shall not be recorded. 8.4 Scanning limitations shall be recorded.
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI personnel. Final evaluation and dispos.ition of reportable indications shall be the responsibility of the customer.
- 10. RECORDS
_Documents genera_ted in accordance with this procedure shall be stored_ as specified in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan .
- SwRI Form QA 3-2
SwRI-NDT-600-15
.SOUTHWEST RESEARCH INSTITUTE Revision 72 August 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 16 of 16
.......~~~--------------.!
c,
-. 0 I
r 1/3t...........!.. 1/.A in. I
!Mm.vet.
c-o-s-i= L.--. I iu FIGURE 1 CLASS 2 NOZZLE-TO-VESSEL WELDS
""'T 1
-t/4in.
i I
\o 1 t3r ti* in * ......,;
II :.ica"'. *JCI, i c-o-s-F : - i; i
=
- il:lt GENERAL NOTE:
SwRI Form QA 3-2 Nozzle sizes over 4 in. NPS; vessel thickness over 1/2 in.
- Procedure SwRl-NDT- 600-16 PROCEDURE DEVIATION The following examination areas are affected bY this deviation:
.IRevision No.
31 I Deviation No. Page 1 of
/
1 Pages Examinations performed in accordance with this procedure. The following paragraphs .shall be deviated from as indicated: Add t.o Paragraph 6.4.1: Veri:fiC2.tion of Calibration Reflectors at Scanning Speed and Notch Comparison The examiner shall verify the presence of the calibration reflector at scanning speed. It is not necessary t.o assure that this check confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the signals from the calibration reflectors- are readily observable at scanning speed. The following statement shall be documented on the SwRI Sonic Instrument Calibration Record and initialed:
"Calibration reflectors have been verified at scanning speed."
Rationale for deviation: This deviation incorporates customer request. If the deviation is determined to affect the orocedure Deviation Affects Qualification YES D NO~ qualification, the deviation shall be qualified in accordance with Procedure IX*FE*107. APPROVALS SA ri[) Date: Technical Revie~I (\ "J,.;.1//} // 1 I Date:
~~:~----'l //,*~; .1.~A'Urr 3-;1-;r?
03 -$/_g( t - - - - .-"'""./:>""t'~.....,.~f"'"".f--"-1....,..:....:....i....;.:., 1
~=-~+..::D:-at_;e;....;.:~~
Verbal Appro"!a( Given? v 0 Yes 81 No
- Manager of Q.A.:
J.c . .Y~ SwRI FORM FE-4-6
~ r Ill"'
.Date:
.J/3; /gr; Cognizant Director: Date:
* ~SOUTHWEST RESEARCH INSTITUTE Title
. NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-16 Revision 31 March 1988 Page 1 of 15 MANUAL ULTRASONIC EXAMINATION OF VESSEL SUPPORT SKIRT ATTACHMENT ~ELDS EFFECTIVITY AND APPROVAL Revision 31 of this proc~dure became effective or: Mar* 30 1988 . Other revisions of the base document may be effective concurrently.
SA Approvals f 1,,J) WJ~9-Jr~~ Date Technical Review Date
~ 3-11-d-~ ~!A~ Jp1/n-
- Manager of 0.A.
- J.e.Y~
qil> Date 3/d/ii °Jt;;t~~ Date 3/so/~~ The following information may be used for convenience. Completion of this portion is not mandatory. Deviation No. Date Effective Procedure Section(s) Affected Notes: SwRI Form QA*40A*O
SwRI-NDT-600-16 SOUTHWEST RESEARCH INSTITUTE Revision 31 March 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 15 MANUAL ULTRASONIC EXAMINATION OF VESSEL SUPPORT SKIRT ATTACHMENT WELDS SwRI-NDT-600-16
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure a proper ultrasonic examination of support skirt attachment welds and the adjacent base material, in accordance with the applicable ASME Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION Manual, contact, pulse-echo, shear-wave angle-beam ultrasonic techniques shall be. employed for examinations described in this procedure.
Support skirt attachment welds and adjacent base material greater than 1.0 to 12.0 inches in thickness shall be examined as specified in the applicable SwRI Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components"
- I I
I (2) ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition with I Addenda through Summer 1983, "Nondestructive Examination" I (3) SwRI Nuclear *Quality Assurance Program Manual (NQAPM) 3.1 Calibration and Examination Records SwRI-NDTR Form No. Revision Date 17-19 12-01-83 17-89 08-19-80 17-90 08-19-80 SwRl Form QA 3*2
SwRI-NDT-600-16 SOUTHWEST RESEARCH INSTITUTE Revision 31 March 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 15
- 4. RESPONSIBILITY (1) The Director of the Department of NDE Services, Nondestructive Evaluation Science and Technology Division, shall be responsible for 1::he preparati.on, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan. (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Support and Administration Section of the Nonde-structive Evaluation Science and Technology Division shall be respon-sible for storage of records generated in accordance with this procedure .
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing ultrasonic examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control."
5.2 Reference Block Reference blocks used for screen distance calibration and verifi-cation shall be made of carbon steel and shall be one of the following: (1) SwRI Half-Round, (2) AYS Type* DC, (3) IIW, or (4) ROMPAS. 5.3 Basic alibration Block 5.3.1 Side-drilled hole calibration reflectors in accordance with Paragraph T-546.l, Section V, Article 5 of the ASME Code shall be used to establish sensitivity. 5.3.2 The material from which the blocks are fabricated shall be: {a) A nozzle dropout from the component. (b) A component prolongation. (c) Material of the same material specification, product form, and heat treatment as one of the materials being joined. SwRI Form QA 3*2
SOUTHWEST RES-EARCH INSTITUTE NUCLEAR PROJECTS OPERATINq PROCEDURE SwRI-NDT-600-16 Revision 31 March 1988 Page 4 of 15 (d) "IJhen two or more base material thicknesses are involved, the calibration block thickness shall be of a size suffi-cient to contain the entire examination metal path. 5.3.3 The nominal thickness for support skirt attachment welds shall be the distance "t" measured at the location in Sketch l for T welds and the nominal thickness of the base material adjacent to the weld for butt welds. 5.3.4 Approved drawings of the basic calibration blocks to be used with this procedure are in the applicable SwRI Examination Plan. 5.3.5 For examination of support skirt welds with contact surface curvatures greater than 20 inches in diameter, a flat basic calibration block or blocks of essentially the same curvature as the part to be examined may be used. 5.3.6 For the examination of support skirt welds having a contact surface curvature of 20 ~nches i~ diameter or less, a single curved basic cali-bration block may be used to establish distance amplitude correction (DAG) curves for the examination of welds in the range of curvature from 0.9 to 1.5 times the basic calibration block diameter. 5.4 Search Units (1) After the nominal thickness has been determined in accor-dance with Paragraph 5.3 and Sketch 1, search unit sizes shall be selected from the following: Angle-Beam Nominal Thickness Nominal Search Unit Size 1.0" to 2.0" 3/8" x 3/8"' 3/8" Round
- 1. on to 4.0" 1/2" x 1/2"' 1/2" Round 2.0" to 7.0" 1/2" x l" 3/4" Round 5.0" l" x '
to 12.0" l"' 1 Round, 1-1/8" Round 11 (2) Search unit wedges producing 45° +/-2° shear-wave shall be used to perform examinations to detect transverse indica-tions as specified iri Paragraph 7.5.5. (3) The exit point of the sound beam and the actual refracted beam angle of shear-wave units shall be determined on an IIW block. . The exit point of the sound beam shall be marked on the search unit wedge. (4) For examination of T welds, search unit wedges shall be fabricated to produce refracted shear-wave angles of 45°, SwAI Form QA 3*2
SwRI-NDT-600-16 SOUTHWEST RESEARCH INSTITUTE Revision 31 March 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 15 60°, and 70°. Other angles may be used as necessary to ensure that at least one of the sound beams used for the examination propagates in a direction normal to the fusion lines of the support skirt weld. The measured refracted angle shall be within 2° of the required refracted.angle. (5) For examination of butt.welds (Sketch 2) search.unit wedges shall be fabricated as required. to produce 45° +/-2° and 60° +/-2° refracted shear-waves. (6) The nominal search unit frequency shall be 2.25 MHz, 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument h shall be aligned and shall display a valid alignment calibration tag as red by NQAP 10-1. 5.6 Couplant (1) USP-grade glycerine or reactor-grade water (with or without wetting agent) shall be used when performing ultrasonic calibrations and examinations in accordance with this
- I procedure. I (2) All couplants other than deionized water shall be certified for sulfur content and total halogens. The residual amount of total sulfur or halogens shall not exceed 1% by weight.
Reactor grade water, when used, shall be supplied by the* customer. (3) Couplant materials used for examinations shall be the same as used for the calibration. 5.7 Thermometer The thermometer to be used for measuring the calibration block component temperatures shall display a valid calibration tag as required by 10-1. CALIBRATION METHOD The ultrasonic calibration shall be completed prior to the examination. The REJECT control shall be maintained in the 0 position during calibra-and examination. m QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-16 Revision 31 March 1988 Page 6 of 15 All spaces on the SwRI Sonic Instrument Calibration Record shall be filled The FREQ MHZ control shall be turned to 2. The centerline of the search unit' shall be at least 1-i/2 inches from the earest side of the calibration clock. Rotating the beam into the corner formed y the hole and the side of the block may produce a higher amplitude at a longer eam path. The type and length of the search unit cable shall be recorded on the -SwRI onic Instrument Calibration Record and all information blocks on this form hall be filled in. The basic calibration block temperature shall be within 25°F of tha com-onent temperature. Calibration block temperature shall be recorded on the ONIC INSTRUMENT CALIBRATION RECORD for initial calibration and each verifica-ion. The surface temperature of the component shall be taken prior to and fter each examination. The component temperature shall be recorded on the pplicable SwRI Examination Record. ' J 6.1 Angle-Beam Distance Calibration (1) Select shortest screen distance size that includes at least 1/8 vee-path beyond the anticipated examination range. (2) Position the search unit on an appropriate reference block, observe the radius echoes, and set up a linear sound path distance along the screen baseline. The screen distance calibration shall be conducted in the follow-ng manner when the same instrument is used for two different angles: (3)
- The screen distance s,ize shall be determined by the angle-beam search unit requiring the longer examination range.
(4) Position the search unit with the shorter examination range on the appropriate reference block; observe and record all reference block entries as required on the SwRI Sonic Instrument Calibration Record. (5) Position the search unit with the larger examination range on the appropriate reference block and, without changing the calibrated sc=een distance; observe and record all reference block entries as required on the SwRI Sonic Instrument Calibration Record. I Form QA 3*2
OUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-16 Revision 31 March 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 7 of 15 (6) No attempt shall be made to compensate for any delay dif-ference observed between the screen distance calibrations. This difference shall be considered when resolving indications. 6.2 Angle-Beam Distance Amplitude Correction for Butt Welds (1) Position the 45° search unit on the basic calibration block to obtain a maximum response from the calibration hole and vee-path position selected from a minimum of three vee-path positions required to cover the entire examination area described in Paragraph 7.1. (2) Set this signal to the primary reference level of 80% +/-5% of FSH and mark its amplitude on the instrument screen. (3) ~ithout changing the gain controls, obtain maximum response from the remaining applicable vee-path position(s) that will.ensure adequate coverage; mark and join all amplitude points with a smooth curved line that shall not extend more than 1/8 vee-path beyond the last qualified calibration point. (4) Repeat steps (1) through (3) using a 60° search unit. EXCEPTION e configuration of the weld is such that the above calibration is not the appropriate to provide coverage of the required examination area from two tions, a calibration may be established which uses any vee-path position red to obtain complete coverage of the examination area from one direc-Consideration shall be given to previous data to ensure that equivalent rations are performed where practicable. 6.3 Angle-Beam Distance Amplitude Correction for T Welds Distance amplitude correction (DAC) curves shall be constructed ilizing the responses from the basic calibration holes as described below. An accurate scale drawing of the cross section of the support weld and adjacent base material shall be obtained prior to the examina-The examiner shall determine che sound beam paths, and scan paths for beams from the available scan surfaces, as illustrated in Sketch 3. A separate determination shall be made for each support skirt configuration. Sketch 3 represents only one of several support skirt weld gurations that may be encountered and is given o~ly as an example. QA 3*2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERA TING PROCEDURE SwRI-NDT-600-16 Revision 31 March 1988 Page 8 of 15 (1) Position an appropriate search unit on the basic calibration block to obtain maximum response from the hole and vee-path position which produces the highest amplitude. (2) Set this signal to the primary reference level of 80% +/-5% of FSH and mark its amplitude on the instrument screen. (3) Without changing the gain controls, obtain maximum response from the other required vee-path positions; mark and join all amplitude points with a smooth curved line to construct a DAC curve covering the anticipated examination area. 6.4 Secondary DAC Calibration If all points on the DAC curve do not appear at 20% of FSH or greater, a secondary DAC curve shall be constructed as follows: (1) All secondary-DAG curves shall contain at least 2 points. (2) The DAC point at 20% of FSH or greater, next to a DAC point that falls below 20% of FSH, shall be brought to the primary reference level and marked on .the instrument screen. The other point(s), previously at less than 20% of FSH, shall be marked on the screen and all points connected with a smooth curved line. The gain setting for this secondary DAC curve shall be recorded on the SwRI Sonic Instrument Calibration Record. EXCEPTIONS When the first DAC point is the only point above 20% of FSH, the next highest point shall be brought to the primary reference level and marked on the instru-ment screen. The other points previously at less than 20% of FSH shall be
~arked on the screen and all points connected with a smooth curved line. The gain setting for this secondary DAC curve shall also be recorded.
6.5 Sweep Range and DAC Curve Verification Sweep range calibration shall be verified on the appropriate reference block and DAC curve calibration (if applicable) shall be verified on the appropriate basic calibration block: (1) Prior to a series of examinations (2) With any substitution of search unit cable (3) With any substitution of the same type of power source; e.g.~ a* change of batteries SwAI Form QA 3-2
rHWEST RESEARCH INSTITUTE SwRI-NDT-600:-16 Revision 31 March 1988 .
. NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 15 (4) At least every 4 hours during the examination (5) At the completion of a *series of examinations (6) Whenever the validity of the calibration is in doubt Calibration Changes (1) Perform the following if any point on the DAC curve has decreased more than 20% or 2 dB in amplitude, or any point on the sweep line has moved more than 5% of full screen width:
(a) Void all examinations referring* to the calibration in question and performed after the.last valid calibra-tion verification. (b) Conduct a new ca*libration . (c) Reexamine the areas for which the examinations have been voided. (2) Perform the following if any point on the DAC curve has increased more than 20% or 2 dB in amplitude: (a) Correct the sweep range and record the change on the SwRI Sonic Instrument Calibration Record. (b) If any indications have been recorded with this cali-bration, the SwRI Examination Record shall be voided, a new calibration performed, and the areas for which examinations have been voided reexamined . Recalibration Substitution of any of the following shall be cause for on: (1) Search unit transducer or wedge (2) Couplant (3) Ultrasonic instrument (4) Examination personnel (5) Changing type of power source; e.g., a change from direct to alternating current
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-16 Revision 31 March 1988 Page 10 of 15
- 7. EXAMINATION 7.1 Examination Areas The area to be examined shall include the support skirt attach-ment weld, base material beneath the weld, and adjacent base material of the support skirt attachment for a distance of 2t of support thickness from the fusion line of the weld.
Ultrasonic examination of vessel support skirt attachment welds shall be performed from the outside surface of the vessel and support skirt attachment. 7.2 Surface Condit.ion The contact surfaces must be free from weld spatter, roughness, or other conditions that interfere with free movement of the search unit or impair the transmission of ultrasound. 7.3 Scanning When practicable, scanning shall be performed at a minimum gain setting of two times the reference level sensitivity.
- Instrument gain setting for scanning shall be determined on the basic calibration block as follows for each primary reference level utilized:
(1) Yith the instrument at the primary reference level, manipu-late the search unit on the basic calibration block to obtain a signal of 40% FSH from a calibration reflector (hole). (2) Add 6 dB of gain by utilizing the 6 dB switch (if present), the fine gain control, or a combination of the fine and coarse gain controls and choose any method which yields a signal response within +/-2 dB of 100% FSH. *
* (3) This amplitude and method shall be recorded on the SwRI Sonic Instrument Calibration Record and shall be used during the valid calibration period for all scanning at five times the reference level sensitivity.
The search unit movement rate for scanning shall not exceed' 6 inches per second. Scanning overlap shall be a minimum of 10% of the search unit piezoelectric element dimension perpendicular to the direction of scan. SwRI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-16 Revision 31 March 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 11 of 15 7.5 Butt and T Welds of Support Attachm~nt 7.5.l Angle-Beam Examination for Indications Parallel with the Weld Angle-beam examinations shall be accomplished using the appropri-ate angle of refracted shear wave from both sides of the support skirt butt weld, when possible, or from the support skirt side of the T weld. For these examinations the sound beam shall be directed perpendicularly into the weld to detect indications which are parallel with the weld. 7.5.5 Angle-Beam Examination for Indications Perpendicular to the Weld An angle-beam examination shall be conducted on the weld and the required volume of base material using a 45° refracted shear-wave search unit. This examination shall be conducted by placing the search unit on the weld and base material with the sound beam directed into and parallel with the weld to detect indications perpendicular to the weld. .The entire length of the weld required to be examined, when possible, shall be scanned with the search unit sound beam directed in this manner from two opposing directions. 7.6 Postexamination Cleaning Arrangements shall be made with the customer for postexamination removal of couplant materials.
- 8. RECORDING CRITERIA 8.1 Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Nuclear Projects Operating Procedure IX . . FE-117.
8.2 Ultrasonic reflectors producing a response equal to or greater than 50% of the reference level shall be recorded (see Table 1). 8.3 Ultrasonic reflectors producing a response equal to or greater than 100% of the reference level shall be investigated by a Level II or Level III examiner to determine the shape, identity, and location of all such reflectors in terms of the flaw indication characterization rules and acceptance standards of IWA-3000. Reflectors investigated and found to be other than geometry shall be reported to the customer. 8.4 The size of reflectors shall be measured between points that give amplitudes equal to 100% of the reference level (see Table l) . 8.5 Recordable indications attributable to geometry shall be recorded only once, even if the amplitude of the indication drops below the required recording amplitude along its length. Geometric indications need not be charac-terized or compared with the acceptance standards of IWA-3000. SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-16 Revision 31 March 1988 Page 12 of 15 8.6 Scanning limitations shall be recorded. Table 1 Data required when reflector* amplitude is equal to or greater than 50% DAC:
% W max L Search Unit Search Unit DAC WIMP Max Location Angle Data required when reflector amplitude is equal to or greater than 100% DAC:
% .100% DAC W max 100% DAC L1 L L2 s.u. s.u.
DAC I I 100% DAC 100% DAC Location Angle W1 MP WIMP W2 MP MAX I
/
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI personnel. Final evaluation and disposition of reportable indications shall be the responsibility of the customer.
- 10. RECORDS Documents generated in accordance with this procedure shall be stored as specified in the SwRI Project Plan. *The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan.
SwRI Form QA 3-2
SwRI-NDT-600-16 HWEST RESEARCH INSTITUTE Revision 31 March 1988 NUCLEAR PROJECTS OPERATIN
G. PROCEDURE
Page *13 of 15
- Examination Volume A-B-C-D-E-F
....,.__Integral attachment iJ.. t S' r E
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UTHWEST RESEARCH INSTITUTE
. NUCLEAR PROJECTS OPERATING PROCEDURE .
SwRI-NDT-600-16 Revision 31 March 1988 Page 14 of 15 I I I i
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SKETCH 2 TYPICAL SUPPORT SKIRT BUTT WELD CONFIGURATION ~3-2
SwRI-NDT-600-16 THWEST RESEARCH \NST\TUTE Revision 3J. March 1988 Page 15 of 15 NUCLEAR PROJECTS OPERATING PROCEDURE SKETCH 3 TYPICAL SUPPORT SKIRT T YELD CONFIGURATION I
-f' mQA3-2
PROCEDURE DEVIATlON Page 1 of 1 Pages r-' 600-18 Revision No. 42 I Deviation No. 2 ing examination areas are affected by this deviation: on to b~ performed in accordance with this procedure. ing paragraphs shall be deviated from as indicated: graph 6.2.4 to read as follows: on of Calibration Reflectors miner shall verify the presence of the calibration reflector at scanning speed. It is not necessary to assure that this check confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the signal from the calibration reflectors are readily observable at scanning speed. llowing st.atement shall be* documented on the SwRI Calibration Record Sheet and
- ed: "Calibration reflectors have been verified at scanning speed'.'
or deviation: ation complies with the NRC's requests to verify the presence of the calibration reflectors cedural scanning conditions. If the deviation is determined to arlec:t :he procedure ffects n YES D NO f& aualific:mon. the deviation shall be aua1ified in accordance with f'roce<Sure IX-FE-107. APPROVALS SA fLJ) Date: Tec~I ..-=.'~ew: 3- 7-8' r
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°;)7/$cf f Q.A.: V'HM- 3/ 71 W
-ii7 Date:
Verbal-Approval Given 7 Cognizant Director: CJ Yes 12!-No Date: Date: 3/q !31 Jj//1/t~ ~/kviiv )c~/ 3/1 Y/tiI
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-:-18 Revision 42 NUCLEAR PROJECTS June 1987 OPERATING PROCEDURE Page l of 11 MANUAL ULTRASONIC EXAMINATION OF PRESSURE-RETAINING STUDS AND BOLTS GREATER THAN 2 INCHES IN DIAi."1ETER CONTAINING ACCESS HOLES
- EFFECTIVITY ANO APPROVAL ision 42 of this procedure became effective on June 23, 1987 Other revisions of the base document may ffective concurrently.
SA Technical Review Date
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. :£-A~ 1'it7
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The following information may be used for convenience. Completion of this portion is not mandatory. ion No. ffective dure Section(sl ed
- orm QA*-10A*O
SOUTHWEST RESEARCH IN.STITUTE SwRI-NDT-600-18 Revision 42
~
June 1987
* . NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 11 " MANUAL ULTRASONIC EXAMINATION OF PRESSURE-RETAINING STUDS AND BOLTS GREATER THAN 2 INCHES IN DIAMETER CONTAINING ACCESS HOLES
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure a proper ultrasonic examination of pressure-retaining studs and bolts, in accordance with the applicable American Society of Mechanical Engineers *(ASME) Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION (1) Pressure-retaining studs and bolts greater than 2 inches in diameter with access holes.shall be examined as specified in the applicable, Southwest Research Institute.(SwRI) Examination Plan.
(2) Shear-wave angle-beam, manual, contact pulse-echo ultrasonic examina-tion techniques utilizing a manual stud e~amination probe shall be used to locate flaws that are oriented perpendicular to the axis of the stud.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) Code Case N-307-1 (4) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Calibration and Examination Records SwRI NDTR Form No. Revision Date 17-19 12-1-83 17-27 2-03-82 17-37 2-18-80 SwRI Form QA 3-2
-I.ST RES_EARCH.INSTITUTE SwRI-NDT-600-18 Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 3 of 11 IIBILITY
~he Director of the Department-of Engineering Services, Nondestruc-
- ive Evaluation Science and Technology Division, shall be responsible
- or the preparation, review, approval, and control of this proc_edure.
~he Project Manager shall be responsible for the implementation of his procedure in accordance with the NQAPM specified in the appli- ~able SwRI Project Plan. he examiner shall be responsible for implementing the requirements f this procedure. he Manager of the Support and Administration Section, Nondestructive Evaluation Science and Technology Division,1shall be responsible for torage of records generated in accordance with this procedure. EL AND EQUIPm:NT
~*nnel Certification Personnel performing ultrasonic examinations shall be certified in ith SwR! NQAP 11-1, "Spec~al Process Control."
Reference Block Reference blocks used for screen distance calibration and verifica-e of the same basic material as the production material, carbon hall be one of the following: (1) SwRI Half~round, (2) AWS Type DC, Reference blocks shall be used as follows for the angle-beam screen libration: Screen Distance Block Type Block Dimension s.o" SwRI Half-Round 1.0" Radius AWS Type DC 1.0" and 2.0" Radii 10.0" SwRI Half-Round 1.0" Radius AWS Type DC 1.0" and 2.0" Radii IIW' Block 4.0" Radius
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-18 Revision 42
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5.3 NUCLEAR PROJECTS OPERATING PROCEDURE Basic Calibration Block June 1987 Page 4 of 11 The basic calibration block shall be fabricated from. material of the same material specification, product form, and heat-treatment as the compo-nent to be examined. It shall be threaded as the component and have an aecess hole equal in size to that of the component *to be examined. The basic calibra-tion reflectors shall be notches machined one thread deep, or 1/8-inch deep, whichever is smaller. Notches shall be measured from the base of the thread root and shall follow the lead angle of the threads. The particular notch util-ized for the calibration shall be identified on the applicable SwRI Sonic Instru-ment Calibration Record. The scanning surface of the calibration block shall be representative of the scanning surface of the component. Approved drawings of the basic calibration block are contained in the applicable SwRI Examination Plan. 5.4 Search Units (1) The sear.ch unit shall have an active element size of l/ 4" x 1/4" or 1/4" round. (2) A special search unit wedge shall be used to produce a 60° :2° refracted shear-wave. This angle and the exit point of the sound beam shall be determined on an IIW block. The exit point shall be marked on the search unit wedge. (3) The nominal search unit frequency shall be 2.25 MHz. 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1. 5.6 Couplant (1) USP-grade glycerine or reactor-grade water shall be used when performing ultrasonic calibrations and examinations in accor-dance with this procedure. (2) All couplants other than reactor-grade water shall be certi-fied for sulfur content and total halogens in accordance with. SD-129 and SD-808 of Article 24, Section v. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Reac_tor-grade water, when used, shall be supplied by the customer. SwRI Form QA 3*2
OUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-18 Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 5 of 11 (3) Couplant materials used for examinations shall be the same as used for the calibration. 5.7 Thermometer The thermometer to be used for measuring the calibration block and component temperatures shall be calibrated and certified and shall display a valid calibration tag as required by NQAP 10-1.
- 6. CALIBRATION METHOD 6.1 Instrument Linearity Ultrasonic instrument linearity shall be verified once prior to and once after completion of a period of extended use or every three months, which-ever is less, in accordance with Paragraphs 6.1.1 and 6.1.2. Data required shall be recorded on the applicable SwRI Instrument Linearity Verification ecord, a~d the sheet number shall be referenced on each applicable SwRI Sonic strument Calibration Record.
If due to instrument failure a linearity verification cannot be performed, the calibration verification of Paragraph 6.3 shall constitute evi-dence of the instrument linearity. If a calibration verification does not fall within the tolerances required by Paragraph 6.3.1 due to instrument failure, an instrument linearity check must be performed prior to continuing examinations, and all components examined since the last valid calibration verification shall be reexamined. NOTE The setting of the damping control shall be recorded on the applicable SwRI Instrument Linearity Verification Record. The damping control shall be in the same position during linearity verification, calibrations and examinations or a new linearity verification shall be performed. 6.1.l Screen Height Linearity (1) Position a shear-wave search unit on a calibration block to obtain indications from the l/2T and 3/4T holes (the cali-bration block for amplitude linearity verification may not be the basic calibration block specified for calibrating dis-tance amplitude correction curves in accordance with this procedure). SwAI Form QA 3-2
UTHWEST RESEARCH INSTITUTE SwRI-NDT-600-18 Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 11 EXCEPTION tively, a straight-beam search unit may be used on any calibration block ovides amplitude differences with sufficient signal separation to prevent ping of the two signais. (2) Adjust the search unit position to give a 2:1 ratio between the two indications, with the larger indication set at 80% of full screen height (FSH) and the smaller indication set at 40% of FSH. (3) Without moving the search unit, set the larger indication to 100% of FSH and record the amplitude of the smaller indica-tion, estimated to the nearest 1% of FSH. (4) Successively set the larger indication from 100% to 20% of FSH in 10% ~ncrements (or 2 dB steps if a fine control is not available); record the smaller indication estimated to the nearest 1% of FSH at each setting. The reading must be 50% of the larger amplitude within 5% of FSH. Amplitude Control Linearity (1) Position a shear-wave search unit on a calibration block to obtain maximum amplitude from the 1/2T hole. NOTE imary reference level sensitivity should be within the highest and lowest ttings used during amplitude control linearity verifications. The high-lowest gain settings used during the amplitude control linearity verifi-shall be recorded in the Remarks column of the applicable SwRI Linearity ation Records. (2) Without moving the search unit, set the indication to the required percent of FSH and increase or decrease the dB as specified below. The signal shall be recorded to the nearest 1% of FSH and shall fall within the limits of the following table: 3-2
EST RESEARCH INSTITUTE SwRI-NDT-600-18 Revision 42 June 1987 NUCLEAR PROJECTS OPERATJNG PROCEDURE Page 7 of 11 Indication dB Control Indication Set at % of FSH Change* Limits, % of FSH 80% '-6dB 32 to 48% 80% -12dB 16 to 24% 40% +6dB 64 to 96% 20% +12dB 64 to 96%
*Minus denotes decrease in amplitude; plus denotes increase.
Calibration The ultrasonic calibration shall be completed prior to the on. The REJECT control shall be maintained in the 0 position during on and examination. ~ The FREQ MHz control shall be turned to 2. The type and length of the search unit cable shall be recorded on. Sonic Instrument Calibration Record, and all other information blocks rm shall be filled in.
.l Temperature The calibration block temperature shall be ~ithin 25°F of the com-mperature and shall be recorded on the SwRI Sonic Instrument Calibra-rd for the initial calibration and each verification. The surf ace tem-of the component to be examined shall be taken prior to and after g and upon completion of each examination and shall be recorded on the e SwRI Examination Record. .2 Distance Calibration Using the applicable reference block selected in accordance with 5.2, set up the required sound path distance along the screen base-e screen distance chosen shall be the smallest applicable size which at least 10% of the screen distance past the examination area. .3 Distance Amplitude Correction (l) Position the applicable Manual Stud Examination Probe in the access hole of the basic calibration block to obtain maximum response from the notch reflector nearest the center of the
- threaded portion of the block.
JTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-18 Revision 42 June 1987 Page 8 of 11 (2) Set this signal to 80% +/-5% of FSH and mark its amplitude on the screen. The gain controls shall not be adjusted once this primary reference response has been established. Indi-cations shall be recorded as a percentage of this signal amplitude. (3) A line shall be drawn on the instrument screen *at a distance of at least 0.50 inch prior to the calibration point. The examiner must assure that the distance between this line and the calibration point as d~splayed on the instrument screen encompasses the examinati.on area described in Section 7 .1. Sweep Range and Distance-Amplitude Calibration Verification;, Sweep range and distance amplitude calibrations shall be verified ppropriate reference and basic calibration block when any of the follow-rs: (1) (2) (3) Prior to a series of examinations With any substitution of the same type and length of search unit cable With any substitution utilizing the same type of power source; e.g., a change of batteries (4) At least every 4 hours during-the examination (5) At the completion of a series of examinations (6) Whenever the validity of the calibration is in doubt 3.1 Calibration Changes (l) Perform the following if any point on the DAC curve has decreased more than 20% or 2 dB in amplitude, or if any point on the DAC has moved on the sweep line more than 10% of the sweep division reading or 5% of full sweep, whichever is greater: (a) Void all examinations referring to the calibration in question and performed after the last valid calibration verification. (b) Conduct a new calibration. (c) Reexamine the areas for which examinations have been voided.
UTHWEST RESEARCH INSTITUTE SwRI-NDT-600-18 Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 9 of 11 (2) Perform the following if any point on the DAC curve has increased in amplitude more than 20% or 2 dB: (a) _Correct the calibration. (b) Reexamine all indications recorded since the last valid calibration verification. (c) Enter proper values on a n~w SwRI Examination Record. 6.3.2 Recalibration Substitution of*any of the following shall be cause for recali-bration: (1) Search unit wedge or transducer (2) Search unit cable type or length (3) Ultrasonic instrument (4) Examination personnel (5) Couplant (6) Change in type of power source; e.g., a change from direct to alternating current 7* EXAMINATION 7.1 Examination of Pressure-Retaining Studs and Bolts Forged studs and bolts shall be examined from the inside surface of the access hall'!* The examination area *shall include the thread root and 1/4 inch as measured inward from the thread root (with the exception of the nonload-bearing portion beyond the nut). The outer 1/4 inch of the nonthreaded. portion shall also be examined. 7.2 Surface Conditions The contact surfaces must be free from roughness or other.condi-* tions that interfere .with free movement of the search unit or impair the trans-mission of ultrasound. I Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-18 Revision 42 June 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 10 of 11 7.3 Scanning Parameters When practicable,*scanning shall be performed a~ a minimum gain_ setting of 2 times the reference level sensitivity. Instrument gain setting for scanning shall be determined on the basic calibration block as follows for.each primary reference level utilized: (1) With the instrument a~ the primary reference level, manipu-late the search unit in the basic calibration block access hole to obtain a signal from a calibration reflector (machined notch) of 40% FSH. (2) Add 6 dB of gain by utilizing the 6 dB switch (if present), the fine gain control, or a ccmbination of the fine and coarse gain controls and choose any method which yields a signal response within =2 dB of 80% FSH. (3) This amplitude and method shall be recorded on the SwRI Sonic Instrument Calibration Record and* shall be used during the valid calibration period for all scanning at 2 times the reference level sensitivity. The search unit movement rate shall not exceed 6 inches per second. Scanning overlap shall be a minimum of 10% of the search unit piezo-electric element dimension perpendicular to the direction of scan. 7.4 Postexamination Cleaning Arrangements shall be made with the customer for postexamin~tion remov~l of couplant materials.
- 8. *RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-117.
Ultrasonic reflectors producing a response greater than 50% of the ref er-ence level shall be recorded on the applicable SwRI Examination Record. Indications producing a response greater than 100% of the reference level shall be investigated by a Level II or a Level III examiner to determine the shape, -identity, and location of the reflector. RI Form QA 3-2 *
-r8EST RESEARCI INSTITUTE SwRI-NDT-600-18 Revision 42 June 1987 NUCLEAR PROJECTS OPERA NG PROCEDURE Page 11 of 11
- ations greater than 100% of -:i.e reference level, investigated and other than geometrical in c :u~~' shall be reported to the customer
- ion.
ing limitat.ions s_hall be rec cded. ATION Lal evaluation of reportable ndications shall be performed by SwRI and shall be conducted in ac ordance with the applicable AS}!E Boiler e Vessel Code, Section XI, c ticle IWA-3000. Final evaluation and of reportable indications t all be the responsibility of the DS ments generated in accordanct with this procedure shall be stored as n the SwRI Project Plan. Tl customer shall receive copies of these n & Examination Report, u: .ess specified otherwise in the SwRI an~
- Procedure SwRl-NDT- 600-26 PROCEDURE DEVIATION The following examination areas are affected by this deviation:
Revision No. 12 I Pa~e Deviation No. 1 of 1 1 Pages Ultrasonic examinations performed with this procedure shall be affected by this deviation. The following paragraphs shall be deviated from as indicated: Add to the end of Paragraph 6.4: Verification of Calibration Reflectors at Scanning Speed-The examiner shall verify the presence of the calibration reflector at scanning speed. It is not necessary to assure that this check confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the signal from the calibration reflectors are readily observable at scanning speed.
- The following statement shall be documented on the SwRI Calibration Record and initialed: "Calibration reflectors have been verified at scanning speed."
Rationale for deviation: This deviation incorporates customer request to verify calibration reflectors scanning speed. Deviation Affects YES 0 NO ~ If :he deviation is cetermined to affect the prccecure Qualification, the deviation shall be cualified in I Qualification accordance with Prccecure IX-FE-107. APPROVALS Written b:(! Date: I
,::!>Jr1 1~..:::1 I Date:'
Date: Cognizant Director: Date:
!kw~~~
SwRI FOnM FE-4-6
SwRI-NDT-.600- 26
~SOUTHWEST RESEARCH INSTITUTE Revision 12 NUCLEAR PROJECTS November 1988 OPERATING PROCEDURE Page 1 of 11 Title MANUAL ULTRASONIC EXAMINATION OF THIN WALL VESSEL WELDS (0.1 to 0.4 INCH THICK)
EFFECTIVITY AND APPROVAL Revision 12 of this procedure became effective on Nov 23, 1988. Other revisions of the base document may be effective concurrently. SA fl}) Approvals Wcittoo By ~ ( 1ll'iS-2 [ (/-/- . .j 1~-1'L\ Date z3J~ Technical Review
~ /
/~
~
Date Z~AI~ I L --~ -- ' !9/'fl
/~ ~
Manager of Q.~ Date Cognizant Director
- Date
-J,_pc
.. :tA I~
J 11h3/:;2 /Jwu( ~k frdW 11/z~jss
*The following information may be used for convenience. Completion of this portion is not mandatory.
Deviation No. ' Date Effective Procedure Section(s) Affected Notes:
- SwRI Form QA--lOA*O
SwRI-NDT-()00-26 SOUTHWEST RESEARCH INSTITUTE Revision 12 November 1988 NUCLEAR PROJECTS .OPERATING PROCEDURE Page 2 of 11 MANUAL ULTRASONIC EXAMINATION OF THIN WALL VESSEL WELDS SwRI-NDT-600-26/12
- 1. PURPOSE This procedure provides the*technical information and detailed steps necessary to ensure a proper manual ultrasonic examination of thin wall pressure vessel welds and adjacent base material, in accordance with the applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION Pressure vessel welds in the thickness range from 0.1 to 0.4 inch, adjacent ba.se material, heat-affected zone (HAZ), and nozzle-to-shell welds shall be examined as specified in the applicable Southwest Research Institute (SwRI)
Examination Plan. Manual, contact, pulse-echo shear-wave angle-beam ultrasonic techniques shall be utilized.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules* for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination," with the exception of the following:
(3) ASME Boiler and Pressure Vessel Code, Section IX, 1983 Edition with Addenda through Summer 1983, "Welding and Brazi!_lg Qualifications" (4) SwRI Nuclear Quality Assurance Program Manual (NQAPM) Swnl Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-26 Revision 12 Nov.ember 1988 Page 3 of 11 3.1 Applicable Calibration and Examination Records SwRI NDTR Form No .. Revision Date 17-19 12-01-83 17-126 01/15-86 17-127 01/15/86
- 4. RESPONSIBILITY (1) The Director of the Department of NDE Services, Nondestructive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval', and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this.procedure in accordance with the NQAPM in effect on the date this procedure is approve4 .
- (3)
(4) The examiner shall be responsible for implementing the requirements of this procedure. The Manager of Quality Assurance shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations in accordance with. this proce-dure shall be certified in accordance with SwRI Nuclear Quality Assurance Procedure (NQAP) 11-1, "Special Process Control."
5.2 Reference Block Reference blocks used for screen distance calibration and verifi-cation shall be of the same basic material as the production material, stainless steel or carbon steel, and shall be one of the following: (1) SwRI Half-Round, (2) AWS Type DC, or (3) IIW.
- 5.3 Basic Calibration Block Approved drawings of the basic calibration block are contained in the applicable SwRI examination plan .
SwRI Form QA 3-i
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-26 Revfsion 12 November 1988 Page 4 of 11 5.4 Search Units (1) Search units shall be selected form the following: (a) Angle Beam (Shear-W?ve) Average Weld Thickness Nominal Search Unit Size 0.1" to 0.4" 1/4" x 1/4", 1/4" Round, 0.2" to 0.4" 3/8" x 3/8", 3/8" Round (2) The exit point of the sound beam and the actual refracted beam angle of shear-wave search units shall be determined on an IIW reference block. The exit point shall be marked on
*the search unit wedge.
(3) The nominal shear-wave search unit frequency for examination of austenitic material shall be as follows: Nominal Frequency 2.25 MHz 1.5 MHz Search Unit Size 1/4" Round, 1/4" x 1/4", 3/8" Round, 3/8" x 3/8" (4) The nominal shear-wave search unit frequency for ferritic vessel welds shall be 2.25 MHz. (5) The search unit wedges shall be fabricated as required to produce a 45 +/-2° refracted shear wave.as demonstrated on the IIW block. In addition to the 45 shear-wave search unit wedge, other angles may be used to supplement the examination. 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark.I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1.
- 5. 6. Couolant (1) USP-grade glycerine, Sonotrace 40, or Ultragel II shall be used when performing calibrations and examinations in SwRr Form QO.. 3*2 accordance with this procedure.
- SOUTHWEST RESEARCH.INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-26 Revision 12 November 1988 Page 5 of 11 (2) Other couplant materials*may be used if approved by the
. Project Manager*.
(3) Couplant materials used shall b~ certified for sulfur content and total halogens. The residual amount o.f total sulfur or halogens shall not exceed 1% by weight. (4) Couplant materials used for examinations shall be the same as used for the calibration. 5.7 Thermometer The thermometer to be used for measuring the calibration block and component temperatures shall be calibrated and certified and shall display a valid calibration tag as required by NQAP 10-1.
- 6. CALIBRATION 6.1 Calibration The ultrasonic calibration shall be comple:ted prior to the examination.
The REJECT control shall be maintained in the 0 position during calibration and examination. The. centerline of the search unit shall be at least 1-1/2 inches from the nearest side of the calibratio.n block. Rotating the beam into the corner formed by the hole and the side of the block may produce a higher amplitude signal at a longer beam path. This signal shall not be used for calibration. The FREQ MHz control shall be turned to 1 with a 1.5-MHz search unit, to 2 with a 2.25-MHz search unit, and to 5 when a 5.0-MHz search unit is used. The type and length of the search unit cable shall be recorded on the SWRI Sonic Instrument Calibration Record and all other information blocks on this form shall be filled in. 6.1..1 Temoerature The calibration block temperature shall be within 25°F of the component temperature and shall be recorded on the SwRI Sonic Instrument Calibration Record for the initial calibration and each verification. The surface temperature of the component to be examined shall be taken prior to and SwAI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-26 Revision 12 November 1988 Page 6 of 11 after completion of each examination and shall be recorded on the applicable SwRI Examination Record.* 6.. 2 Angle-Beam Distance Calibration Position the search unit on the appropriate reference block, observe the radius echoes and adjust the instrument controls to ensure a linear sound path distance along the instrument screen baseline. Select the shortest screen qistance size which will include at least 1/8 vee-path beyond the 11 anticipated examination range. 6.3 Distance Amplitude Correction 6.3.l Angle-Beam DAC DAC curves shall be constructed from notches perpendicular to the axis of curved basic calibration blocks when examining circumferential welds. DAC curves shall be constructed from the axial notches of curved basic calibra-. tion blocks for examinations of longitudinal welds and nozzle-to-shell welds . The DAC curve shall be constructed as follows:' (1) Position the search unit on the basic calibration block to obtain maximum response from the vee-path position, selected from the following, that produces the highest amplitude: Vee-Path Positions 4/8, 8/8, 12/8 (2) Set this response to the primary reference leve.l of 80% +/-5% and mark its amplitude on the instrument screen. (3) Without changing the gain controls, obtain maximum response from the remaining vee-path positions; mark and join all amplitude points with a smooth curved line that shall not extend more than 1/8 vee-path past the last qualified calibration point. EXCEPTION If the configuration of the weld is such that the full vee-path examination fails to cover the entire weld volume, a 16/8 vee-path calibration shall be
*accomplished.
SwAI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS .OPERATING PROCEDl,JRE SwRI-NDT-600-26 Revision 12 November 1988 Page 7 of 11 6.4 Secondary DAC Calibration Each point on the DAC curve shall appear at .a minimum of 20% FSH or a secondary DAG curve shall be constructed as follows: >
(1) Secondary DAG curves shall contain at least 2 points. (2) The DAG point at the 8/8 vee-path position shall be brought to the 80% +/-5% FSH and marked on the instrument screen. The 12/8 vee-path position, previously at less than 20% of FSH, shall be marked on the screen and these points connected with a smooth curved line. The instrument gain settings for _this secondary DAG curve shall be recorded on the appro - priate SwRI Sonic Instrument Calibration Record. EXCEPTION When the 8/8 vee-path position is set at the primary reference level, and the 12/8 vee-path position is below 20% of FSH, a secondary DAG curve is ,not required. 6.5 Calibration Verification 6.5.l Sweep Range and DAG Curve Verification Sweep range and DAC curve shall be verified on the appropriate reference and basic calibration block when any of the following occur: (1) Prior to a series of examination (2) Substitution of the same type or length of search unit cable (3) Substitution of the same type of power source; e.g.' a change of batteries (4) At least every 4 hours during the examination (5) At the completion of a series of examinations (6) Whenever the validity of the calibration is in doubt 6.5.2 Calibration Changes
- (1) Perform the follo~ing if any point on the DAC curve has decreased more than 20% of FSH or 2 dB in amplitude, or if any point on the DAG curve has moved on the sweep line more SwRI Form QA 3-2
SwRI-NDT~600-26 SOUTHWEST RESEARCH INSTITUTE Revision 12 November 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 11 than 10% of the sweep division reading or 5% of full screen width, whichever ;s greater: (a) Void all examinations referring to the calibration ~n question and performed after th~ last valid calibra-tion verification. (b) Conduct a new calibration. (c) Reexamine the areas for which examinations have been voided. (2) Perform the following if any point on the DAC curve has increased in amplitude more than 20% or 2 dB: (a) Correct the calibration. (b) Reexamine all indications recorded since the last valid calibration verification. (c) Enter proper values on a new SwRI Examination Record. 6.5.3 Recalibration Substitution of any of the following shall be cause for recalibration: (1) Search unit transducer or wedge (2) Search unit cable type_ or length (3) Ultrasonic instrument (4) Examination personnel (5) Couplant (6) Change in type of power source; e.g., a change from direct to alternating current
- 7. EXAMINATION 7.1 Examination VolumP-The examination volume shall be the weld and adjacent base mate~
rial for a distance of 1/2 inch from the fusion line on each side of the weld. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-26 Revision 12 November 1988 Page 9 of 11 7.2 Surface Condition The contact surfaces shall be free from weld spatter, roughness, or other conditions which interfere with free movement of the search unit or impair the transmission of ultrasound.
7.3 Scanning When practical, scanning shall be performed at a minimum gain setting 5 times the reference level sensitivity. If 5 times reference level is not possible, the limitation shall be recorded on the examination record. The search unit movement rate for scanning shall not exceed 6 inches per second. While scanning, the search unit shall be oscillated approxi-mately _+/-20°. Scanning overlap shall be a minimum of 25% of the search unit piezoelectric element dimension perpendicular to the direction of scan . 7.4 Longitudinal and Circumferential Butt Welds in Vessels 7.4.l Angle-Beam Examination for Reflectors Parallel with the Weld The examination shall be performed with a sufficiently long examination metal path to provide coverage of the required examination volume in two beam path directions. The examination shall be accomplished from each side of the weld. When an examination cannot be accomplished from both sides of the weld, an examination shall be performed from at least one side of the weld. 7.4.2 Angle-Beam Examination for Indications Perpendicular to the Weld The examination shall be conducted on the weld and the base material on both sides of the weld by placing the search unit on the surface of the weld and base material with the sound beam directed in an axial orientation with respect to the weld i:o detect indications perpendicular to the weld. The entire length of the weld and adjacent base material shall be scanned with the search unit directed in this manner from two opposing directions. Scanning coverage for this examination shall extetld a minimum of 1/2 inch from the weld fusion line. SwRI Form QA 3-2
SwRI-NDT-600-26
*SOUTHWEST RESEARCH INSTITUTE Revision 12 November 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 10 of 11 7.5 Nozzle-to-Shell Welds in Vessels 7.5.l Angle-Beam Examination for Reflectors Parallel to the Weld The examination shall be accomplished from the vessel side of the weld. The examination shall be performed with a sufficiently long examination metal path to provide full coverage of the required examination volume, when possible. Other angles may be used to supplement the examination.
7.5.2 Angle-Beam Examination for Indicat.ions Perpendicular to the Weld The examination shall be conducted on the weld and on the vessel base material by placing the search unit on the weld surface and required base material parallel to the weld. Scan the entire length of the weld and base material with the search unit fro*m i:wo opposing directions. Scanning coverage for this examination shall be the weld and extend a minimum of 1/2 inch from the weld fusion line.
- 8. RECORDJNG CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-117 except as noted below.
Indications producing a response 20% or greater of the reference level shall be recorded and investigated by a level II or a Level III examiner to determine the shape, identity, and location of the reflector. Indications 20% or greater of the reference level attributable to geometry shall be recorded only once, even if the amplitude of the indication drops below the required recording amplitude along its length. These indications shall be investigated by a Level II or a Level III examiner to determine the shape, identity, and location of the reflector. If indications that have been recorded as geometry have been investigated and found to be nongeometric reflectors, the entire weld shall be reexamined, recording all nongeometric reflectors and other reflectors not previously recorded at least once. All ultrasonic reflectors, regardless of signal amplitude, not readily attributable to geometry by the examiner, shall be recorded on the appropriate Ultrasonic Examination Record and investigated by a Level II or a Level III examiner to determine the shape, "identity, and location of the reflector. Examples of nongeometric reflectors are those which are slightly removed from the weld root and/or chamfer, mask the root indications, are transverse to the weld, or have linear dimensions with side branches.* SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-26 Revision 12 November 1988 Page 11 of 11 Indications investigated and.'found to be other than geometrical in nature shall be reported to the customer for evaluation.
Scanning*limitations shall be recorded. 9* EVALUAT I ON Initial evaluation of reportable indications shall be performed by SwRI personnel, and shall be conducted in *accordance with the applicable ASME Boiler and Pressure Vessel Code, Section XI, IWA-3000. Final evaluation and disposi-tion of reportable indications shall be the responsibility of the customer.
- 10. RECORDS Documents generated in accordance with this procedure shall be stored *as specified in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI
- Project Plan .
SwAI Form QA 3*2
PROCEDURE DEVIATION' Page 1 of Pages 1 Procedure Revision No. Deviation No. SwRl-NDT- 600-31 23 1 The following examination areas are affected by this deviation: Angle beam examinations performed in accordance with this procedure. The following paragraphs shall be deviated from as indicated: Change Paragraph 6.6.2 to Read as follows: 6.6.2 Verification of Calibration Reflectors at Scanning Speed and Notch Comparison (1) The examiner shall verify the presence of the calibration reflector at scanning speed. It is not necessary to assure that this check con.firms the signal amplitude at 100% of reference level, but merely to demonstrate that the signals from the calibration reflectors are readily observable at scanning speed. The following statement shall be documented on the SwRI Sonic Instrument Calibration Record and initialed:
"Calibration reflectors have been verified at scanning speed."
(2) A notch and side drilled hole comparison shall be performed to verify notch sensitivity. I I The sensitivity will be established on an inside surface notch by setting the signal amplitude at the level of the DAC curve and marking *with an X. Record the gain setting i i under Instrument Setting. Rationale for deviation: This deviation incorporates the comparison of notches and side drilled holes as requested by Public Service and Gas Company. Deviation Affects If the deviation is determined to affect the ~rocecure I' Qualification YES 0 NO IZJ qualification. the ceviation s1'all be qualified in - accordance with Procedure IX-FE* 1C7. APPROVALS Written by: Date: Technic Date:
)-/f,,,-f-f'
'~~\~~ D No
., Date:
Manager of Q.A.: Date: Cognizant Director: Date:
.!\ ~ ',
'/!o~!.Y-/'faJ~re-r ;(.. 1-r._h 9f rJ CJ SwAI FOAM FE-4-B
SwRI-NDT-600-31
~ SOUTHWEST RESEARCH INSTITUTE Revision 23 NUCLEAR PROJECTS -
December 1987 OPERATING PROCEDURE Page 1 of 22 Title MANUAL ULTRASONIC EXAMINATION OF AUSTENITIC PRESSURE PIPING WELDS EFFECTIVITY AND APPROVAL 23 of this procedure became effective on Dec 22, 1987. Other revisions of the base document may I Revision be effective concurrently. SA Approvals , fJ) Written By Date Technical Review Date PA~ f°'11' pivf I). j ;,J,;,, ?"~!fl~ Fq- J7l1 I ')./J.;./p-J
- Manager of Q.A.
!U£~~!/-~rc-r u I'
* *Date 1-z../z.z/~
Cog?i ?.nt Director The following information may be used for convenience. 1i~01~,
- 1 f-Ywi C~l.:f~ ..
- d.
Date
. if>>_/r'7 I amp et1on o t 1s portion 1s not man atory.
I Deviation No. Date Effective Procedure Section (s) Affected Notes:
- SwRI Form QA-40A-O
SwR -NDT-SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE Revision 23 December 1987 Page 2 of 22
- MANUAL ULTRASONIC EXAMINATION OF AUSTENITIC PRESSURE PIPING WELDS SwRI-NDT-600-31
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure a proper m.anual ultrasonic examination of similar or dis-similar metal welds and adjacent base material in clad or unclad austenitic pressure piping .in accordance with the applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION Manual,. contact, pulse-echo, shear-~ave angle-beam, and longitudinal-wave straight-beam ultrasonic techniques shall be utilized for the examination of austenitic pressure piping welds and adjacent base material in a nominal thick-ness range of greater than 0.4 to 5.0 inches.
Welds to be examined in wrought austenitic material shall be similar or dissimilar metal circumferential welds, longitudinal pipe welds, and branch connection full-penetration butt welds as specified in the applicable Southwest Research Institute (SwRI) Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Calibration and Examination Records SwRI-NDTR Form No. Revision Date 17-18 3-14-79 17-19 12-1-83 17-25 7-10-80 17-37 2-18-80 17-89 8-19-80 17-90 8-19-80 SwRI Form QA 3*2
SwRI-NDT-600-31 Revision 23 SO.UTHWEST RESEARCH INSTITUTE December 1987
~ Page 3 of 22 I~~ NUCLEAR PROJECTS OPERATING PROCEDURE l'f'1:1111". ~If//.J..--1~
- ,ir\. //
- 4. RESPONSIBILITY
*. (1) The Director of the Department of Engineering Services, Nondestruc-tive Evaluation Science and Technology D~vision, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be re.sponsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan. _(3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Support and Administration Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with th~s procedure. ~-
- 5. PERSONNEL AND EQUIPMENT
- 5.1 5.2 Personnel Certification Personnel performing ultrasonic examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control."
Reference Block Reference blocks used for screen distance calibration and verifi-cation shall be of the same material as the production material; i.e., stainless steel or carbon steel, and shall be one of the following: (1) SwRI Half Round, (2) AW'S Type DC, (3) IIW', or (4) Rompus Block. Reference blocks shall be used as follows for screen distance calibration: (1) Straight-Beam Screen Block Distance Block Type Dimension 1.0", 2.0" SwRI Half-Round, 1.0" AW'S Type DC, 0.5" or 1.0" IIW' 1. 0"
- SwAI Form QA 3-2
w SOUTHWEST R.ESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE Revision 23 December 1987 Page 4 of 22
- 2.5", 5 .0" SwRI Half-Round, 1.0" AWS Type DC 1.0" IIW 1.0" 10.0" IIW :> 4~ 0" (2) An~le-Beam Screen Block Distance Block Type Dimension 2.0", 2.5", SwRI Half-Round 1.0" Radius 5.0" AWS Type DC 1. 0 and 2
- 0 II II Romp us Radii 10.0" SwRI Half-Round 1. 0" Radius AWS Type DC 1.0" and 2.0" Rompus Radii IIW 4.0" Radius 20.0" IIW 4.0" Radius
- 5.3 Basic Calibration Block Side-drilled basic calibration hole reflectors, in accordance with Section V of the ASME Boiler and Pressure Vessel Code, shall be placed in a block manufactured from the same product form, and material specification and heat treatment as one of the materials being joined.
The basic calibration block thickness shall be determined by the average weld thickness of the piping to which the search unit is applied and Article 5, Section V. When a basic calibration block of the same thickness as t is not available and where t is 1 inch or less, the basic calibration block thickness shall be no more than 25% thinner than t or shall be closer to t than the 3/4-inch thick alternate calibration block allowed by Article 5. For calibration blocks for: dissimilar metal welds, the material selection shall be based on the material on the side of the weld from which the examination will be conducted. If the examination will be conducted from both sides, calibration reflectors shall be provided in both materials. Where two or more base material thicknesses are involved, the calibration block thickness shall be of a* size sufficient to contain the entire examination metal path. SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-31 Revision 23 December 1987 Page 5 of 22*
Where the component material is clad, the block shall be clad by the same welding procedure as the production part. Where the automatic method is impractical, deposition of clad shall be by the manual method. The surface finish of the basic calibration block shall be representative of the surface finish of the piping to be examined. Flat basic calibration blocks or blocks of essentially the same curvature as the part to be examined may be used when contact surface curvatures are greater than 20 inches in diameter. A curved basic calibration block shall be used to establish distance amplitude correction (DAC) curves for examinations on contact surfaces in the range of curvature from 0.9 to 1.5 times the basic calibration block diameter, when contact surface curvature is 20 inches in diameter or less. The curvature of the main run pipe shall be used to establish the,requirements for the basic calibration block curvature for the examination of branch connection welds . Approved drawings of basic calibration blocks to be used in accordance with this procedure are contained in the applicable SwRI Examination Plan. 5.4 Search Units Search units shall be selected from the following: (1) Straight-Beam Average i:.Teld Thickness Nominal Search Unit Size Greater than 0.4n to 2.0n l/4n Round i.on to 3.0n 3/8" Round 2.on to 4.0" l/2n Round 3.on to 5 .0" 3/4n to l" Round (a) The nominal straight-beam longitudinal-wave search unit frequency for austenitic piping shall be 1.5 MHz or 2.25 MHz, and 2.25 MHz for carbon steel .
- SwRI Form QA 3-2
SwRI.-NDT-600-31 SOUTHWEST RESEARCH INSTITUTE Revision 23 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 22 (2) Angle-Beam Average ~eld Thickness Maximum Nominal Search Unit Size Greater than 0.4" to 1/4" x 1/4", 1/4" Round less than 0.5" 0.5" to 2.0" 3/8" x 3/8", 3/8" Round
*0 . 7 5" to 4. 0" 1/2" x 1/2", 1/2" Round Greater than 2.0" to 5.0" 1/2" x l", 3/4" Round (a) The ~ominal angle-beam shear-wave search unit fre-quency for examination of austenitic piping shall be 2.25 MHz for 1/4 inch search units and 1.5 MHz for search units greater than.1/4 inch in size.
(b~ The nominal angle-beam shear-wave search unit fre-quency for the carbon steel side of dissimilar piping welds shall be 2.25 MHz. (c) Search unit wedges shall be fabricated to .prod~ce 45°
+/-2° refracted shear-wave ~hen examining circumferen-tial piping welds, or branch connections. A 60° +/-2° refracted shear-wave shall.be used only to augment the examination.
(d) For examination of longitudinal piping welds, search unit wedges shall be fabricated to produce 45° +/-2~ refracted shear waves. (e) The exit point of the sound beam and the actual refracted beam angle of shear-wave search units shall be determined on an IIY block or a Rompus block. The exit point shall be marked on the search unit wedge. (f) 1/4" x 1/4" or 1/4" round search units may be used for angle-beam calibrations when examining 4-inch diameter piping. 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1. SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-31 Revision 23 December*l987 Page 7 of 22 5.6 Couplant (1) USP-grade glycerine or reactor grade water shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure.
(2) USP-grade glycerine shall be certified for sulfur content and total halogens in accordance with SD-12~ and SD-808 of Article 24, Section V. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Reactor grade water, when used, shall be supplied by the customer. (3) Couplant materials used for examinations shall be the same as used for the calibration. 5.7 Thermometer The thermometer to be used for measuring the calibration block and component temperatures shall be calibrated and certified and shall display a valid calibration tag as required by NQAP 10-1.
- 6. CALIBRATION METHOD 6.1 Instrument Linearity Ultrasonic instrument linearity shall be verified prior to each period of extended use or every 3 months, whichever is less, in accordance with Paragraphs 6.1.1 and 6.1.2. Data required sh~ll be recorded on the SwRI Instrument Linearity Verification Record and the sheet number shall be referenced on each applicable SwRI Sonic Instrument Calibration Record.
NOTE The setting of the damping control shall be recorded in RE.i.'IARKS on the SwRI Instrument Linearity Verification Record. The damping control shall be in the same position during linearity verification, calibrations and examinations or a new linearity verification shall be performed. 6.1.1 Screen Hei~ht Linearity (1) Position a shear-wave search unit on a calibration block to obtain indications from the l/2T and 3/4T holes, or use a straight-beam search unit on any calibration block that provides amplitude differences .
- SwRI Form QA 3-2
SwRI-NDT-600-31 Revision 23 SOUTHWEST RESEARCH INSTITUTE December 1987 Page 8 of 22 NUCLEAR PROJECTS OPERATING PROCEDURE (2) Adjust the search unit position to give a 2:1 ratio between the two indications, with the larger indication set at 80% of full screen height (FSH) and the smaller indication at 40% of.FSH. (3) Yithout moving the search unit, set the larger indication to 100% of FSH; record the amplitude of the smaller indica-
. tion, estimated to the nearest 1% of FSH.
(4) S~ccessively set the larger indication from 100% to 20% of FSH in 10% increments (or 2 dB steps if a fine control is not available); observe and record the smaller indication estimated to the nearest 1% of FSH _at each setting. The reading must be 50% of the larger amplitude within 5% of FSH. 6.1.2 Amplitude Control Linearity (1) Position a shear-wave or straight-beam search unit on a calibration block to obtain maximum amplitude from an applicable reflector. The primary reference level sensitivity should be within the highest and lowest gain settings used during amplitude control linearity verifications. The highest and lowest gain settings used during the amplitude control linearity verifications shall be recorded in the Remarks column of the applicable SwRI Linearity Verification Records. (2) Yithout moving the search unit, set the indication to the required percent of FSH and increase or decrease the dB as specified below. The estimated signal shall be recorded to the nearest 1% of FSH and shall fall within the limits of the following table: Indication dB Control Indication Set at % of FSH Change* Limits. % of FSH 80% -6 dB 32 to 48% 80% -12 dB 16 to 24% 40% + 6 dB 64 to 96% 20% +12 dB 64 to 96%
*Minus denotes decrease in amplitude; plus denotes increase.
SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-31 Revision 23 December 1987 Page 9 of 22 6.2 Calibration The ultrasonic calibration shall be completed prior to the examination.
The REJECT control shall be maintained in the 0 position. The FREQ MHz control shall be turned to 1 when a 1.5-MHz search unit is used and to 2 with a 2.25-MHz search unit. The centerline of the search unit shall be at least 1-1/2 inches from the nearest side of the calibration block. Rotating the beam into the corner formed by the hole and the side of the block may produce a higher ampli-tude at a longer beam path. This beam path shall not be used for calibration. The type and length of the search unit cable shall be recorded on the SwRI Sonic Instrument Calibration Record, and all other information blocks on the form shall be filled in .
- The average weld thickriess' shall be used to determine the correct calibration block.and search units for examinations with geometric restrictions such as piping or components which may be thicker than the nominal pipe size, examinations limited to one side of the weld or wide weld crowns. The Level II or III examiner shall ensure that complete coverage of the examination volume is obtained. Additional calibration vee-path positions and larger screen sizes may be required to assure this coverage.
6.2.1 Temperature The calibration block temperature shall be within 25°F of the component temperature and shall be recorded ori the SwRI Sonic Instrument Cali-bration Record for the initial calibration and each verification. The surface temperature of the component to be examined shall be taken prior to and after performing each examination and shall be recorded on the applicable SwRI Exami-nation Record. 6.3 Calibration for Circumferential But~ Welds 6.3.l Straight-Beam Distance Calibration The screen distance chosen shall be the shortest applicable size to include at least l/4t beyond the thickest production material to which the search unit is applied. Observing back reflections from the applicable refer-ence block, set up the required linear sound path distance along the screen I baseline . SwRI Form QA 3*2
SwRI-NDT-600-31 Revision 23 SOUTHWEST RESEARCH INSTITUTE December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 10 of 22 Screen distance calibration shall be selected from the following sizes: l.on, 2.on, 2.5n, 5.0" and lo.on. 6.3.2 Angle-Beam Distance Calibration The screen distance chosen shall be the shortest applicable size to include at least 1/8 vee-path past the anticipated examination range. Observ-ing radius echoes from the applicable reference block, set up the required linear sound path distance along the screen baseline. Screen distance calibration for angle beam shall be selected from the following sizes: 2.0", 2.5n, 5.on, 10.on, arid 20.0". If a 60° shear-wave angle-beam is required to augment the exami-nation, and the same instrument is used for both 45° and 60° examinations, the screen distance calibration shall be conducted as follows: (1) The screen distance size shall be determined by the angle-beam _search unit requiring the longer examination (2) range. Position the 45° search unit on the appropriate reference block and record all required reference block entries on the appropriate SwRI Sonic Instrument Calibration Record. (3) Yithout changing the calibrated screen distance, repeat step (2) with the 60° search unit. (4) No attempt shall be made to compensate for the delay difference between 45° and 60° screen distance calibra-tions. This difference_ shall be considered when resolving indications. 6.3.3 Straight-Beam Distance Amplitude Correction A DAC curve shall be established by utilizing responses from the basic calibration holes. 6.3.3.1 Production Material 1 Inch or Less in Thickness (1) Position the straight-beam search* unit to obtain maximum response from the l/2T hole, and set this response to 80% +/-5% of FSH. (2) Draw a straight horizontal line on the instrument screen at
- this amplitude to extend a distance equal to the nominal thickness of the production material.
SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE
- wRI*NDT*bUU-31 Revision 23 December 1987
~;(D Page 11 of 22 NUCLEAR PROJECTS OPERATING PROCEDURE (3) Signal amplitudes for indications recorded shall be refer-enced as a percentage of this line.
6.3.3.2 Production Material Greater Than 1 Inch in Thickness (1) Position the straight-beam search unit to obtain maximum response from the calibration hole selected from the following, .that produces the highest amplitude: l/4T _ l/2T (if present) 3/4T (2) Set this response to the primary reference level of 80% +/-5% of FSH and mark its amplitude on the instrument screen.
- 6.3.4 (3) .W'ithout changing the gain controls, obtain maximum response from the remaining calibration holes; mark and join all amplitude points with a smooth curved line that shall extend l/4T beyond the: last qualified calibration point.
Angle-Beam Distance Amplitude Correction If a curved block is used, DAC curves for the examination of circumferential welds shall be constructed by utilizing the responses from the holes oriented.perpendicular to the axis of the basic calibration block. 6.3.4.1 Unclad Material (1) Position the 45° search unit to obtain maximum response from the calibration hole* and vee-path position selected from a minimum of three vee-path positions required to cover the entire examination area, the first of which must be situated prior to the lower l/3t volume and the last at the end or after the l/3t volume. (2) Set this response to the primary reference level of 80% +/-5% of FSH and mark its amplitude on the instrument screen. (3) Yithout changing the gain controls, obtain maximum response from the remaining required vee-path positions. Mark and join.all amplitude points with a smooth curved line that shali encompass the examination area not to extend more than 1/8 vee-path past the last qualified calibration node . SwRI Form QA 3-2
SwRI-NDT-600-31 SOUTHWEST RESEARCH INSTITUTE Revision 23 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 12 of 22* (4) If a 60° shear-wave angle-beam is required to 'augment the examination, repeat steps (1) through (3) using a 60° search unit. EXCEPTION If the configuration of the weld is such that the above calibration is not the most appropriate to provide coverage from two directions of the examination volume C-D-E-F as depicted in Figure l, then a calibration may be established which uses any vee-path position required to obtain complete coverage of the examination area*. Consideration shall be given to previous examination data to ensure that equivalent calibrations are.performed where practicable. 6.3.4.2
- Clad Piping (1) Position the 45° search unit to obtain maximum response from the calibration hole and the vee-path posit~on, selected from the following, that produces the highest amplitude:
l/4T Vee-Path Positions l/2T (if present) 3/4T 1/8 2/8 3/8 (2) Set this response to the primary reference level of 80% +/-5% of FSH and mark its amplitude on the instrument screen. (3) "Without changing the gain controls, obtain maximum response from the remaining vee-path positions; mark and join all amplitude points with a smooth curved line that shall extend 1/8 vee-path beyond the last qualified calibration point. (4) If a 60° shear-wave angle-beam is required to augment the examination, repeat steps (1) through (3) with* a 60° search unit. 6.4 Calibration for Branch Connection and Longitudinal Seam qelds 6.4.1 Straight-Beam Distance Calibration
.The strafght-beam distance calibration shall be the same as that described in Paragraph 6.3.1.
SwRI Form QA 3-2
- SwRI-NDT-6UO-:H Revision 23 SOUTHWEST RESEARCH INSTITUTE December 1987 Page 13 of 22 NUCLEAR PROJECTS OPERATING PROCEDURE 6.4.2 Angle-Beam Distance Calibration The screen distance chosen shall be the shortest applicable size to include at least 1/8 vee-path past the anticipated examination range.
Observing the radius echoes from the applicable refer~nce block, obtain the required linear sound path distance along the screen baseline. 6.4.3 Straight-Beam Distance Amplitude Correction The ~traight-beam distance amplitude correction shall be the same as that described in Paragraph 6.3.3. 6.4.4 Angle-Beam Distance Amplitude Correction r*f a curved block is utilized, DAC curves shall be constructed by utilizing the responses from the basic calibration holes oriented axially with the basic calibration block. 6.4.4.1 Unclad Mate.rial This calibration shall be the same as that described in ~aragraph 6.3.4.1, steps (1) through (3), using only the 45° search unit. 6.4.4.2 Clad Piping This calibration shall be the same as that described in Para-graph 6.3.4.2, steps (1) through (3), using only the 45° search unit. 6.5 Secondarv DAC Calibrations If any point on the DAC curve (within the examination volume) does not appear at 20% of FSH or greater, a secondary DAC curve shall be con-structed as follows: (1) All secondary DAC curves shall contain at least 2 points. (2) The DAC point at 20% of FSH or greater, adjacent to a DAC point that falls below 20% of FSH, shall be brought to the primary reference level and marked on the instrument screen. The other point(s), previously at less than 20% of FSH, shall be marked on the screen and all points connected with a smooth curved line. The gain setting for this secondary DAC curve shall be recorded on the appro-priate SwRI Sonic Instrument Calibration Record .
- SwRI Form QA 3-2
SwRI-NDT-600-31 SOUTHWEST RESEARCH INSTITUTE Revision 23 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 14 of :n EXCEPTIONS When the first DAC poinc is the only point above.20% of FSH, the next highest point shall be brought to the primary reference level and marked on _the instru-ment screen. The other points previously at) less than 20_% of FSH shall be marked on the screen and all points connected with a smooth curved line. 6.6 Calibration*verification 6.6.1 Sweep Range and DAC Curve Verification Sweep range calibration shall be verified on the appropriate reference block; and DAC curve calibration, if applicable, shall be verified on the appropriate basic calibration block: (1) Prior to a series of examinations (2) T.Jith any substitution of the same type or length of search unit cable (3) (4) (5) Yith any substitution of power utilizing the same type source; e.g., a change of batteries At least every 4 hours during the examination At the completion of a series of examinations (6) Whenever the validity of the calibration is in doubt 6.6.2 Verification of Calibration Reflectors at Scanning Soeed The examiner shall verify the presence of the calibration reflec-tor at scanning speed. It is not necessary to assure that this check confirms the signal amplitude at 100% o~ reference level, but merely to demonstrate that the signal from the calibration reflectors are readily observable at scanning speed. The following statement shall be documented on the SwRI Sonic Instrument Calibration Record and initialed:
"Calibration reflectors have been verified at scanning speed." ,,
SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE w
Revision 23 December 1987 Page 15 of 22
.L 6.6.3 Calibration Changes (1) Perform the follOwing if any point on the DAC curve has decreased more than 20% of FSH or 2 dB in amplitude, or any point on the sweep line has moved raore than 10% of the sweep division reading or 5% of full sweep whichever is greater:
(a) Void all examinations referring to the calibration in quest~on and perf-0rmed after the last valid calibra-tion verification. (b) Conduct a new calibration. (c) Reexamine the areas for which examinations have been voided. (2) Perform the following if any point on the DAC curve has increased in amplitude more than 20% of FSH or 2 .dB: (a) Correct the calibration. (b) Reexamine all indications recorded since the last valid calibration verification. (c) Enter proper values on a new SwRI Examination Record. 6.6.4 Recalibration Substitution of any of. the following shall be cause for recali-bration: (1) Search unit transducer or wedge (2) Search unit cable type or length (3) Ultrasonic instrument (4) Examination personnel (5) Couplant (6) Change in type of power source; e.g., a change from direct to alternating current SwRI Form QA 3-2
SwRI-NDT-Revision 23 SOUTHWEST RESEARCH INSTITUTE December 1987 Page 16 of 22 NUCLEAR PROJECTS OPERATING PROCEDURE
.7. EXAMINATION 7.1 Examination Volume 7 .1.1 Circumferential and Longitudinal Butt Welds in Piping Scanning of the weld and base material shall be adequate to ensure complete two-directional coverage for l/3t from the inside surface of the pipe as shown in Figure 1. The base material shall be examined for a distance of 1/4 inch as measured from the outside surface fusion line on each side of the weld.
Class 1 longitudinal welds shall be examined along the entire length of the weld during the preservice exainination and for at least one pipe-diameter length .or 12 inches, whichever is less, from the fusion line of the intersecting circumferential weld during inservice examinations. Class 2 longitudinal welds shall be examined for at least 2-l/2t length from the fusion line of the intersecting circumferential weld during preservice and inservice examinations. 7 .1.2 Butt Welds of Branch Connections Scanning of the weld and base material shall be adequate to ensure complete coverage for l/3t from the inside surface of the pipe as shown in Figure 2. The base material shall be examined for a distance of 1/4 inch measured from the outside surface fusion line on the main run pipe side of the weld. 7.2 Surface Condition The contact surfaces shall be free from weld spatter, roughness, or other conditions which interfere with free movement of the search unit or impair the transmission of ultrasound. 7.3 Indication Length Zero Reference (Lo) Location Areas to be examined in accordance with this procedure shall have an Lo marked in accordance with the applicable revision of SwRI Procedure IX-FE-103. 7.4 Scanning When practicable, scanning shall be performed at a minimum gain
.setting of 2 times the reference level sensitivity.
SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-Revision 23 December 1987 Page 17 of 22 Instrument gain setting for scanning shall be determined on the basic calibration block as follows for each primary reference level utilized:
(1) ~ith the instrument at the primary reference level, manipu-late the search unit on the basic calibration block to obtain a signal of 40% of FSH from a calibration reflector (side-drilled hole). (2) Add 6 dB gain by utilizing the 6 dB switch (if present), the.fine gain control, or a combination of the fine and coarse gain controls and choose any method that yields a signal response within +/-2 dB of 80% FSH. (3) This amplitude and method shall pe recorded on the SwRI Sonic Instrument Calibration Record and shall be used during the valid calibration period for all scanning at 2 times the reference level sensitivity. Scanning overlap shall be a mini~um of 25% of the search unit piezoelectric element dimension perpendicular to the direction of the scan. The search unit movement rate shall not exceed 3 inches per second. 'tJhile scanning, the search unit shall be oscillated approximately +/-20°. 7.5 Thickness Measurements and Lamination Scan Screen distance calibration for these examinations shall be conducted in accordance with Paragraph 6. 3 .*l:. 7.5.l Thickness Measurements Thickness measurements shall be taken at a minimum of three points adjacent to Lo for longitudinal and circumferential welds (on the center-line of the weld and at one point in the base material on each side of the weld). Thickness measurements shall be taken at a minimum of two points adja-cent to Lo for branch connection welds (one on the base material of the main run pipe, and one on the base material of the branch connection). If these measurements cannot be taken adjacent to Lo, the location of the measurements shall be recorded on the appropriate SwRI Examination Record. 7.5.2 Base Material Lamination Scan A lamination*scan using longitudinal-wave shall be performed. This scan shall cover as much as practical of the area through which the
- angle-beam passes. The lamination scan shall be conducted as follows:
SwRI Form QA 3*2
SwRI-NDT-600-31 SOUTHWEST RES EAR-CH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE Revision 23 December 1987 Page 18 of 22 * (1) Scanning shall be performed at a gain setting that gives an initial backwall amplitude of 80% +/-5% FSH. E.."'CCEPT! ON If performed previously, a lamination scan is not required except in the area(s) where a lamination was previously recorded.
* (2) To record an inte_rmediate indication, obtain a backwall reflection signal from an indication-free area and adjust this signal to 80% +/-5% of FSH. Record the intermediate.
indication when its amplitude is equal to the remaining backwall reflection. Areas 1 of total loss of backwall reflection accompanying the intermediate echo shall also be recorded. 7.6 Examination of Circumferential and Longitudinal Butt Welds in Piping 7.6.1 Angle-Beam Examination for Indications Parallel with the Weld Angle-beam examinations for circumferential welds shall be accomplished using the required refracted shear-wave from both sides of the weld. For this examination, the sound-beam shall be directed perpendicularly into the weld to detect indications parallel with the weld. Calibration for these examinations shall be in accordance with Paragraphs 6.3.2 and 6.3.4. Angle-beam examinations for longitudinal welds shall be accom-plished using the required refracted shear-wave from both sides of the weld. For this examination, the .sound-beam shall be directed perpendicularly into the weld to detect indications parallel with the weld. Calibration for this exami-nation shall be in accordance with Paragraphs 6.4.2 and 6.4.4. 7.6.2 Alternate Examination A shear-wave angle-beam examination shall be conducted as . required to assure complete coverage from both sides of the circumferential or longitudinal weld. Any areas of the weld not receiving complete coverage from both sides shall be examined from one side of the weld with the required shear-wave(s) and a straight-beam longitudinal-wave applied to the surface of the weld crown in the affected areas. Calibration for the longitudinal-wave search unit shall be in accordance with Paragraphs 6.3.1 and 6.3.3. SwAI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE w
Revision 23 December 1987 Page 19 of 22
- 7.6.3 Angle-Beam Examination for Indications Perpendicular to the Weld Calibration for these examinations shall be in accordance with Paragraphs 6.3.2 and 6.3.4 for circumferential welds, and Paragraphs 6.4.2 and
- 6. 4. 4 for longitudinal *and branch connection we*lds.,
A shear-wave angle-beam examination shall be conducted on each weld by placing the search unit on the weld and lt base metal adjacent to each weld with the sound beam directed into and parallel with the weld to detect indications perpendicular to the weld. The entire length of the weld and base material within lt of the weld shall be scanned with the.search unit beam directed in this manner from two opposing directions. The search unit shall then be placed on the base metal with the search unit sound beam directed tangentially into the weld at a 45°. +/-10° angle. The entire length of the weld and adjacent base material shall be scanned with-the search unit beam directed in this manner on each accessible side of the weld from two opposing directions. Geometric root ripple echoes occurring at the same metal path distance as flaws adjacent to the weld root are to be expected. A flaw must be distinguished from root ripple by its greater echo amplitude compared-to the amplitude of the root ripple at the same location. A flaw indication adjacent to the weld root tends to mask out several facets of the root ripple and travels along the baseline through the root ripple package. 7.7 Examination of Butt Welds of Branch Connections 7.7.1 Angle-Beam Examination for Indications Parallel with the Weld A shear-wave angle-beam examination shall be accomplished from the main run pipe side of the weld. For this examination, the sound beam shall be directed perpendicularly into the weld to detect indications parallel with the weld. Calibration for these examinations shall be in accordance with Paragraphs 6.4.2 and 6.4.4. 7.7.2 Angle-Beam Examination for Indications Perpendicular to the Weld The angle-beam examination for indications perpendicular to the weld shall be the same as the examination described in Paragraph 7.6.3. 7.8 Postexamination Cleaning Arrangements shall be made with the customer for postexamination removal of couplant materials .
- SwAI Form QA 3*2
_ __J
SwRI-NDT-600-31 Revision 23 SOUTHWEST RESEARCH INSTITUTE December 1987 Page 20 of 22 NUCLEAR PROJECTS OPERATING PROCEDURE
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-117.
All ultrasonic reflectors, regardless. of signal amplitude, not attributable to geometry shall be recorded and investigated by a Level II or a Level III examiner to determine the shape, identity, and location of the reflector. Examples of nongeometric reflectors are those which are slightly removed from the weld root and/or chamfer, mask the root indications, are transverse to the weld, or have linear dimensions with side branches. Ultrasonic reflectors attributable to geometry and producing a response greater than 50% of the reference level shall be recorded on the appropriate SwRI Ultrasonic Examination Record and investigated. Recordable indications attributable to geometry shall be recorded only once, even if the amplitude of the indication drops below the required recording amplitude along the weld. These indications shall be investigated by a Level II or a* Level III examiner to determine the shape, identity, and location of the reflector. If indications that have been recorded as geometry have been investigated and found to be nongeometric reflectors, the entire weld shall be reexamined and all nongeometric reflectors and other reflectors not previously recorded at least once shall be recorded. Indications investigated and found to be other than geometrical in nature, regardless of the amplitude, shall be reported to the customer for evaluation. Scanning limitations shall be recorded.
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI personnel, and shall be ~onducted in accordance with the applicable ASME Boiler and Pressure Vessel Code, Section XI, Article IYA-3000. Final evaluation and disposition of reportable indications shall be the responsibility of the cus-tomer.
- 10. RECORDS Documents generated in accordance with this procedure shall be stored as specified in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan.
0 SwAI Form QA 3*2
- 'SOUTHWEST RESEARCH INSTITUTE*
NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-31 Revision 23 December 1987 Page 21 of 22 Profile of valw tlOdV. vessel nozzle, or (
- pump connect1on
~
I
- F 1/4in;i 1/4 in.
+
, i:lt
)
i I_ E.xam . ..al. i-c-o-e-Fj Figure 1 W'ELDS IN PIPING (Volumetric Examination Requirements)
- SwRI Form QA :3-2
w SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE Revision 23 December 1987 Page 22 of 22
- r Figure 2 Examinacion Area A-B-C-0 (Lower l/3t of che Yeld and 1/4 Inch t -
- Base Ma.cerial on Each Side of che Yeld)
~----------*- ____:=_
---- --JJ*
y !i . i. r*~ *L~Jd jHi I c==-----. H-- J I I
--r
.__.. . . _ __,,..---___ _J
'------l h
! ~
1 11 BRANC:i CONNECTION w~I.DS
. (Volumecric Examinacicn Requiremencs) i' r---*-*--;
SwRI Form QA 3-2
- t I
f-
~
- PROCEDURE DEVIATION Page 1 of 1 Pages Procedure SwRl-NDT-IRevision No. I Deviation No.
- 1 i;nn- 11 11 The following examination areas are affected. by this deviation:
Examinations performed in accordance with this procedure. The following paragraphs shall be deviated from as indicated: :> Add to Paragraph 6.6: Note Verifieation of Calibration Reflectors at Scanning Speed and Notch Comparison The examiner shall verify the presence of the calibration reflector at scanning speed. It iS not necessary to assure that this check confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the signals from the calibration reflectors are readily observable at scanning speed. I The following statement shall be documented on the SwRI Sonic Instrument Calibration Record arid initialed:
"Calibration reflectors have been verified at scanning speed."
II II Rationale for deviation: This deviation incorporates customer request. If the deviation is determined to affect the procedure Deviation Affects Qualification YES D NO ~ qualification, the deviation shall be qualified in accordance with Procedure IX-FE-107. APPROVALS SA fLJ) Written by: Date: lL-. _ ~ Technical Revie\111: )J/, {J,J,;'/}d 711" Date:
~ /} } 3'-31-J'S 4
- c 3-JI 1-S'
*-%.LU':<~ Verbal-Approva~ Given?
-* u ' I. Date:
- l. DYes fl No
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SwRI-NDT-600-33
~ SOUTHWEST RESEARCH INSTITUTE Revision 11 NUCLEAR PROJECTS March 1988 OPERATING PROCEDURE Page 1 of la Title
' MANUAL ULTRASONIC EXAMINATION OF PRESSURE VESSEL WELDS GREATER THAN 0.4 TO 2.0 INCHES IN THICKNESS EFFECTIVITY AND APPROVAL Revision 11 of this procedure became effective on Aor. 5 2 1988. Other revisions of the base docum~nt may be effective concurrently.
Approvals srlD v\l17itten Sy *""\ / Date Technical Review Date I
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- Manag'er of Q.A.
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/kil ~Phtl #.WvU The following information may be used for convenience. Completion of this portion is not mandatory.
Date lf/S-/<t~ Deviation No. Date Effective I I Procedure Section(s) Affected Notes:
- SwRI Form QA*40A*IJ
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SOUTHWEST RESEARCH INSTITUTE rsJ~- 1~!~ I
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- NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 2 of 18
. MANUAL ULTRASONIC EXAMINATION OF PRESSURE VESSEL WELDS GREATER THAN 0.4 TO 2.0 INCHES IN THICKNESS SwRI-NDT-600-33
- 1. PURPOSE This procedure provides the technical information and the detailed steps necessary to ensure a proper manual ultrasonic examination of vessels in accor-dance with the applicable ASME Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION Longitudinal, circumferential, and nozzle-to-shell welds in wrought fer-ritic and austenitic vessels in the thickness range from 0.4 to 2.0 inches shall be examined with this procedure. Welds to be examined shall be as speci-fied in the applicable SwRI Examination Plan. Welds examined with this pro-cedure may be cladded or uncladded.
Shear-wave angle-beam, manual, contact, pulse-echo ultr~sonic techniques shall be utilized for these examinations.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1980 Edition with Addenda through W.inter 1981 and 1983 EditiGn with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V 1980 Edition with Addenda through Winter 1981 and 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Calibration and Examination Records SwRI-NDTR Form No. Re~rision Date 17-19 12-01-83 17-89 08-19-80 17-90 08-19-80
- 4. RESPONSIBILITY
( 1) The Director of the Department of NDE Services, Nondestructive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure. SwAI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 3 of 18 (2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan.
(3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Support and Administration Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations in accordance with this proce-dure shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control."
5.2 Reference Block Reference blocks used for screen distance calibration and verifi-cation shall be of the same basic material as the production material; i.e., s~ainless steel or carbon steel, and shall be one of the following: (1) SwRI Half-Round, (2) AWS-Type DC, (3) IIW, or (4) ROMPAS. 5.2.1 Reference Block Selection -I Reference block types shall be used as follows for screen dis- i tance calibration: Angle-Beam Screen Block Distance Block Tvne Dimension
- 1. 0", 2.0", SwRI Half-Round 1.0" Radius
- 2. 5", 5. 0" AWS Type DC or ROMPAS 1.0" and 2.0" Radii 10.0" SwRI Half-Round 1.0" Radius AWS Type DC or ROMPAS 1.0" and 2.0" Radii 4.0" Radius IIW SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 4 of 18 5.3 Basic Calibration Block 5 .: 3 .1 Calibration reflectors shall be holes drilled parallel to the examination surface of the calibration block in accordance with Article 5, Section V, Figure T-546.l of the ASME Gode. Approved drawings of basic calibra-tion blocks are contained in the applicable SwRI Examination Plan. 5.3.2 The material for the basic calibration block shall be manufac-tured from one of the following: (1) the ~omponent nozzle dropout; (2) the component prolongation; or (3) material of the same specification, product form, and.heat treatment as one of the materials being joined. 5.3.3 The basic calibration block thickness shall be determined by the nominal production material thickness (t) to be examined. When a basic calibration block of the same thicknes.s as t is not available and where t is 1 inch or less, the calibration block thickness shall be no more than 25% thinner than t or closer to t than the 3/4-inch thick alternate calibration block allowed by Article 5. 5.3.4 A flat basic calibration block or block of essentially the same curvature as the part to be examined may be used for the examination of welds with contact surface curvatures greater than 20 inches in diameter. 5.3.5 A single curved basic calibration block may be used to establish distance amplitude correction (DAC) curves for* examinations on contact surfaces in the range of curvature from 0.9 to 1.5 times the basic calibration block diameter, when contact surface curvature is 20 inches in diameter or less. The finish on the surface of the block shall be representative of the surface finish of the component. 5.3.6 li1here the component ~s clad, the block shall be clad by the same welding procedure as the component. When the automatic method is impractical, deposition of clad shall be by the manual method. 5.4 Search Units Search units shall be selected from the following: Weld Thickness Nominal Search Unit Size 1.0" or less 1/4" x 1/4", 1/4" Round 0.40" to 2. 0" 3/8" x 3/8", 3/8" Round 0.75" to 2.0" 1/2" x 1/2", 1/2" Round SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 5 of 18 Search unit wedges shall be fabricated as required to produce 45° +/-2~ or 60° +/-2° refracted shear-waves.
The exit point of the sound beam and the actual refracted beam angle of shear-wave search units shall be determined on an IIW, or ROMPAS reference block. The exit point shall be marked on the search unit wedge. The nominal shear-wave search unit frequency for examination of austenitic welds shall be 1.5 MHz, except when 1/4-inch search units are used. The nominal frequency for 1/4-inch search units shall be 2.25 MHz. The nominal shear-wave frequency for the examination of ferritic vessel welds shall be 2.25 MHz. 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1 . 5.6 Couplant (1) USP-grade glycerine or reactor grade water shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure. (2) All couplant materials, except reactor grade water, shall be certified for sulfur content and total halogens. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Reactor grade water, when used,
~hall be supplied by* the customer.
(3) Couplant materials used for exami~ations shall be the same as used for the calibration. 5.7 Thermometer The thermometer to be used for measuring the calibration block and component temperatures shall be calibrated and certified*and shall display a valid calibration tag as required by NQAP 10-1.
- 6. CALIBRATION METHOD 6.1 Calibration
- examination.
SwAI Form QA 3-2 The ultrasonic calibration shall be completed prior to the
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 6 of 18 The type and length of the search unit cable shall be recorded on the SwRI Sonic Instr'ument Calibration Record and all information blocks on this form shall be filled in. The centerline of the search unit shall be at least 1-1/2 inches from the nearest side of the calibration block. Rotating the beam into the corner formed by the hole and the side of the block may produce a higher ampli-tude at a longer beam path. This beam path shall not be used for calibration. The REJECT control shall be maintained in the 0 position during calibration and examination. The FREQ MHZ control shall be turned to 2 when a 2.25-MHz search unit is used, and to 1 with a 1.5-MHz search unit. 6 .1.1 Temnerature The calibration block temperature shall* be within 25°F of the component temperature and shall be recorded on the SwRI Sonic Instrument Cali-bration Record for the initial calibration and each verification. !:le surface temperature of the component to be examined shall be taken prior to and after performing each examination and shall be recorded on the applicable SwRI Exami-nation Record. 6.2 Calibration for Circumferential. Longitudinal. and Class 1 Nozzle-to-Shell Welds 6.2.1 Screen Distance Calibration Observing radius echoes from the applicable reference block, obtain the required linear sound path distance along the screen baseline; which shall be the shortest app.licable* size to incl1.1de at least 1/8 vee-path past the anticipated examination range. Screen distance shall be selected from the following sizes: 1.0", 2.0 II ' 2.5 II ' 5.0 II ' and 10 . 0 II I When the same* instrument is used for both 45° and 60° examina-tions, the screen distance calibration shall be conducted as follows: (1) The screen distance size shall be determined by the angle-beam search unit requiring the longer examination range. (2) Position the 45° search unit on. the appropriate reference block. Observe and record all verification block entries as required on the appropriate SwRI Sonic Instrument Calibration Record. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 7 of 18 (3) Position the 60° search unit on the appropriate reference block. Without changing the calibrated screen distance, observe and record all required verification block entries.
(4) Do not compensate for any delay difference observed bet*,.;een the 45° and 60° screen distance calibrations. This dif-ference shall be considered when resolving indications. 6.2.2 Distance Amplitude Correction If a curved block is used, DAG curves for the examination of circumferential welds shall be constructed by utilizing responses from the. holes orie.nted perpendicular to the axis of the basic calibration block. If complete coverage is not obtained with 45° angle beam, then a 60° shear wave shall be used to 'obtain additional coverage. 6.2.2.1 Material Less Than 1 Inch in Thickness (45° and 60° DAG Cu~es) (1) Position the 45° search unit to obtain maximum response from the ~ee-path position selected from the following, that produces the highest amplitude: Vee-Path Positions l/2T 2/8,* 6/8, 10/8 (2) Set this response to 80% +/-5% of FSH and mark its amplitude on the screen. The gain controls shall not be adjusted once this primary reference response has been established. (3) Obtain maximum response form the remaining vee-path posi-tions; mark and join all amplitude points with a smooth curved line which shall extend 1/8 vee-path past.the last qualified calibration point. (4) Repeat steps (1) through (3) using a 60° search unit, i::: required. 6.2.2.2 Material 1 Inch and Greater in Thickness (45° and 60° DAC Curves) (1) Position the 45° search unit to obtain maximum response from the vee-path position selected from the following, that produces the highest amplitude:
- SwRI Form QA 3-2
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SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600~33 Revision 11 March 1988 Page 8 of 18 45° Vee-Path Positions l/4t 1/8, 7/8 l/2t 2/8, 4/8 3/4t 3/8, 5/8 (2) Set this signal to 80% +/-5% of FSH and mark its amplitude on the screen. The gain controls shall not be adjusted once this primary reference response has been established. (3) Obtain maximum response from the remaining vee-path posi-, tions; mark and join all amplitude points w~th a smooth curved line, which shall extend 1/8 vee-path past the last qualified calibration point. (4)
- Repeat steps (1) through (3) using a 60° search unit utilizing the following vee-path positions:
'Holes 60° Vee-Path Positions l/4T 1/8, 7/8 l/2T 2/8, 6/8 3/4T 3/8, 5/8 6.3 Distance A..mplitude Correction for Class 2 Nozzle-to-She'll Welds If a curved block is used, DAC curves for the examination of nozzle-to-shell welds shall be constructed by utilizing responses from the holes oriented perpendicular to the axis of the basic calibration block.
(1) Position a 45° search unit or a 60° search unit, as required, to obtain maximum response from the calibration hole and vee-path position selected from a minimum of three vee-path positions required to cover the entire examination area, the first of which must be situated prior to the lower l/3t volume and the last at the end or after the l/3t volume. (2) Set this response to 80% +/-5% of FSH and mark its amplitude 0 on the instrument screen. This is the primary reference level. (3) Without changing the gain controls, obtain maximum response from the remaining required vee-path positions. Mark and join all amplitude points with a smooth curved line that shall encompass the examination area not to extend more SwRI Form QA 3-2.
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 9 of 18 than 1/8 vee-path past the last qualified calibration
. point.
6.4 Secondary DAG Calibration~ If all points on the DAC curve do not appear at 20% of FSH or greater, a secondary DAC curve that contains at least two points shall be constructed as follows: (1) The DAC point at 20% of FSH or greater and adjacent to a DAC point that falls below 20% of FSH shall be brought to the primary reference level and marked on the instrument screen. (2) The other point(s), previously at less than 20% of FSH, shall be marked on the' screen and all points connected with a smooth curved line. The instrument gain setting for this secondary DAC curve shall be recorded on the appropriate SwRI Sonic Instrument Calibration Record . EXCEPTIONS When the first DAC point is the only point above 20% of FSH, the next highest point shall be brought to the primary reference level and marked on the instrument screen. The other points previously at less than 20% of FSH shall be marked and all points connected with a smooth curved line. When the 60°* calibration consists of a 2/8, 6/8, 10/8 vee-path and no indica-tions are to be recorded past the 6/8 vee-path, it shall not be necessary to construct a secondary DAC. 6.5 Calibration Verification 6.5.1 Sweep Ranae and Distance-Amplitude Calibration Verification Sweep range and distance amplitude calibrations shall be verified on the appropriate reference and basic calibration block when any of the follow-ing occurs: (1) Prior to a series of examinations (2) With any substitution of the same type and length of search unit cable (3) With any substitution utilizing the same t~e of power source; e.g., a change of batteries (4) At least every 4 hours during the examination SwAI Form QA 3-4
SOUTHWEST RESEARCH INST'ITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988
*Page 10 of 18 (5) At the completion of a series of examinations (6) Whenever the validity of the calibration is in doubt 6.5.2 Calibration Changes (1) Perform the following if any point on the DAG curve has decreased 20% or 2 dB or more in amplitude, or if any point on the DAG has moved on the sweep line more than 10%
of the screen reading or 5% of full screen, whichever is greater: (a) Void all examinations referring to the calibration in question and performed after the last valid calibra-tion verification. (b) Conduct a new calibration. (c) Reexa.'lline. the areas fo'r which examinations have been voided. (2) Perform the following if any point on the DAG curve has increased in amplitude more than 20% or 2 dB: (a) Correct the calibration. (b) Reexamine all indications recorded since the last valid calibration verification. (c) Enter proper values on a new SwRI Examination Record. 6.5.3 Recalibration Substitution of any of the following shall be cause for recali-bration. (1) Search unit wedge or transducer (2) Search unit cable type or length (3) Ultrasonic instrument (4) Examination personnel (5) Couplant SwRI Form QA 3-2 (6) Change in type of power source; e.g., a change from direct to alternating current
- SOUTHWEST RESEARCH INST-ITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March,1988 Page 11 of 18
- 7. E.XAMINATION 7.1 Examination Volume 7.1.1 A detailed scale drawing should be obtained to determine the exact weld configuration for circumferential and meridional welds in spherical Glass 1 vessel heads. In cases where the weld crown is on the insida surface and the examination *is to be performed from the outside surface, the examiner shall determine the i/2t examination area based upon the l/2t distance on the inside surface.
7.1.2 In Glass 1 vessels, the examination volume shall be the weld and adjacent base ma~erial for a distance of l/2t from the fusion line on each side of the weld for longitudinal, circumferential butt, and tube sheet-to-head welds, and the weld and l/2t of base material on each side of the weld for nozzle-to-vessel butt welds as shown in Figures 1, 2, and 3. In cases where the weld crown is on the_ inside surface, the l/2t distance shall be based upon l/2t from the fusion line of the weld crown . 7.1.3 In Glass 2 vessels, the examination volume shall be the weld and adjacent base material for a distance of 1/2 inch from the fusion line on each side of the weld for circumferential butt and tube sheet-to-head welds as shown in Figures 1 and 2. The examination area*for nozzle-to-vessel welds shall be the weld and base material for l/3t from the inside surface of the vessel including 1/4 inch of base material on each side of the weld as shown in Figure 4. In cases where the weld crown is on the inside surface, the 1/4-inch distance shall be based upon 1/4 inch from the fusion line of the weld crown. 7.2 Surface Condition The contact surfaces shall be free from weld spatter, roughness, or other conditions which interfere with free movement of the search unit or impair transmission of ultrasound. 7.3 I~dication Length Zero Reference (L0 ) Location Areas to be examined in accordance with this procedure shall have an L0 marked in accordance with the applicable revision of SwRI Procedure IX-FE-103. 7.4 Scannin~ When practicable, scanning shall be performed at a minimum gain setting of 2 times the reference level* sensitivity. If 2 times the. reference level is not possible, the limitation shall be recorded. SwAI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE
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. I "~ :-02~t1 NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 12 of 18 Instrument gain setting for scanning shall be determined on the basic calibration block as follows for each primary reference level utilized:
(1) With the instrument at the primary reference level, manip-ulate the search unit on the basic.calibration block to obtain a signal of 40% of FSH from a calibration reflector (side-drilled hole). (2) Add 6 dB gain by utilizing the 6 dB switch (if present), the fine gain control or a combination of the fine and coarse gain controls and choose any method which yields a signal response within +/-2 dB of 80% FSH. (3) This amplitude and method shall be recorded on the SwRI Sonic Instrument Calibration Record and shall be used during the valid calibration period for all scanning at 2 times the reference level sensitivity. Scanning overlap shall be a minimum of 10% of the search unit piezoelectric element dimension perpendicular to the direction of the scan. The search unit mo,1ement rate shall not exceed 6 inches per second. 7.5 Examinations 7.5.l Examination for Indications Parallel with the weld Examinations shall be accomplished using the appropriate angle(s)
*of refracted shear-waves from both sides of the weld. For this examination, the sound-beam shall be directed perpendicularly into the weld to detect indications which are parallel with the weld. ,
7.5.2 Examination for Indications Perpendicular to the Weld Examination shall be conducted by placing the search unit on the weld and the base material with the sound beam directed into and parallel with the weld to detect indications perpendicular to the weld. The entire length of the weld and the required base material shall be scanned with the search unit sound beam directed in this manner from two opposing directions. 7.6 Postexamination Cleaning Arrangements shall be made with the customer for postexamination removal of couplant materials. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 13 of 18
- 8. RECORDING CRITERIA 8.1 Ind"ications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-117.
8.2 Ultrasonic reflectors producing a response equal to or greater than 50% of the reference level shall be recorded. 8.3 Ultrasonic reflectors producing a response equal to or greater than 100% of the reference level shall be investigated by a Level II or Level III examiner to determine the shape, identity and location of all such reflectors in terms of the Flaw-Indication Characterization Rules and acceptance standards of IWA-3000. 8.4. The size of reflectors shall be measured between points that give amplitudes equal to 100% of the reference level (See Table 1). 8.5 Recordable indications attributable to geometry shall be recorded
- only once, even if the amplitude of the indication drops below the required recording amplitude along the weld. Geometric indications need not be charac-terized or compared with the acceptance standards of IWA-3000.
8.6 If indications that have been recorded as geometry have been investigated and found to be nongeometric reflectors, the entire weld shall be reexamined and all nongeometric reflectors and other reflectors not previously recorded at least once shall be recorded. 8.7 When examining tube sheet-to-shell welds from the tube sheet side, indications appearing beyond the 4/8 vee-path shall not be recorded. 8.8 Indications investigated and found to be other than geometric in nature shall be reported to the customer for evaluation. 8.9 Scanning limitations shall be recorded.
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI personnel. Final evaluation and disposition of reportable indications shall be the responsibility of the customer.
- 10. RECORDS Documents generated in accordance ~ith this procedure shall be stored as specified in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan.
SwRI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-!)00-33 Revision 11 March 1988 Page 14 of 18 Table 1 Data required when the reflector amplitude is equal to or greater than 50% DAG: W MAX L Search Unit Search Unit DAG WIMP MAX Location Angle Data required when the reflector amplitude is equal to or greater than 100% DAG:
% 100% DAG W MAX 100 M L1 L L2 s.u s.u DAG I W1 I M WjMP W2 MP 100% DAG MAX 1100% DAG Location Angle SwRI Form QA 3-2
- S*OUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision.11 March 1988 Page 15 of 18 1-- .. --f I I 112 in. I A '
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- Figure 1. Circumferential and Longitudinal Welds SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 16 of 18
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- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 17 of 18
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SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-33 Revision 11 March 1988 Page 18 of 18
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600-39 PROCEDURE DEVIATION The following examination areas are affected by this deviation: I Revision No. 9 I Page 1 of 3 D~viation No. 1 Pages Manual ultrasonic examination of small diameter socket welds at Salem Units 1 and 2. The following paragraphs shall be deviated from as indicated: Change the second paragraph of 5.2 as follows: The actual refracted beam angle of 45° .+/- 2° shear-wave search units shall be determined on an SwRI pipe reference block (PRB). The curvature of the PRB shall conform to the nominal curvature of the examination area; i.e., a 1.5" nominal diameter pipe shall require a 1.5" diameter PRB to be utilized. The actual refracted beam angle of 70° .+/- 2° search units shall be determined on the basic calibration block.
- Change paragraph 5.4(2) (a) and (b) as follows:
- (a)
(b) The nominal angle-beam shear-wave search unit frequency shall be 5.0 MHz. The search unit wedges shall be fabricated as required to produce a 45o .+/- 2° and 70° .+/- 2° refracted shear waves. The contact surface of the wedges shall conform to the surface of the pipe for the examination being conducted. Rationale for deviation: This deviation incorporates 70° angle beam requirements for e.'talnination of small diameter piping socket welds, and complies with the NRC's request to verify the presence of the calibration reflectors under procedural scanning conditions. Deviation Affects If the deviation is determined :o affect the procecure I Qualification YES ~ NO D qualif1calion. the deviation shall be quaiified in accorcance with Procedure IX-FE-107.
'APPROVALS SA f UJ Written by: Date:
db/!. tk~7/J1/ Id ( Verbal Approval Given? 0Yes ~No Da~/A Date: Cognizant Director: Date:
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SwAI FOAM FE-4-6
Procedure Deviation SwRI Procedure 600-39 Revision No. 9 Deviation No. 1 Page2 of3 The following paragraphs shall be deviated from as indicated: (Cont) Change the first sentence of 6.5 Angle Determination as follows: The actual refracted beam: angle of 4;3° .+/-. 2° search units shall be determined on the PRB as follows: Add the following to 6.5: The actual refracted beam angle of 70° .+/-. 2° search units shall be determined on the basic calibration blocks as follows: * (5) Peak the signal from the inside surface notch perpendicular to the basic calibration axis (circumferential notch). * (6) Measure the skip distance from the notch to the scribed exit point of the wedge. (7) The measured skip distance shall be between 2.5 to 3.1 times the actual basic calibration block thickness. Change 6. 7 (1) as follows: 45o .+/-. 2° vee-path Positions 700 .+/-. 2° vee-path Positions 4/8, 8/8, 12/8 4/8,8/8 Add the following NOTE to paragraph 6.8. A secondary DAC curve need not be constructed with the 10° .+/-. 20 search unit. Add paragraph 6.9.2.1 to read as follows: 6.9.2.1 Verification of Calibration Reflectors at Scanning Speeds The examiner shall verify the presence of the calibration reflector at scanning speed. It is not necessary to assure that this check confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the signal from the calibration reflectors are readily observable at scanning speed. The following statement shall be documented on the SwRI Calibration Record Sheet and initialed: "Calibration reflectors have been verified at scanning speed."
- Procedure Deviation SwRI Procedure 600-39 Revision No. 9 Deviation No. 1 Page 3 of3 The following paragraphs shall be deviated from as indicated: (Cont)
Change the title of 7. 7 as follows:
- 7. 7 Circumferential Welds Change 7.7.1 as follows:
7.7.1 Thickness Measurements Thickness measurements shall be ta.ken at a minimum of two points (in the base material on each side of the weld). Screen dist.a.nee calibration for this examinatjon shall be in accordance with Paragraph 6.4. Measurements shall be ta.ken by placing the straight-beam search unit on the examination surface and recording the position of the back wall reflection observed on the instrument screen.
- Change 7.7.2 as follows:
7.7.2 Angle-beam Examination for Indications Parallel with the Weld Calibration for these examinations shall be in accordance with Paragraphs 6.5 and 6.6. An angle-beam examination shall be accomplished using a 45° and 70° refracted shear-wave from the pipe side of the weld. The sound beam shall be directed perpendicularly into the weld to detect indications parallel with the weld.
*When an examination cannot be accomplished from both sides of the weld, a 45° and 70° refracted shear-wave examination shall be accomplished from one side of the weld.
- Change 7.7.3 as follows: .
7.7.3 Angle-Beam Examination for Indications Perpendicular to the Weld An angle-beam examination shall be conducted on the base material on the pipe side of the weld by placing the 45° shear-wave search unit on the surface of the pipe base material with the sound beam directed parallel with the weld to detect indications perpendicular to the weld. The entire length of the weld and the adjacent base material shall be scanned with the search unit directed in this manner from two opposing directions. Scanning coverage for this examination shall extend a minimum of 1 inch from the weld fusion line.
/
PROCEDURE DEVIATION Page 1 of 1 Pages Procedure . IRevision No. I Deviation No. S~Rl-NDT- .600-39 9 2 The following examination areas are affected by this deviation: Manual ultrasonic examination of small diameter piping welds. The following. paragraphs shall be deviated from as indicated: Add paragraph 6.9.2.1 to read as follows: 6.9.2.1 Verification of Calibration Reflectors at Scanning Speeds The examiner shall verify the presence of the calibration reflector at scanning speed. It is not necessary to assure that this check confinrui the signal amplitude at 100% of reference level, but merely to demonstrate that the signal from the calibration reflectors are readily observable at scanning speed*
- The following statement shall be documented on the SwRI Calibration Record Sheet and initialed:
"Calibration reflectors have been verified at scanning speed.*
Rationale for deviation: This complies with the customer's request to verify calibration reflectors under procedural scanning conditions. If the deviation is determined to affect !he procedure Deviation Affects Qualification YES D NO (iJ qualification. the deviation shall be qualified in accordance with Procedure IX*FE-107. APPROVALS SAFL.J) Date: Technical Review: .. / _/ ///~ P-<!'!~ ~t:t_
- , /
Date: / ., Verbal Approval Given? 0Yes B"No ,.../i*r"'
.I Date: Cognizant Director: Date:
SwRI FORM FE-4-6
-* SwRI-NDT-600-39
- ~SOUTHWEST RESEARCH INSTITUTE Title NUCLEAR PROJECTS OPERATING PROCEDURE MANUAL ULTRASONIC EXAMINATION OF SMALL-DIAMETER PIPING WELDS Revision 9 February 1989 Page 1of16 EFFECTIVITY AND APPROVAL Revision 9 of this procedure became effective on Feb 15, 1989 . Other revisions of the base document may be effective concurrently.
SA Approvals f UJ W<ittar-t*1~
* *'1, * //('/} J1/.7/Z J'
Date
~o/6'8 J:}.'~ (/.fi{µur Date l/:..'./G-6-~
Mana(er of Q.A. J Date Cognizant Director Date
~r: ....f~ ~11~~ ~~4r z/t>/81 The following.information may be used for convenience. Completion of this portion is not mandatory.
Deviation No. Date Effective Procedure Section (s) Affected Notes:
- SwRI Form QA 40A*O
\
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 2 of 16 MANUAL ULTRASONIC EXAMINATION OF SMALL-DIAME1ER PIPING WELDS SwRI-NDT-600-39
- 1. PURPOSE This procedure provides the technical information and detailed steps necessary to ensure a proper manual ultrasonic examination of small-diameter circumferential piping welds in accordance with the applicable AS:ME Boiler and Pressure Vessel Code.
2 SCOPE AND APPUCATION Angle-beam shear-wave, straight-beam longitudinal-wave, manual, contact, pulse-echo ultrasoriic techniques shall be employed for weld examination of 1.5-to 2.5-inch nominal-diameter circumferential piping. Circumferential piping welds and adjacent base material with a 0.1- to 0.4-inch nominal thickn~ss shall be ~xamined as specified in the applicable SwRI Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) AS:ME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) AS:ME Boiler and Pressure Vessel Code, Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination," with the exception of the following:
Figure T-542.2.1 of Article 5, Section V, requires the basic calibration block for the weld thickness of material to which the search unit is applied up to and including 1 inch to be 3/4 inch or t.- Paragraph 5.3.2 of this procedure requires the basic calibration block to be either t, no more than 25% less than t, or closer in thickness to t than the 3/4-inch
- alternate thickness allowed by Article 5 for t up to and including 1 inch. This will assure a more accurate calibration than the Article 5 basic calibration block design allowed by Code.
(3) SwRI Nuclear Quality Assurance Program Manual (NQAPM) SwAI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 3 of 16 3.1
- Applicable Cah"bration and Examination Records SwRI NDTR Form No. Revision Date 17-13 7-31-75 17-14 7-31-75 17-18 3-14-79 17-19 12-01-83 17-25 7-10-80
- 4. RESPONSIBJLITY (1) The Director of the Department ofNDE Services, Nondestructive Evaluatio~ Science and Technology .Division, shall be responsible for the preparation, review, appr:oval, and control of this procedure. ,
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the latest revision of the NQAPM specified in the applicable SwRI Project Plan.. (3) The examin~r shall be respo~sible for implementing the requirements of this procedure. (4) The Manager of the Quality Assurance Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in. accordance with this procedure.
- 5.
- PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations in accordance with this procedure shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control."
5.2 Reference Blocks Reference blocks used for screen distance calibration and verification shall be of the same basic material as the production material; i.e., carbon steel or stainless steel, and shall be one of the following: (1) SwRI Half-round, (2) AWS-type DC, or (3) IIW. The actual refracted beam angle of shear-wave search units shall be determined on an SwRI Pipe Reference Block (PRB). The curvature of the PRB shall conform to the nominal curvature of the examination area; i.e., a 1.5" nominal diameter pipe shall require a 1.5" diameter PRB to be utilized . SwAI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 4 of 16 5.21 Reference Block Selection Reference' blocks shall be used as follows for screen distance calibration: (1) Straight-Beam Screen Block Distance Block Type Dimension 0.5" AWS-Type DC 0.5" 1.0" SwRI Half-Round 1.0" AWS-Type DC 0.5" or 1.0" IIW 1.0"* (2) Angle-Beam Screen Block Distance Block Type Dimension 1.0" AWS-Type DC 1.0" Radius 2.0" or 2.5" SwRI Half-Round 1.0" Radius AWS-Type DC 1.0" or 2.0" Radius 53 Basic Cah'bration Block Calibration reflectors shall be notches machined on the outside and inside surfaces of the basic calibration block. The notches shall be in accordance with approved drawings of the basic calibration block contained in the applicable SwRI Examination Plan. The finish on the surfaces of the basic calibration block shall be representative of the surface finishes of the piping. 5.3.1 Ferritic Piping The basic calibration block for ferritic piping shall be fabricated from material of the same nominal diameter and of the same nominal wall thickness and pipe schedule as the pipe to be examined. This material shall be from-one of the materials specified for the piping being joined by the weld . SwAI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 5 of 16
- 5.3.2. Austenitit: ]';ping The basic cahbration _!Jlock for austenitic piping shall be manufactured from material of the same nominal wall thickness, specification, product form, *and heat treatment as one of the materials being joined. When examining dissimilar metal welds, the calibration block material specification shall be based on the material to which the search unit is applied.
Where two base material thicknesses are joined, the basic calibration block thickness shall be determined by the average weld thickness of the piping to which the search unit is applied and by Article 5, Section V. When a basic cahbration block of the same thickness as t is not available, the basic calibration block thickness shall be no more than 25% thinner than tor shall be closer to t than the 3/4"."inch thick alternate basic calibration block allowed by Article 5. A curved basic calibration block shall be used to establish distance amplitude correction (DAC) curves for examinations on contact surfaces in the range of curvature from 0.9 to 1.5 times the basic cahbration block diameter. 5.4 Search Units
- Search units shall be selected from* the following:
( 1) Straight-Beam Longitudinal-Wave Average Weld Thickness Nominal Search Unit Size 0.1" to 0.4" 1/4" x 1/4" Aerotech (Diamond) Gamma MSWS, 1/4" Round Dual Element (a) A straight-beam longitudinal-wave search unit shall be used. A delay line shoe shall be attached if a 1/4" x 1/4" Aerotech (Diamond) Gamma MSWS search unit is used. (b) The nominal straight-beam longitudinal-wave search unit frequency shall be 5.0 MHz when using an Aerotech (Diamond) 1/4" x 1/4" Gamma MSWS or
- 1/4" round dual-element search unit. A 1/4" round dual-element search unit with a frequency of 2.25 MHz may also be used.
SwRI Form QA 3-2
SOUTHWEST RES EAR.CH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 6 of 16 (2) Angle-Beam Shear-Wave Average Weld Thickness Nominal Search Unit Size
)
0.1" to 0.4" 1/4" Round or 1/4" x 1/4", Aerotech (Diamond). Gamma MSWS (a) The nominal angle-beam shear-wave search unit frequency shall be 2.25 MHz. (b) The search unit wedges shall be fabricated as required to produce a 45° +/-2° refracted shear wave. The contact surface of the wedges shall conform to the surface of the pipe for the examination being c~nducted. 5.5 Ultrasonic ~ent The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1. 5.6 Couplant (1) (2) USP-grade glycerine or reactor-grade water shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure. USP-grade glycerine shall be certified for sulfur content and total halogens in accordance with D-129 and D-808 of Article 24, Section V. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Deionized water, when used, shall be supplied by the customer. (3) Couplant materials used for examinations shall be the same as used for the calibration. 5.7 Thermometer The thermometer to be used for measuring the calibration block and component temperatures ~hall be calibrated and certified and shall display a valid calibration tag as required by
- NQAP 10-1. . .
SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 7 of 16
- 6. CALIBRATION METIIOD 6.1 Instrument Linearity Ultrasonic instrument linearity shall be verified once prior to and once after a period of extended use or every three months, whichever is less, in accordance with Paragraphs 6.1.1and6.1.2.
Data required shall be recorded on the applicable SwRI Instrument Linearity Verification Record, and the sheet number shall be referenced on each applicable SwRI Sonic Instrument Calibration Record. If due to instrument failure a linearity verification cannot be performed, the calibration verification of Paragraph 6.9 shall constitute evidence of the instrument linearity. If a calibratiun verification does not fall within the tolerances required by Paragraph 6.9.2 due to instrument failure, an inst~ment linearity check must be performed prior to continuing examinations, and all components examined' since the last valid calibration verification shall be reexamined. NOIB The setting of the damping control shall be recorded on the applij::able SwRI Instrument Verification Record. The damping control shall be in the same position during linearity verifica~ion, calibrations, and examinations or a new linearity verification shall be performed.. 6.1.1 Saeen Height Linearity (1) Position a shear-wave search unit on a calibration block to obtain indications from the 1/2T and 3/4T holes [the calibration block for amplitude linearity verification is not necessarily the basic calibration block specified for calibrating distance amplitude correction (DAC) curves in aecordance with this procedure]. EXCEPTIONS Alternatively, a straight-beam unit may be used on any calibration block that provides amplitude differences with sufficient signal separation to prevent overlapping of the two signals. (2) Adjust the search unit position to give a 2: 1 ratio between the two indications, with the larger indication set at 80% of full screen height (FSH) and the smaller indication set at 40% of FSH. (3) Without moving the search unit, set the larger indication to 100% of FSH and record the amplitude of the smaller indication, estimated to the nearest 1% of FSH. (4) Successively set the larger indication from 100% to 20% ofFSH in 10% increments (or 2 dB steps if a fine control is not available); record the smaller indication estimated. to the nearest 1% of FSH at each setting. The reading muse be 30% of the larger amplitude within 3% of FSH. SwAI Form QA 3*2
SwRI-NDT-600-39 SOUTHWEST RESEARCH INSTITUTE Revision 9 February 1989 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 16 6.1.2 Amplitude Control Linearity (1) Position a shear-wave search unit on a calibration block to obtain maximum amplitude from the 1/2T hole. NOTES The primary reference level sensitivity should be within the highest and lowest gain settings used
*during amplitude control linearity verifications. The highest and lowest gain settings used during the amplitude control linearity verifications shall be recorded in the Remarks column of the applicable *swRI Linearity Verification Record.
Other convenient reflectors from any cah'bration block may be used with angle- or straight-beam search units. (2) Without moving the search unit, set the indication to the required percent of FSH and increase or decrease the dB as specified below. The signal shall be recorded to the nearest 1% of FSH and shall fall within the limits of the following table: Indication Set at % of FSH 80% 80% 40% dB Control Change*
- 6 dB
-12 dB
- 6 dB Indication Limits. % of FSH
.32 16 64 to to to 48%
24% 96% 20% +12 dB 64 to 96%
*Minus denotes decrease in amplitude; plus denotes increase.
.6.2 Cah'bration The ultrasonic calibration shall be completed prior to the examination.
The REJECT control shall be maintained in the 0 position during calibration and examination. The FREQ MHZ control shall be turned to 2 when a 2.25-MHz search unit is used and to 5 when a 5.0-MHz search unit is used. The type and length of the search unit cable shall be recorded on the Sw RI Sonic Instrument Calibration Record and all other information blocks on this form shall be filled in. SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 9 of 16 6.3 Tempera~e Requirements The basic calibration block temperature shall be within 25°F of* the component temperature and shall be recorded on the SwRI Sonic Instrument Calibration Record for the initial calibration and each verification. The surface temperature of the component to be examined shall be taken prior to and after performing each examination and shall be recorded on the applicable SwRI Examination Record.
6.4 Straight-Beam. Distance Calibration (1) The screen distance chosen shall be the shortest applicable size to include at least 1/4t beyond the thickest production material to which the search unit is applied. (2). Attach a delay line shoe if a 1/4" x 1/4" Aerotech (Diamond) Gamma MSWS search unit is used. (3) Position the straight-beam search unit on an appropriate reference block, observe the back reflections, and set up the required linear sound path distance along the screen baseline. (4) Screen distance shall be selected from the following sizes: 0.5" or 1.0". 6.5 Angle Determination The actual refracted beam angle of shear-wave search units shall be determined on the PRB as follows: (1) Select a PRB with the same nominal curvature as the examination surface and wedge. (2) Peak the signal from the hole parallel to the block axis for transverse wedges and the hole perpendicular to the block axis for nontransverse wedges. (3) Read the actual refracted angle in line with the exit point scribed on the wedge. (4) This angle shall be 45° +/-2° or the wedge shall not be* used. 6.6 Angle-Beam Distance Calibration Distance calibration shall be performed using the appropriate reference block and calibration block as follows: SwAI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 10 of 16 (1) Screen distance shall be selected from the following sizes: l.0",.2.0", or 2.5". (2) Couple a flat wedge to the search unit. *Observe the radius echoes from the applicable reference block and set up a linear sound path distance along the screen baseline, which shall include 1/8 vee-path beyond the anticipated examination distance. Couple the search unit to the wedge for the nontransverse examinations. (3) Calculate Qr measure the metal path to the 4/8 vee-path position on the applicable calibration block. (4) Obtain the peak response from the 4/8 vee-path position. (5) Using only the DEIAY control, set the signal on the appropriate position on the screen baseline. Observe the 4/8 notch signal and record all required verification block entries on the SwRI Sonic Instrument Calibration Record. (6) Obtain the peak response from the 4/8 vee-path position using the search unit required for the transverse examinations. Without changing the screen distance, observe and record all required data entries. ) (7) No attempt shall be made to compensate for any delay difference between the nontransverse and transverse search units. This difference shall be considered when resolving indications. 6.7 Angle-Beam Distance Amplitude Correction N01E DAC curves shall be constructed from the notches perpendicular to the axis of the calibration block when using the nontransverse wedge. DAC curves shall be constructed from the axial notches for cah"brations requiring the transverse wedge. (1) Position the angle-beam search unit on the calibration block to obtain maximum response from the vee-path position selected from the following, that produces the highest amplitude: Vee-Path Positions 4/8, 8/8, 12/8 (2) Set this primary reference response to 80% ::!:5% of FSH and mark its amplitude on the screen. SwR I Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9
- February 1989 Page 11of16 (3) Without changing the gain controls, obt'ain maximum response from the remaining vee-path positions; mark and join all amplitude points with a smooth curved line, which shall not extend more than 1/8 vee-path past the last qualified calibration point.
6.8 Secondary DAC Calibrations Each point on the DAC curve shall appear at a minimum of 20% of FSH or a secondary DAC curve shall be constructed as follows: (1) Secondary DAC curves shall contain at least 2 points. (2) The DAC point at the 8/8 vee-path shall be brought to the primary reference level and marked on the instrument screen. The 12/8 vee-path position, previously at less than 20% of FSH, shall be marked on the screen and both points connected
- with a smooth curved line. Instrument gain settings for this secondary DAC curve shall be recorded on the appropriate SwRI Sonic Instrument Calibration Record.
- . EXCEPTION When the 8/8 vee-path position is set at the primary reference level, and the 12/8 vee-path position -
is below 20% of FSH, a secondary DAC curve is not required. 6.9 Cah"'bration Verification 6.9.1 Sweep Range and DAC Curve Verification Sweep range calibration shall be verified on the appropriate reference block; and DAC curve calibration, if applicable, shall be verified on the appropriate basic calibration block: (1) Prior to a series of examinations (2) With any substitution of search unit cable (3) With any substitution utilizing the same type of power source; e.g., a change of batteries (4) At least every 4 hours during the examination (5) At the completion of a series of examinations (6) Whenever the validity of the calibration is in doubt
- SwRI Form QA 3*2
SOUTHWEST RES EAR.CH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revisi9n 9 February 1989 Page 12 of 16 6.9.2 Calibration Changes (1) Perform the following if any point on the DAC curve has decreased more than 20% or 2 dB in amplitude, or any point on the sweep line has moved more than 10% of the sweep division reading or 5% of full sweep whichever is greater: (a) Void all examinations referring to the cahbration in question and performed after the last valid calibration verification. (b) Conduct a new cahbration. (c) Reexamine the areas for which examinations have been voided. (2) Perform the following if any point on the DAC curve has increased in amplitude more than 20% or 2 dB: (a) Correct the calibration. (b) Reexamine all indications recorded sinc;:e the last valid calibration verification . (c) Enter proper values on a new SwRI Examination Record. 6.9.3 Recalibration Substitution of any of the following shall be cause for recalibration: ( 1) Search unit wedge or transducer* (2) Couplant (3) Ultrasonic instrument (4) Examination personnel (5) Type of power source; e.g., a change from direct to alternating current
- 7. EXAMINATION*
7.1 &amination Areas This procedure shall apply to ultrasonic examination from the outside surface of 1.5- to 2.5-inch nominal diameter pressure piping circumferential welds and adjacent base material with a 0.1-inch to 0.4-inch nominal thickness. SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 13of16 Scanning of the weld and base material shall be adequate to ensure complete two.--
directional coverage. The base*material shall be examined for a distance of 1 inch as* measured from the outside surface fusion line on each side of the weld. NOTE The examination of circumferential welds shall be conducted only from the pipe side of the weld when piping components are welded to the pipe. 72 Surface Condition The contact surfaces shall be free from weld spatter, roughness, or other conditions which interfere with free movement of the search unit or impair the transmission of ultrasound. 7.3 .Attenuation
.Attenuation measurements shall not be performed.
- 7.4 15 Indication Length Zero Reference (LcJ Location
.Areas to be examined in accordance with tqis procedure shall have an L 0 marked in accordance with the applicable revision of SwRI Nuclear Projects Operating Procedure IX-FE-103.
Scanning When practicable, scanning shall be performed at a minimum gain setting of 2 times the reference level sensitivity. If 2 times the reference level is not practicable, the limitation shall be recorded and the customer shall be notified on a case-by-case basis. Instrument gain setting for scanning shall be determined on the basic calibration block as follows for each primary reference level utilized: (1) With the instrument at the primary refere'nce level, manipulate the s.earch unit on the basic calibration block to obtain a signal of 40% of FSH from a calibration reflector (machined notch). (2) Add 6 dB gain by utilizing the 6 dB switch (if present), the fine gain control, or a combination of the fine and coarse gain controls and choose any method that yields a signal response within +/-2 dB of 80% FSH. (3) This amplitude and method shall be recorded on the SwRI Sonic Instrument Calibration Record and shall be used during the valid calibration period for all scanning at 2 times the reference level sensitivity. SwAI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE
, SwRI-NDT-600-39 Revision 9 February 1989 Page 14 of 16 Search unit movement rate for scanning shall not exceed six inches per s~~ond.
Scanning overlap shall be a minimum of 25% of the search unit piezoelectdc elemen,t dimension perpendii:ular to the direction of scan. 7.6 Base Material Lamination Scan A lamination scan using straight-beam shall be performed on ferritic piping which shall cover the entire area through which the angle-beam passes. The lamination scan shall be conducted as follows: (1) Screen distance calibration for this examination shall be conducted in accordance with Paragraph 6.4 of this procedure. (2) Scanning sensitivity shall be as required to maintain the first back reflection at an amplitude of between 50% and 90% of FSH. , (3) To record an intermediate indication, a back reflectien signal shall be obtained from an indication-free area and the instrument gain control adjusted until this ., signal is at 80% +/-5% of FSH. Record the intermediate indication when its . amplitude is equal to the initial back reflection. Areas of total loss of back reflection accompanying the intermediate echo shall also be recorded. A lamination scan is not required for austenitic piping. 7.7 Circumferential Butt Welds in Piping
- 7. 7.1 , Thidaless Measurements Thickness measurements shall be taken at a minimum of three points (on the weld centerline and in the base material on each side of the weld). Screen distance calibration for this examination shall be in accordance with Paragraph 6.4. Measurements shall be taken by placing the straight-beam search unit on the examination surface and recording the position of the back wall reflection observed on the instrument screen.
- 7.7.2 Angle-Beam E:r.amination for Indications Parallel with the Weld NOTE Calibration for these examinations shall be in accordance with Paragraphs 6.5 and 6.6.
An angle-beam examination shall be accomplished using a 45° refracted shear-wave from both sides of the weld. The sound beam shall be directed perpendicularly into the weld to detect indications parallel with the weld. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-39 Revision 9 February 1989 Page 15 of 16 When an examination. cann~t be aecomplished from both sides of the weld, a 45° refracted shear-wave examination shall be accomplished from one side of the weld and the limitation shall be recorded.
7.7.3 Angle-Beam Examihation for Jnmcatimu Perpendicular to the Weld An angle-beam examination shall be conducted on the weld and the base material on both sides of the weld by placing the 45° shear-wave search unit on the surface of the weld and base material with the sound beam directed into and parallel with the weld to detect indications perpendicular to the weld. The entire length of the weld and the adjacent base material shall be scanned with the search unit directed in this manner from two opposing directions. Scanning c~JVerage for this examination shall extend a minimum of 1/4 inch from the weld fusion line. 7.8 Postexamination Cleaning Arrangements shall be made with the customer for postexamination removal of couplant materials.
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-117.
Ultrasonic reflectors producing a response 50% or greater of the reference level shall be recorded on the appropriate SwRI Examination Record. All ultrasonic reflectors, regardless of signal amplitude, not attributable to geometry shall be investigated by a Level II or Level ill examiner to determine the shape, identity, and location of the reflector. Examples of nongeometric reflectors are those which are slightly removed from the weld, root, and/ or chamfer, mask the root indications, are transverse to the weld, or have linear dimensions with side branches. Indications 50% or greater of the reference level attributable to geometry shall be recorded only once, even if the amplitude.of the indication drops below the required recording amplitude along the weld. These indications shall be investigated by a Level II or a Level III examiner to determine the shape, identity, and location of the reflector. If indications that have been recorded as geometry have been investigated and found to be nongeometric reflectors, the entire weld shall be reexamined and all nongeometric reflectors and other reflectors not previously recorded at least once shall be recorded. Indications 100% or greater of the reference level shall be investigated by a Level II or a Level ill examiner to determine the shape, identity, and location of the reflector.
- Scanning limitations shall be recorded .
SwRI Form QA 3-2
SwRI-NDT-600-39 SOUTHWEST RESEARCH INSTITUTE Revision 9 February 1989 NUCLEAR PROJECTS OPERATING PROCEDURE Page 16 of 16
- 9. EVALUATION Initial evaluation .of reportable indications shall be performed by SwRI personnel. Final evaluation and disposition of reportable indications shall be the responsibility of the customer and shall be conducted in accordance with Article IWA-3000, Section XI, of the applicable ASME Boiler and Pressure Vessel Code.
- 10. RECORDS .
Documents generated in accordance with this procedure shall be stored as specified in the SwRI Project Plan. The* customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan. SwR I Form QA 3-2
- PROCEDURE DEVIATION The following examination areas are affected by this deviation:
Revision No. Page 1 of 1 . Pages 1 tntrasonic baseline examinations to be performed in accordance with this procedure for Public Service Electric and Gas Company. * *
.)
The following paragraphs shall be deviated from as indicated: Change the title of 7.5 to read as follows: Thickn e?ss Measurements and Base Material Lamination Scan Add the following as the third and fourth paragraphs under 7.5: A lamination scan using longitudinal-wave shall be performed. This scan shall cover as much as practical of the area through which the angle-beam passes. The lamination scan shall be conducted as follows: (1) Scanning shall be performed at a gain setting that gives an initial backwall amplitude of 80% +/- 5% FSH. Exception
- (2)
A lamination scan is only required for baseline examinations. To record an intermediate indications, obtain a backwall reflection signal from an indication-free area and adjust this signal to 80% +/- 5% of FHS. Record the intermediate indication when its amplitude is equal to the remaining backwall reflection. Areas of total loss ofbackwall reflection accompanying the intermediate echo shall also be recorded.
- Rationale for deviation:
The customer requests that base material lamination scans be performed during baseline examinaitons performed in accordance with this procedure. It !he deviation is determined to affect the crocedure Deviation Affects Qualification YES 0 NO [) c:iualification. the deviation shall be c:iualified in ac::ordance with Procedure IX*~E-107. APPROVALS SA ,t::i_j) Date: £ _~--./e _ Technical Review: , /
- I Date: / I
'-._;J Verbal Approval Given? D Yes 1.)4 No Date:
S.*1rll FCRM FE-4-6
SwRI-NDT-600-41
~SOUTHWEST RESEARCH INSTITUTE Revision 16
_ .NUCLEAR PROJECTS December 1987 OPERATING PROCEDURE Page 1 of 20 Title MAi.~AL ULTRASONIC EXAMINATION OF FERRITIC PRESSURE PIPING WELDS
~ EFFECTIVITY AND APPROVAL I{;, 1 z..; z*zJ ti7 Fievision ..J...3""'ot this procedure became effective on Qei;; 21
- 1987. Other revisions ot the base document may be effective concurrently.
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Date Cogl~' m"cto' ef:e following infor~tion may be used for convenience. Completion 1i-I of this portion is not mandatory. Date
~I/ft Deviation No.
Date Effective Procedure Section(s) Affected Notes:
- SwRI Form QA*40A*O
I SOUTHWEST RESEARCH INSTITUTE fSJL-_
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~ 10' / 7 NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 2 of 20 MANUAL ULTRASONIC EXAMINATION OF FERRITIC PRESSURE PIPING WELDS SwRI-NDT-600-41
- 1. PURPOSE This procedure provides the technical information and detailed steps necessary.to ensure a proper manual ultrasonic examination of ferritic pressure piping welds and the adjacent base material in accordance with the applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.
- 2. SCOPE AND APPLICATION r Class 1 and Class 2 full-penetration pressure piping butt welds and the adjacent base material in the nominal thickness range of 0.2 to 6.0 inches shall be examined.
Manual, contact, pulse-echo, shear-wave angle-beam, and longitudinal-wave straight-beam ultrasonic techniques shall be utilized for the examination of clad.or unclad piping welds and adjacent base material. Welds to be examined shall be circumferential and longitudinal ferritic pipe welds and set-in type branch connection butt welds as specified in the applicable Southwest Research Institute (SwRI) Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Anplicable Calibration and Examination Records SwRI-NDTR Form No. Revision Date 17-18 3-14-79 17-19 12-1-83 17-25 7-10-80 17-37 2-18-80 17-89 8-19-80 17-90 8-19-80 SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 3 of 20
- 4. RESPONSIBILITY (1) The Director of the Department of Engineering Services, Nonde-structive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and. control of
~his procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan. (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Support and Administration Section, Nonde-structive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with this procedure .
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations in accordance with this pro-cedure shall be certified in accordance with SwRI.NQAP 11-1, "Special Process Control."
5.2 Reference Block Reference blocks used for screen distance calibration and verification shall be made of carbon steel and shall be one of the following: (1) SwRI Half-Round, (2) AYS Type DC, or (3) IIY .
- SwR I Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 4 of 20 (1) Straight-Beam Screen Block Distance Block Tvoe Dimension 0.5" AWS Type DC 0. 5" 1.0", 2.0" SwRI Half-Round 1.0" AWS Type DC 0.5" or 1. 0" IIW 1.0" 2 ,5" I 5 0" o SwRI Half-Round 1.0" AWS Type DC 1.0" IIW 1.-0 11 10.0" IIW 4.0" (2) Angle-Beam Screen Block Distance Block Type Dimension 1.0" AWS Type DC 1.0" and 2.0" Radii 2.0", 2.5", SwRI Half-Round 1. 0" Radius 5 .0" AWS Type DC 1. 0" and 2.0" Radii 10.0" SwRI Half-Round 1.0" Radius AWS Type DC 1.0" and 2.0" Radii IIW 4.0" Radius 20.0" IIW 4.0" Radius 5.3 Basic Calibration Block The basic calibration block shall be fabricated from material of the same nominal diameter and of the same nominal wall thickness or pipe schedule as the pipe to be examined. This material shall be from one of the materials specified for the piping being joined by the weld. The finish on the surfaces of the basic calibration block shall be representative of the surface finishes of the piping to be examined.
- When the examination is to be performed from only one side of the weld, the calibration block material shall be of the same specification as the material on that side of the weld. If material of the same specification is not available, material of similar chemical analysis, tensile properties, and metallurgical structure may be used.
SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 5 of 20 The curvature* of the main run pipe shall be used to establish the requirements for the basic calibration block curvature for the examination of branch connection welds.
Calibration reflectors for 12/8 Yee-path (N-path) calibrations shall be notches machined on the outside and inside surfaces of the basic calibration block. The notches shall be in accordance with approved drawings of the basic calibration block and Appendix III of Section XI. Calibration reflectors for 1/2 vee-path examinations shall be a* minimum of two equal-diameter, axially drilled holes located at l/4T and 3/4T, and the inside surface notch. Approved drawings of basic calibration blocks to be used in accordance with this procedure are contained in the applicable SwRI Examination Plan. 5.4 Search Units
- (1) Search units shall be selected from the following:
(a) Straight-Beam Nominal Production Material Thickness Nominal Search Unit Size 2.0" or less 1/4" Round 1.0" to 3.0" 3/8" Round 2.0" to 4.0" 1/2" Round 3.0" to 6.0" 3/4" or 1 11 Round (b) Angle-Beam Nominal Production Material Thickness Nominal Search Unit Size 1.0" or less 1/4" x 1/4", 1/4" Round 0.4" to 2.0" 3/8" x 3/8" 3/8" Round I 0.75" to 4.0" 1/2" x 1/2", 1/2" Round 2.0" to 6.0" 1/2" x l" 3/4" Round I (2) Search unit wedges for angle-beam examinations shall be fabricated as required to p_roduce 45° +/-2° or 60° +/-2° refracted shear waves. (3) The exit point of the sound beam and the actual refracted beam angle of shear-wave search units shall be determined SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITU.TE SwRI-NDT-600-41 Revision 16 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page .6 of 20 on an IIW block. The exit point shall 'be marked on the search unit wedge. (4) The nominal search unit frequency shall be 2~25 MHz. 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1. 5.6 Thermometer The thermometer to be used for measuring the calibration block anci component temperatures shall be calibrated and certified and sha_ll display a valid calibration tag as required by NQAP 10-1. 5.7 Couplant (1) USP-grade glycerine or reactor-grade water shall be used when performing ultrasonic calibrations and examinations in accordance with this procedure. (2) USP-grade glycerine shall be certified for sulfur *content and total halogens in accordance with SD-129 and SD-808 of Article 24, Section V. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Reactor-grade water, when used, shall be supplied by the customer. (3) Couplant materials used for examinations shall be the same as used for the calibration.
- 6. CALIBRATION METHOD The ultrasonic calibration shall be completed prior to the examination.
The FREQ MHz control shall be turned to 2. The REJECT control shall be maintained in the 0 position during calibration and examination. The type and length of the search unit cable shall be recorded on the SwRI Sonic Instrument Calibration Record and all other information blocks on this form shall be filled in. The centerline of the search unit shall be at least 3/4 inch from the nearest side of the calibration block. Rotating the beam into the corner formed SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI~NDT-600-41 Revision 16 December 1987 Page 7 of 20 by the hole and ~he side of the block may produce a higher amplitude at a longer beam path. This beam path shall *not be used for calibration.
The nominal piping production material thickness shall be used to determine
.the correct calibration block and search units for the examinations with geometric restrictions such as piping or components which may be thi.cker than the nominal pipe size, examinations limited to one side of the weld, or wide weld crowns. The Level II or Level III examiner shall ensure that complete coverage of the examination area is obtained. Additional calibration vee-path positions, different angles, and larger screen sizes may be required to assure this coverage.
6.1 Instrument Linearity Ultrasonic-instrument linearity shall be verified once prior to and once after each period of extended use or every three months, whichever is* less, in accordance with Paragraphs 6 .1.1 and 6 .1. 2. Data required shall be recorded on the SwRI Instruinent Linearity Verification Record and the sheet number shall be referenced on each applicable s*wRI Sonic Instrument Calibration Record . If due to instrument failure a linearity verification cannot be performed, the calibration verification of Paragraph 6.4.l shall constitute evidence of the instrument lin.ear_ity. If a calibration verification does not fall within the tolerances required by Paragraph 6.4.3 due td instrument failure, an instrument linearity check must be performed prior to continuing .. examinations and all components examined since the last valid calibration verification shall be reexamined. The setting of the damping control shall be recorded in REMARKS on the SwRI Instrument Linearity Verification Record. The damping control shall be in the same position during linearity verification, calibrations, and examinations, _or a new linearity verification shall be performed. 6.1.1 Screen Height Linearitv (1) Position a search unit on a basic calibration block and obtain indications from two applicable reflectors. (2) Adjust the search unit position to give a 2:1 ratio between the two indications with the larger indication set at 80% of full screen height (FSH) and the smaller indication sec at 40% of FSH. SwRI Form QA 3-2 I*
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-41 Revision 16 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8. of 20
, (3) Without moving the search unit, set. the larger indication to 100% of FSH and record the amplitude of the smaller indication, estimated*to the riearest 1% of FSH.
(4) Successively set the larger indication from 100% to 20% of FSH in 10% increments (or 2 dB steps if a fine control is not available); record the smaller indi*cation estimated to the nearest 1% of FSH at each setting. The reading must be 50% of the larger amplitude within 5% of FSH 6.1.2 Amplitude Control Linearity (1) Position a search unit on a basic cal5.bration block to obtain maximum amplitude from an applicable reflector .
. (2) Without moving the search unit, set the indication to the required percent of FSH and increase or decrease the dB as specified below. The signal shall be recorded to the nearest 1% of FSH .and shall fall within the limits of the following table:
Indication Set at % of FSH 80% 80% dB Control*
-6 dB
-12 dB Indication Limits. % of FHS 32 16 to to 48%
24% 40% + 6 dB 64 to 96% 20% 12 dB 64 to 96%
*Minus denotes decrease in amplitude; plus denotes increase.
6 .1. 3 Temperature Reguirements The basic calibration block temperature shall be within 25°F of the component temperature and shall be recorded*on the SwRI Sonic Instrument Calibration Record for the initial calibration and each verification. The surface temperature of the component to be examined shall be taken prior to and after performing each examination and shall be recorded on t~e applicable SwRI Examination Record. 6.2 Calibration 6.2.1 Straight-Beam Distance Calibration The screen distance chosen shall be the shortest applicable size to include at least l/4t beyond the thickest production material to which the search unit is applied. SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE
'.NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 9 of 20 Observing back reflections from. the applicable reference block, set. up the required linear sound path distance along the screen baseline.
Screen distance calibration for straight beam shall be selected from th~ following sizes: 0.5", 1.0", 2.0", 2.5", 5.0" and 10.0". .. A straight-beam distance amplitude calibration, using calibration reflectors shall not be established with this procedure. 6.2.2 Angle-Beam Distance Calibration The screen qistance chosen shall be the shortest applicable size to include at least 1/8 vee-path past the anticipated examination range. Observing radius echoes from the applicable reference block,-* set up the required linear sound path distance along the screen baseline. Screen dfstance calibration for angle beam shall be selected
- froni the following sizes: 1.0", 2.0", 2.5", 5.0 11 , 10.0", and 20.0" .
6.2.3 Angle-Beam Distance Amplitude. Correction Thickness measurements in accordance with Paragraph 7.5 and crown width measurements taken in accordance with the applicable revision of Nuclear Projects Operating Procedure IX-FE-117 shall be used to determine the shear-wave angle that provides the required coverage. These physical measure-ments, the angle chosen, determined method of coverage, and identification of the Level II or the Level III examiner shall be recorded on the SwRI Straight Beam Lamination Examination Record. Only one angle shall be required for the examination. A 45° angle-beam search unit with a 1/2 vee-path calibration shall be utilized if complete coverage is obtained. The 1/2 vee-path calibration may be extended to include additional vee-path positions if the calibration obtained is equal to or better than the N-path calibration (see Figure 1). A 60° angle-beam search unit with a 1/2 vee-path calibration shall be used if the 45° 1/2 vee-path calibration (or extended calibration) does not obtain complete coverage. A 45° search unit with a calibration extending to the 12/8 vee-path positi9n (N-path) shall be used when the 45° or the 60° 1/2 vee-path calibration does not obtain complete coverage. EXCEPTIONS For examinations on clad material and for 45° transverse examinations, only the.1/2 vee-path calibration shall be used. Only a 45° 1/2 vee-path, 60° 1/2 vee path, or 45° N-path calibration shall be utilized for examination of longitudinal or branch connection welds. SwRI Form QA 3-2
SwRI-NDT.* 600-41 SOUTHWEST RESEARCH INSTITUTE Revision 16 December .1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 10 of 20 6.2.3.1 Angle-Beam Distance Amplitude Correction (1/2 Vee-Path) Whenever possible, a 1/2 vee-path distance amplitude correction (DAC) shall be used. The slope of the DAC curve shall be constructed from the holes parallel to the axis of the basic calibration block. The notch perpendicular to the axis of the curved basic calibration block shall be utilized to establish sensitivity when examining circumferential welds or for transverse examinations on longitudinal or branch connection welds. The axial notch shall be used to establish sensitivity when examining longitudinal or branch connection welds or for transverse examinations on circumferential welds. The 1/2 vee-path DAC calibration shall be constructed as follows: (1) Position a 45° or a 60° search unit, as required, on the basic calibration block to obtain maximum response from the .calibration hole and vee-path position selected from a minimum of three vee-path positions required to cover the entire examination area, the first of which must be . situated prior to the lower l/3t volume and the last at the end or after the l/3t volume. Use only the 1/8, 2/8, and 3/8 vee-path positions for clad material and 45° transverse examinations (extrapolated to 4/8). (2) Set this response to 80% +/-5% of FSH. Mark its amplitude on the instrument screen and record these gain settings under REMARKS. (3) Yithout changing the gain controls, obtain maximum response from the remaining applicable vee-path position(s) that will ensure adequate coverage; mark and join all amplitude points with a smooth curved line. E.XCEPTION If the configuration of the weld is such that the above calibration is not the most appropriate to provide coverage from two directions of the examination volume C-D-E-F as depicted in Figure 1, then a calibration may be established which uses an alternate vee-path position to obtain complete coverage of the examination area from one direction. (4) Establish the sensitivity from the inside surface notch by setting the indication amplitude at the level of the DAC curve. This is the primary reference level and the notch SwRI Form QA 3-2
- . ~
SOUTHWEST RESEARCH INSTITUTE
' NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 11 of 20 amplitude shall be marked on the screen with an X. Record the primary reference level gain settings under INSTRUMENT SETTINGS.
6.2.3:2 Alternate Angle-Beam DAG (N-Path) The notches perpendicular to the axis of the curved basic calibration block shall be utilized to establish sensitivity when examining circumferential welds. The axial notches shall be used to establish sensitivity when examining longitudinal or branch connection welds. (1) Position the 45° angle-beam search unit on the calibration block to obtain maximum response from the vee-path position selected from the following, that produces the highest amplitude:
- (2)
Vee-Path Positions 4/8, 8/8, 12/8 Set this response to 80% +/-5% of FSH and mark its amplitude on the screen. The gain controls shall not be adjusted once ~his primary reference response has been established. (3) Obtain maximum response from the remaining vee-path positions; mark and join all amplitude points with a smooth curved line that shall not extend more than 1/8 vee-path past the last qualified calibration point. EXCEPTION For components that are significantly thicker than the nominal production material thickness, calibrations shall be established which use V-path positions that obtain complete two-directional coverage of the examination area. 6.3 Secondary DAG Calibrations (N-Path Calibration Onlv) If all points on the DAC curve do not appear at 20% of FSH or greater, a secondary DAC curve shall be constructed as follows: (1) Secondary DAC curves shall contain at least 2 points. I
- SwRI Form QA 3-2 (2) The DAG point at 20% of FSH or greater, adjacent to a DAG point that falls below 20% of FSH, shall be brought to the pri~ary reference level and marked on the instrument
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 . December 1987 Page 12 of 20 screen. The other point(s), previously at less than 20% of FSH, shall be marked on the screen and all points connected with a smooth curved line. The gain setting for this secondary DAC curve shall be recorded on the appropriate SwRI Sonic Instrument Calibration Record. EXCEPTIONS When the first DAC point is the only point above 20% of FSH, the next highest point shall be brought to the primary re-ference level and marked on the instrument screen. The other points previously at less than 20% of FSH sha:l be marked on the screen and all points connected with a smooth curved line. 6.4 Calibration Verification 6.4.1 Sweep *Range and DAC Curve Verification Sweep range calibration shall be verified on the appropriate reference block; and DAC curve calibration, if applicable, shall be verified on the appropriate calibration block: (1) Prior to a series of examinations (2) Yith any substitution of the same type and length of search unit cable (3) ~ith any substitution of power utilizing the same type source; e.g., a change of batteries (4) At least every 4 hours during the examination (5) At the completion of a series of examinations (6) Whenever the validity of the calibration is in doubt 6.4.2 Verification of Calibration Reflectors at Scanning Speed The examiner shall verify the presence of the calibration reflector at scanning speed. It is.not necessary to assure that this check confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the signal from the calibration reflectors are readily observable at scanning speed. The following statement shall be documented on the SwRI Calibra-tion Record Sheet and initialed: SwRI Form CA 3-2 "Calibration reflectors have been verified at scanning speed."
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 13 of 20 6.4.3 Calibration Changes (1) Perform the following if any point on the DAG curve has decreased more than 20% of FSH or 2 dB in amplitude or if any point has moved on the sweep line more than 10% of the sweep division reading or 5% of full sweep, whichever is greater:
(a) Void all examinations referring to the calibration in question and performed after the last valid calibration verification. (b) Conduct a new calibration. (c) Reexamine the areas for which examinations have been voided. (2) Perform the following if any point on the DAG curve has increased more than 20% of FSH or 2 dB in amplitude:
- (a)
(b) (c) Correct the calibration. Reexamine all indications recorded since the last valid calibration verification. Enter proper values on a new SwRI Examination Record. 6.4.4 Recalibration* Substitution of any of the following shall be cause for recalibration: (1) Search unit wedge or transducer (2) Search unit cable type or length (3) Ultrasonic instrument (4) Examination personnel (5) Couplant (6) Change in type of power source; e.g., a change from direct to alternating current
- SwRI Form QA 3-2
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SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 14 of 20
- 7. EXAMINATION 7.1 Examination Volume 7 .1.1 Circumferential and Longitudinal Butt Welds in Pining Circumferential and longitudinal ferritic butt welds with a nominal thickness of 0.2 to 6.0 inches shall be examined from the outside surface.of the pipe. Product forms to be examined shall include extruded, drawn, and rolled material.
Scanning of the weld and base material shall be adequate to ensure complete two-directional coverage for l/3t from the inside surface of the pipe. The base material shall be examined for a distance of 1/4 inch from the outside surface fusion line on each side of the weld. See attached Figure 1 for coverage. Class 1 longitudinal welds shall be examined along the entire length of the weld during the preservice examination and for at least one pipe-diameter length or 12 inches, whichever is less, from the fusion line of the intersecting circumferential weld during inservice examinations. Class 2 longitudinal welds shall be examined for at least 2-l/2t length from the fusion line of the intersecting circumferential weld during preservice and inservice examinations. 7 .1.2 Branch Connection Butt Welds in Piping Full penetration butt welds* of branch connections in pressure piping greater than 0.2 to 6.0 inches nominal thickness shall be examined from the outside surface of the main run pipe side of the weld when required. Only set-in branch connections shall be examined with*this procedure. See attached Figure 2 for two-directional examination coverage of branch connection welds. 7.2 Surface Condition The contact surfaces shall be free from weld spatter, roughness, or other conditions that interfere with free movement of the search unit or impair the transmission of ultrasound. 7.3 Indication Length Zero Reference CL0 ) Location Areas to be examined in accordance with this procedure shall have an L0 marked in accordance with the applicable revision of SwRI Procedure IX-FE-103 . SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page. 15 of 20 7.4 Scanning TJhen practicable, scanning shall be performed at a minimum gain setting of 2 times the reference level sensitivity. If 2 times refer"ence level is not practicable, the limitation shall be recorded and the customer shall.be notified on a case by case basis.
Instrument gain setting for scanning shall be determined on the calibration block as follows for each primary reference level utilized: (1) Yith the instrument at the primary reference level, manipulate the search unit on the calibration block to obtain a signal from a reflector of 40% FSH. (2) Add 6 dB of gain by utilizing the 6 dB switch (if.present), the fine control, or a combination of the fine and coarse gain controls and choose any method which yields a signal response within +/-2 dB or 80% FSH.
- (3) This amplitude and method shall be recorded on the SwRI Sonic Instrument Calibration Record and shall be used during the valid calibration period of all scanning at 2 times the reference level sensitivity.
The search unit movement rate for scanning shall not exceed 6 inches per second. Scanning overlap shall be a minimum of 10% of the search unit piezoelectric element dimension perpendicular to the direction of scan. 7.5 Thickness Measurements Thickness measurements shall be taken at a minimum of three points adjacent to L0 for longitudinal and circumferential welds (on the centerline of the weld and at one point in the base mate~ial on each side of the weld), and at a minimum of two points adjacent to L0 for branch connection welds (one on the base material of the main run pipe, and one on the base mate-rial of the branch connection). Locations of measurements which cannot be taken adjacent to L0 , shall be recorded on the appropriate SwRI Examination . Record. The examiner should take additional measurements when the crown height varies significantly or if other thickness changes are observed. Measurements shall be taken and recorded by placing the. straight-beam search unit on the examination surface and observing the position of the back-wall reflection on the instrument screen. Screen distance calibration for this examination shall be conducted in accordance with Paragraph 6.2.1 . SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 16 of 20 The crown height and crown width shall be measured and re~~rded on the appro-priate SwRI Examination Record. 7.6 Examination of Circumferential and Longitudinal Butt Welds in Piping The calibration for these examinations shall be as described in Paragraphs 6.2.2 and 6.2.3. 7.6.1 Angle-Beam Examination for Indications Parallel with the Weld A 1/2 vee-path using a 45° or a 60° refracted shear wave or a 12/8 vee-path using a 45° refracted shear wave shall be accompl.ished, as applicable, from one or both'sides of the weld, whichever obtains complete. coverage. The sound beam shall be directed perpendicularly into the weld to detect indications par~llel with the weld. A 45° 12/8 vee-path examination shall be conducted if a 45° or a 60° 1/2 vee-path examination does not obtain complete coverage. 7.6.2 Angle-Beam Examination for Indications Perpendicular to the Weld EXCEPTION Only those welds showing reportable preservice transverse indications need to be examined for indications perpendicular to the weld. The 1/2 vee-path angle-beam examination shall be conducted on each weld by placing the 45° search unit on the weld crown with the sound beam directed into and parallel with the weld. Scanning shall be performed from two opposing directions on the weld.
- 7.7 Examination of Branch Connection Butt welds The calibration for these examinations shall be as described in Paragraph 6.2.2 and 6.2.3.
7.7.l Angle-Beam Examination for Indications Parallel with the Weld A shear-wave angle-beam examination shall be accomplished from the main run pipe side of the weld. For this examination, the sound beam shall be directed perpendicularly into the weld to detect indications parallel with the weld. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revision 16 December 1987 Page 17 of 20 7.7.2 Angle-Beam Examination for Indications Perpendicular to the
'Weld The exception and the angle-beam examination for indications perpendicular to the weld shall be the same as described in Paragraph 7.6.2.
7.8 Postexamination Cleaning Arrangements shall be made with the customer for postexamination removal of*couplant materials.
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Procedure IX-FE-117.
All ultrasonic reflectors, regardless of signal amplitude, not attributable to geometry shall be recorded and investigated by a Level II or a Level III - examiner to determine the shape, identity, and location of the reflector. Examples of nongeometric reflectors are those which are slightly removed.from the weld root and/or chamfer, mask the root indications, are transverse to the weld, or have linear dimensions with side branches. Indications in~estigated and found to be other than geometrical in nature, shall be reported to the customer for evaluation. Ultrasonic reflectors producing a response greater than 50% of the reference level shall be recorded on the appropriate SwRI Examination Record. Indications greater than 50% of the reference level attributable to geometry shall be recorded only once, even if the amplitude of the indication drops below the required recording amplitude along the weld. These indications shall be investigated by a Level II or a Level III examiner to determine the shape, identity, and location of the reflector. If indications that have been recorded as geometry have been inve~tigated and found to be nongeometric reflectors, the entire weld shall be reexamined, recording all nongeometric reflectors and other reflectors not previously recorded at least once. Scanning limitations shall be recorded.
- 9.
- EVALUATION Initial evaluation of reportable indications shall be performed by SwRI personnel, and shall be conducted in accordance with the applicable ASME Boiler and Pressure Vessel Code, Section XI, Article IWA-3000. Final evaluation ar.d disposition of reportable indications shall be the responsibility of the customer.
SwAI Form QA 3*2
*soUTHWEST RESEARCH INSTITUTE SwRI-NDT-600-41 Revision 16 December 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 18 of 20 10 .. RECORDS Documents generated in accordance with this procedure shall be stored as specified in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan.
SwAI Form QA 3-2
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SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-41 Revis *ion 16 December 1987 Page 19 of 20 FIGURE 1 EXAM AREAS FOR CIRCUMFERENTIAL AND LONGITUDINAL WELDS VOLUMETIUC EXAMINATION lntwrtennce
~slloe 1/4 11 . 1/4" (1) Two-direc1:ional coverage of the examina1:ion volume shall be ob.t:ained by the following method:
1/2 V-pat:h examination from bot:h sides of the weld if ~eld crown geometr:r permits scanning over the weld. (2) If geometric conditions prevent T.J.se of the aoove method, coverage shall be based on a best effor1: and any limitations shall be ~ecorded . SwRI Form QA 3*2
SwRI-NDT-600-41 SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE Revision 16 December 1987 Page 20 of 20
- Figure 2
~--~1-=----1 Examination Area A-B-C-D I.
i - --
-...;..1-*~.-
(Lower l/3t of the Yeld and r l/4 Inch Base Material on
- ,------;lc=:.___ l Each Side of the Yeld)
Iii r-r--
'-r-*~c.
I t .\__ --, II , -*----------,
-- h---\*
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=--
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n-------- ------t------t I I I - I l
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H i BRANCH CONNECTION YELDS (Volumetric Examination Requirements) SwRI Form QA 3*2
-* PROCEDURE DEVIATION Revision No. Page 1 of 1 Pages Calibrations performed in accordance with this procedure. The following paragraphs shall be deviated from as indicated: Add as Ps.ra.graph 6.3.5 (9): Verification of Calibration Reflectors The Examiner shall verify the presence of the calibration reflector at scanning speed. It is not necessa.cy to assure that this chuck confirms the signal amplitude at 100% of reference level, but merely to demonstrate that the reflector signal is readily observable at scanning speed.
- The following statement shall be documented on the SwRI Calibration Record Sheet and initialed: "Calibration reflectors have been verified at scanning speed.
- Rationale for deviation:
This deviation complies with the NRC's request to verify the presence of the calibration reflectors under procedural scanning conditions. If the deviation is determinea to affect the procedure Deviation Affects Qualification YES D NO Q Quaiification, the deviation shall be Qualified in accordance with Procedure IX-F'E-107. APPROVALS SA t:"LD
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SwRI~NDT-600-48
~SOUTHWEST RESEARCH INSTITUTE Revision 1 NUCLEAR PROJECTS November 1988
. OPERATING PROCE_DU R.E Page 1 of 16 Title MANUAL ULTRASONIC EXAMINATION OF PRESSURE VESSEL WELDS IN ACCGRDANCE WITH REGULATORY GUIDE 1.150 EFFECTIVITY AND APPROVAL Revision 1 of this procedure became effective on Nov. 23, 1988 Other revisions of the base document may be effective concurrently.
SA flj) Approvals Wr~ *;:2 Date 18- L:() {/
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Manager of Q.A. ~ Date Cognizant Director Date J.rJ.J~ 11/z i-h? avvu( ~~~ ;(~ 11/z.1/'68 The following information may be used for convenience. Completion of this portion is not mandatory. Deviation No. Date Effective Procedure Section (s) Affected Notes:
- SwRI Form QA*40A*O
SwRI-NDT-600-48 SOUTHWEST RESEARCH INSTITUTE Revision 1 November 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2 of 16 MANUAL ULTRASONIC EXAMINATlON OF PRESSURE VESSEL WELDS
. IN ACCORDANCE WITH REGULATORY GUIDE 1.150 SwRI-NDT-600-48
- 1. PURPOSE This procedure provides the information and details necessary to ensure a complete and accurate manual ultrasonic examination of ferritic reactor pressure vessel welds and adjacent base material in accordance with the applicable* Ameri-can Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code.
- 2. SCOPE AND APPLICATION This procedure has been prepared for the manual, contact, pulse-echo, shear-wave angle-beam and longitudinal-wave straight-beam, ultrasonic examina-tion of reactor pressure vessel welds and adjacent base material.
Ferritic reactor pressure vessel welds and adjacent base material from greater than 2.0 to 12.0 inches nominal wall thickness shall be examined. Welds to be examined shall be as specified in the applicable Southwest Research Insti-tute (SwRI) Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Sections XI, 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Sections V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) NRG Regulatory *Guide 1.150, Revision 1, Appendix A, entitled "Ultra-sonic Testing of Reactor Vessel Welds During Preservice and Inserv-ice Examinations" (4) SwRI Nuclear Quality Assurance Program Manual (NQAPM).
SwAI Fo;m QA 3-2 I
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-48 Revision 1 November 1988 Page 3 of 16 3.1 Calibration. and Examination Records SwRI NDTR Form No. Revision Date 17-18 03-14-79 17-19 12-01-83 17-25 07-10-80 17-36 08-03-82 17-37 02-18-80 17-105 02-28-84 17-106 02-28-84 17-107 02-28-84
- 4. RESPONSIBILITY (1) The Director of the Department of NDE Services, .Nondestructive Eval-uation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure .
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan. (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of Quality Assurance shall be responsible for storage of records generated in ac'cordance with this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Personnel performing examinations for.flaw resolution and sizing in accordance with this procedure shall be certified in accordance with SwRI NQAP 11-1, "Special Process Cont;rol".
5.2 Reference Block Reference blocks used for screen distance calibration and verifica-tion shall be made of the same material as the production material, carbon steel, and shall be one of the fol~owing: (1) SwRI Half-Round, (2) AWS-Type DC, or (3) IIw .
- SwRI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-48 Revisiori 1 November 1988 Page 4 of 16 5.3 Basic Calibration Block Approved drawings of the basic calibration blocks are contained in the applicable SwRI Examination Plan. 5.4 Search Units The nominal search unit frequency shall be 2.25 MHz. (1) Straight-Beam Averag'e Weld Thickness Nominal Search Unit Size 2 .0 11 to 4.0 11 3/8" or -1/2 11 . round
- 3. 0 11 to 7 .0 11 1/2" or 1.0" round 5.0 11 to 12.0" 1 ~o" or 1-1/8 11 round.
(2) Angle Beam Average Weld Thickness 2.0" to 4.0 11 3 .0 11 to 7 .0" 5 .0" to 12.0" Nominal Search Unit Size 1/2" X 1/2", 1/2 11 round 1/2" X l", 3/4 11 round l" X 1 11 , 1 11 , l-l/8"round Search units wedges shall be fabricated to produce 45° +/-2° and 60° +/-2° refracted shear-wave. The exit point of the sound beam and the actual refracted beam angle shall be determined on an IIW block. The exit point of the sound beam shall be marked on the search unit wedge. 5.5 Ultrasonic Instrument The examiner shall use Sonic "FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1. 5.6 Couplant (1) USP-grade glycerine, Sonotrace 40, or Ultragael II shall be used when performing calibrations and examinations in accor-dance with this procedure. (2) Other couplant materials may be used if approved by the Proj-ect ~-tanager. SwRI Form QA 3-2
- SOUTHWEST.RESEARCH INSTITUTE NUCLEAR PROJECTS OPER.ATING PROCEDURE SwRI-NDT-600-48 Revision 1 November 1988 Page 5 of 16 (3) Couplant materials used shall be certified for suffer content
. and total halogens. The residual.amount of total sulfur or halogens shall not exceed 1% by weight.
(4) Couplant materials used for examinations shall be the same as used for the calibration. 5.7 Thermometer The thermometer to be used to measure the calibration block and component temperatures shall be calibrated and certified and shall display a valid.calibration tag as required by NQAP 10-1.
- 6. CALIBRATION METHOD 6.1 Temperature The basic calibration block temperature shall be within 25°F of the component temperature and shall be recorded on the SwRI Instrument Calibration Record for the initial calibration and each verification. The.surface tempera-ture of the component to be examined shall be measured prior to and after each examination and shall be recorded on the applicable SwRI Examination Record.
6.2 Waveform Photos Photographs shall be taken of the RF waveform from an appropriate. reflector in the calibration block used for the examination (the l/2T hole, if practicable, in the respective calibration block, shall be used. This shall be performed during the initial calibration and final calibration verification or upon change of ultrasonic instrument, transducer, search unit cable, or use of another calibration block as follows: (1) Preset the controls on an oscilloscope (Tektronix or equiva-lent) capable of delayed sweep to measure an RF waveform of approximately 0.3 volts, peak to peak. (2) Using a coaxial cable approximately 4 feet long, connect oscilloscope channel 1 to the RF output jack or internally if a RF output jack is not provided. (3) Using the oscilloscope controls, obtain a stable RF wave-form. Use the delay sweep function as required to expand the RF waveform for photographing. (4) With the CRT camera, obtain a Po.laroid picture of the RF waveform. Identify on the photograph the ultrasonic SwAI Form QA 3-2
SwRI-NDT-600-48 SOUTHWEST RESEARCH 'INSTITUTE Revision 1 November l988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 16 instrument serial number, remote pulsar ch~nnel, and oscillo-scope control settings (i.e., VOLTS/DIV, TIME/DIV AND DELAY TIME), and delay time position control. (5) Photographs shall be identified so that it is traceable to the applicable calibration information and reflector 'l.J,sed for photograph. 6.3 Calibration An ultrasonic calibration shall be completed prior to conducting examinations. The REJECT control shall be maintained in the 0 position during c~libration and examination. The FREQ MHz control shall be turned to 2. The centerline of the search unit shall be at least 1-1/2 inches from the nearest corner formed by tude at a longer side of the calibration block. Rotating the beam into the the hole and the side of the block may produce a higher ampli-beam path. Th.is beam path shall not be used. The type and length of the :search unit cable shall be recorded on the SwRI Instrument Calibration Record and all other information blocks on this form shall be filled in. When the examination is to be performed from the outside surface of a clad vessel, the calibration shall be accomplished from the unclad surface of the basic calibration block. 6.3.l Strai~ht-Beam Distance Calibration Position the search unit on the appropriate reference block, observe back reflections and adjust the instrument controls to ensure a linear sound path distance along the screen baseline. Select the shortest screen dis-tance size which will include at least l/4t beyond the nominal material thick-ness. The screen sizes shall be selected from the following: 2.5", 5.0", 10.0" or 20.0". 6.3.2 An~le-Bearn Distance Calibration Position the search unit on the appropriate reference block, observe the radius echoes and adjust the instrument controls to ensure a linear sound path distance along the instrument.screen baseline. Select the shortest screen distance size which will include at least 1/8 vee-path beyond the SwAI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE ISL._
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IV/ // NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-48 Revision 1 November 1988 Page 7 of 16 anticipated examin~tion range. The screen sizes shall be selected from the following: 5.0", 10.0", 20.0" or 40.0". 6.3.2.l Screen Distance Calibration for 45° and 60° When Using the Same Instrument (1) The screen distance size shall be determined by the angle-beam requiring the longer examination range. (2) Construct a linear screen as specified in paragraph 6.3.2 utilizing the 45° search unit. (3) Record reference block data required on the Calibration Record. (4) Without changing the instrument DELAY and MAT'L CAL controls, position the 60° search unit on the reference block and record the reference block data required on the Calibration Record. 6.3.3 Straight-Beam DAC (1) Position the search unit on the basic calibration block to obtain maximum response from the calibration hole selected from the following that will produce the highest amplitude: l/4T l/2T 3/4T (2) Set the response to the primary reference level of 807. +/-5% of FSH and mark its amplitude on the instrument screen. (3) Without changing the gain controls, obtain maximum response from the remaining holes; mark and join all amplitude points with a smooth curved line. Record these gain settings under the REM.A.RKS section of the Calibration Record. 6.3.4 Angle-Beam DAC from the Clad Side or on Nonclad Blocks (1) Position the 45° search unit on the basic calibration block to obtain maximum :iaesponse from the calibration vee-path position selected from the following which will produce the highest amplitude: SwAI Form QA 3*2
SwRI-NDT-600-48 SOUTHWEST RESEARCH INSTITUTE Revision 1 November 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 of 16 Vee-Path Position 1/8, 2/8, 3/8, 5/8, 6/8, and 7/8 (2) Set this signal to the primary reference level of 80% +/-5% of FSH and mark its amplitude on the instrument screen. (3)
- Yithout changing the gain controls, obtain maximum response from the remaining vee-path positions; mark and join all amplitude points with a smooth curved line which shall extend 1/8 vee-path past the last qualified calibration poi~t.
(4) Yi th the instrument gain set at the* reference level, obtain maximum amplit~de from the square notch on the opposite sur-face (4/8 vee-path), and from the square notch on the same surface (8/8 vee-path). Mark each amplitude with an X. The indications from these notches must be considered when evalu-ating reflectors at the respective surfaces. (5) Repeat steps (1) through (4) with the 60° search unit utiliz-ing the following vee-path positions: Vee-Path Position 1/8, 2/8, 3/8 and 5/8 EXCEPTION The amplitude from the square notch on the same surface (8/8 vee-path) is not required and shall not be used. 6.3.5 Angle-Beam DAG from the U~clad Side of Clad Blocks HalF-Vee Calibration (1) Position the 45° search unit to obtain maximum response from the calibration vee-path position selected from the follow-ing, that produces the highest amplitude: 1/8, 2/8, or 3/8. (2) Set and mark this signal amplitude to the primary reference level of 80% +/-5% of FSH on the instrument screen. (3) without ~hanging the gain controls, obtain maximum .restronse from the remaining vee-path positions and mark each amplitude SwRI Form QA 3-2 on the instrument screen.
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT~600-48 Revision 1 November 1988 Page 9 of 16 (4) Position the search unit on the clad side of.the block.
- Determine the dB difference betwee.n the 3/8 and 5/8 vee-path.
Mark the location of the 5/8 vee-path on the instrument baseline. (5) Position the search unit on the unclad side of the block. Set the instrument gain controls to the primary reference level established in step (2) and obtain the maximum response from the 3/8. (6) Decrease the signal from the 3/8 by the dB difference deter-mined in step (4). Mark the amplitude of this signal at the location of the 5/8 determined in step *(4). Join the marks on the instrument screen to construct the DAG curve. (7) With the instrument gain set at the primary reference level, position the search unit to obtain maximum amplitude from the square notch on the opposite surface. Mark the signal ampli-tude with an X. The indication from this notch must be con-sidered when evaluation reflectors at the opposite surface. (8) Repeat steps (1) through (7) using a 60° search unit. 6.3.6 Beam Spread and Beam Angle Determination Each angle-beam search unit used shall be measured for beam spread and beam angle after the initial calibration, once prior to and once after the completion of all weld examinations performed during one outage. Beam spread and beam angle for calibration shall be determined by recording the distance to the W1 50% DAG and 20% DAG points, Wmu point, and W2 50% DAG and 20% DAG points for each calibration reflector as follows: (1) With the instrument at the primary reference level sensitiv-ity, position the search unit for maximum amplitude from the l/4T hole (Wmax). Measure and record the distance from the incident point of the search unit to the scribe line above the l/4T hole. (2) Repeat step (2) recording the distance to the scribe line for both the l/2T and 3/4 T maximum amplitudes. (3) Position the search unit to obtain maximum amplitude from the l/4T hole. Move the search unit toward the hole until the indication equals 50% and 204 DAG. Measure and record the distance from the incident point of the search unit to the scribe line above the l/4T hole (T..11 ) . SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJE.CTS OPERATING PROCEDURE SwRI-NDT-600-48 Revision 1 November 1988 Page 10 of 16 (4) Move the search unit away from the hole until the indication equals 50% and 20% DAC. Measure and record the. distance from the incident point of the search unit to the scribe line above the l/4T hole (W2 ). (5) Repeat steps (4) and (5), recording the measurements for the 2/8 and 3/8 vee-path posttions (l/2T and 3/4T holes) at 50% and 20% DAC; for the 5/8, 6/8, and 7/8 vee-path positions at 20% DAC only. ( 6) Plot the 1/8, 2/8, and 3/8 points on a scale* drawing of the basic calibration block or on the graph on 'the back of the SwRI Beam Spread Record. When plotting Ws> place the points at the appropriate depth (1/4!°, l/2T, or 3/4T) .. (7) Draw a separate line to each of the Wmax points from the inci-dent point of the search unit. (8) The angle to each of the points shall be measured using a protractor. The beam angle shall be established by determin-ing the average of the three 100% DAC line Wniax angles meas-ured. This is the effective angle which shall be recorded on the SwRI Beam Spread Record and considered during resolution of indications. (9) Connect the three 50% and 20% DAG line W1 and W2 points extending these lines to the search unit drawn-at the top of the graph. Repeat this operation for the 20% DAG line W1 and W2 points. If the three W1 or W2 points do not form a straight line, then a line representing the average of the l/2T and 3/4T holes only shall be drawn and extended until they cross, unless one of the points is- obviously misplaced due to the clad effect (these points must be projected along the same beam path on the block drawing to complete this task). (10) Measure the. angle between the 50% W1 line and W2 line. This is the angle of the 50% DAG beam spread. Measure the angle between the 20% W1 line and W2 line. This is the angle of the 20% beam spread_ SwAI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-48 Revision 1 November 1988 Page 11 of 16 6.4 Calibration Veri'fication 6.4.l Sweep Range and DAC Curve Verification The sweeR range calibration shall be verified on the appropriate reference block. The DAC curve calibration (if applicable) shall be verified on the basic calibration block:
(1) Prior to a series of examinations (2) With any substitute of the same type and length of search unit cable (3) With any substitute utilizing the same type of power source; e.g., a change of batteries (4) Whenever the validity of the calibration is in doubt
- 6.4.2 (5)
(6) At least every 4 hours during examination At the completion of a series of examinations Calibration Changes (1) Perform the following if any point on the DAC curve has moved on the sweep line more than 10% of the sweep division reading: (a) Correct the calibration and record the change on the calibration record. (b) If indications have.been recorded with this calibration, the examination record shall be voided, a new calibra-tion performed, and* the areas for which examinations have.been voided reexamined. (2) Perform the following if any point on the DAG curve has increased more than 207. or 2 dB in amplitude: (a) Correct the calibration and record the change on the calibration record. (b) Reexamine indications recorded since the last valid calibration verification . SwAI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEOURE SwRI-NDT-600-48 Revision 1 November 1988 Page 12 of 16 (c) If any point on the DAC curve has decreased 20% or 2 dB or more in amplitude, all applicable data sheets shall be voided, a new calibration performed and the area for which examinations have been voided reexamined. 6.4.3 Recalibration Substitution of any of the following shall be cause for recalibration: (1) Search unit wedge or transducer (2) Ultrasonic instrument (3) Examination personnel (4) Couplant (5) Change.in type of power source; e.g., change from direct to alternating current
- 7. EXAMINATION 7.1 Surface Condition The contact surfaces must be free from weld spatter, roughness, or other conditions which interfere with free movement of the search unit or impair the transmission of ultrasound.
7.2 Examination Volume Examination volume shall b.e the weld and adjacent base material for a distance of l/2t from the fusion line on each side of the longitudinal and circumferential butt welds, and th.e weld and l/2t of base material on the vessel side of the weld for nozzle-to-shell butt welds. In cases where the weld crown is on the inside surface, the l/2t distance shall be based upon l/2t from the fusion line of the weld crown. 7.3 Reference Points Reference points for physical measurements shall be in accordance
- with the applicable revision of SwRI Procedure IX-FE-125.
SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE, NUCLEAR.PROJECTS OPERATING PROCEDURE SwRI-NDT-600-48 Revision 1 November 1988 Page 13 of 16 7.4 Scanning _Parameters T,.lhen practicable, scanning shall be performed at 5 *times but not less than 2 times the reference level sensitivity. If 2 times *reference level is not possible, the limitation shall be recorded.
The search unit movement rate for scanning shall not exceed 6 inches per second. Scanning overlap shall be a minimum of 50% of the search unit piezoelectric element dimension perpendicular to the direction of scan. 7.4.1 Base Material Lamination Scan A lamination' scan using straight-beam shall be performed, covering the entire area through which the angle-beam passes. Scanning shall be per-formed at a gain setting that gives an initial backwall amplitude of 80% +/-5. % FSH . EXCEPTION If performed previously, a lamination scan is not required except in the area(s) where a lamination was previously recorded. 7.4.2 Thickness Measurements Thickness measurements shall be taken on the centerline of the weld and at one point in the base material on each side of the weld for circumferen-tial and longitudinal welds, and at one point in the base material on the vessel side adjacent to the weld for nozzle~to-shell welds. These measurements shall be recorded on the appropriate examination record. 7.4.3 Straight-Beam Weld Examination A straight-beam examination shall be applied to the surface of the weld crown and l/2t of the ~ase material on each side of the weld for circum-ferential and longitudinal welds, and on the weld crown and l/2t of base mate-rial on the vessel side of the weld for nozzle- to-she'll welds. 7.4.4 Angle-Beam Examination for Indications Parallel with the Weld First half-vee examinations shall be accomplished by using the 45°and 60° search units for l/2t on each side of the weld for circumferential and longitudinal welds, anti from the vessel side of the weld for nozzle-to-shell
- welds. r..7hen examinations are conduc~ed from the clad surfaces or on nonclad components, the 45° shall be extended to the second half-vee to detect near SwRI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-48 Re.vision 1 November 1988 Page 14 of 16 surface indications. This examination shall be performe4 by directing the sound beam perpendicularly into the weld to detect indications. parallel with the weld. 7.4.5 Angle-Beam examination for Indications Perpendicular to the geld First half-vee examinations shall be accomplished by using the 45° and 60° search units. When examinations are conducted from the clad surfaces or on nonclad components, the 45° shall be extended to the second half-vee to detect near surface indications. This examination shall be performed by direct-ing the sound beam into and parallel with the weld to detect indications perpen-dicular with the weld. The length of the weld and l/2t of base material on each side of the weld for circumferential and longitudinal welds, and the weld and l/2t base material on the vessel side of .the weld for nozzle~to-shell welds shall be scanned with the search unit sound beam directed in this manner from two opposing dir~ctions.
- 8. RECORDING AND SIZING It is recognized that not all ultrasonic reflectors indicate flaws; certain metallurgical discontinuities and geometric conditions may produce indications that are not relevant. Included in this category are plate segregates in the heat-affected zone, clad interface, and backwall reflections. Plate segregates may become reflective after fabrication, and may appear as spot or line indica-tions when examined with straight-beam techniques. These indications shall not be considered recordable conditions.
8.1 General Recording Criteria Indications shall be recorded utilizing the techniques outlined in the applicable revision of SwRI Procedure IX-FE-125. Ultrasonic planar surface reflectors obtained at 50% or greater of the response from the square notch s*hall be recorded. Indications determined to be caused by geo~etry shall be recorded at 50% DAC or greater. The basis for this determination shall be described. Further recording and evaluation of geometric indications will not be required. Additionally, any nongeometric indication shall be recorded at 20% DAC or greater. Indications not resolved as geometry shall be .recorded along the length and width in scan increments no greater than 1/4 inch. The recorded information shall include the indication metal path, the search unit position for 20%, 50%, and 100% DAC, and the maximum amplitude of the signal for indica-tions at or within the inner 25% of the through-wall thickness of the vessel wall as measured from the inside surface,_ and the metal path, the search unit SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-48 Revision 1 November 1988 Page 15 of 16 position for 50% and 100% DAG, and maximum amplitude of the signal for indica-tions withiri the outer 75% of the through-wall dimension.
When an examination is performed from the unclad side of a clad v*essel, indications observed past the 4/8 vee-path shall not be recorded. Straight-beam indica-tions whose length and depth from the surface are oriented within 10° of a plane parallel to the surface of the component, shall be considered laminar flaw. 8.2 Recording and Evaluation Criteria Nonlaminar straight-beam indications considered as planar shall be size~ to the-507. DAC limits. Planar indications within the outer 75% of the through-wall thick-ness of the vessel wall measured from the inside sur~ace shall be recorded and investigated at 50% DAG . 8.2.1 Angle-Beam Indications with Changing Metal *Path Indications within the inner 2;5% of the through-wall thickness that change metal path distances on the horizontal baseline of the instrument screen
*for a distance greater than indications from the calibration holes (at 20% DAG amplitude) shall be recorded and sized at 20% DAG. When the indication is sized at 20%, this size may be corrected by subtracting the beam width in the through-thickness direction obtained from the calibration hole (betw*een 20% DAG points) that is at a depth at or near the flaw depth. If the indication exceeds 50%,
the size shall be recorded by measuring the distance between 50% points and between the 20% points as corrected. The determined size shall be the larger of the two. 8.2.2 Angle-Beam Indications Without Changing Metal *Path Indications that do not change metal path and continue for a scan-ning distance of more than 1 inch located within the outer 75% of the through-wall thickness shall be recorded and investigated at 50% DAG. If the indication falls within the inner 25% of the through-wall thickness, it shall be recorded at 20% DAG and investigated at 50%.
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI personnel, and shall be conducted in accordance with the applicable ASME Boiler and Pressure Vessel Code, Section XI, IWA-3000. Final evaluation and disposi-tion of reportable indications shall be the responsibility of the customer.
SwRI Form QA 3-2
SwRI-NDT-600-48 SOUTHWEST RESEARCH .INSTITUTE Revision 1 _ November 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 16 of 16
- 10. RECORDS Documents generated in accordance with this procedure shall be stored as specified in the Project Plan. The customer shall receive copies of these docu-ments in the Examination Report, unless specified otherwise in the SwRI Project Plan.
SwRI Form QA 3-2
PROCEDURE DEVIATION Page 1 of 1 Pages Procedure - Revision No. I Deviati~n No. Sw:Rl-NDT- 600-49 1 1 The following examination areas are affected by this deviation: Examinations performed i~ accordance with this procedure. The foilowing para9raphs shall be deviated from as indicated: Paragraph 3.l Change the SwRI-NDTR Form No. 17-18 from the 7-31-75 edition to the 3-14-79 edition. Add to last paragraph 6.2.2(3) Verification of Calibration Reflectors at Scanning Speed The examiner shall verify the prese11ce of the calibration reflector at scanning speed. It is not necessary to assure that this check confirms the signal amplitude at 100~ of reference level, but merely to demonstrate that the signals from the calibration reflectors are readily observable at scanning speed. The following statement shall be documented on the SwRI Sonic Instrument Calibration Record and initialed: "Calibration reflectors have been verified at scanning speed." Rationale for deviation: This deviation incorporates customer *request to verify the presence of calibration reflector under procedural scanning conditions and changes revision of data sheet.. If the deviation is determined :o affec: the procedure Deviation Affects Qualification YES 0 NO (iJ qualification, the deviation shall be Qualified in accordance with Procedure IX*FE-107. APPROVALS Date: DatE;:
.:~6-ii..'i
(' i/ ' I Date: I ' Verbal App'roval Given? 0 Yes t8J No Ma~er of Q.A.: ~ Date: Cognizant Director: Date: Jc.--Jti~ :z/10/s1 ~~j;(~ SwAi FCRM FE-4-6
~SOUTHWEST RESEARCH. llliSTITUTE SwRI-NDT-600-49 Revision 1 NUCLEAR PROJECTS August 1988 OPERATING PROCEDURE Page 1 of 12 Title MANUAL.ULTRASONIC EXAMINATION USING LONGil'UDINAL-WAVE STRAIGHT-BEAM TECHNIQUES EFFECTIVITY AND APPROVAL Revision 1 of this procedure became effective on Aug 26, 1988 Other- revisions of the base document may be effective concurrently.
SA Approvals ~ fi.J) Written By
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Date 1 lS"{t~,JY 1"'°'
. ~(j""w- lJjQ /~Ji_ ~~-*~ZZ:
a ~ (} . ~ d' Date s---2~-?.Y' Manager of Q.A.7~-1.. Date Cognizant pirector . Date
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The following information may be used for convenience. Completion of this portion is not mandatory. Deviation No. Date Effective Procedure Section(s) Affected Notes: I SwRI Form QA*40A*O
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 August 1988 Page 2 of 12 MANUAL ULTRASONIC EXAMINATION USING LONGITUDINAL-WAVE STRAIGHT-BEAM TECHNIQUES SwRI-NDT-600-49
- 1. PURPOSE This procedure provides information and detailed steps neces~ary to perform an accurate ultrasonic examination when longitudinal straight-beam techniques are required by the applicable American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code.
- 2. SCOPE AND APPLICATION 2.1 Materials and Product Forms This procedure shall apply to full penetration butt welds and adja-cent base material in wrought ferritic and austenitic steels. The weld and base material may be either clad or unclad.
2.2 Thickness Range This procedure shall apply to base materials and welds in the nominal thickness range of 0.2 inch to 12.0 inches. 2.3 Ultrasonic Technique The ultrasonic technique used with this procedure shall be manual, pulse-echo contact using longitudinal-wave straight-beam search units. This procedure shall apply to the examination of components for laminations and/or planar flaws when required by the applicable SwRI Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1980 Edition with Addenda through Yinter 1981 and 1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclear Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1980 Edition with Addenda through Yinter 1981 and 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 August 1988 Page 3 of 12 (3) SwR~ Nuclear Quality Assurance Program (NQAPM) 3 .*l Calibration and Examination Records SwRI-NDTR Form No. Revision Date 17-17 09-04-84 17-18 07-31-75 17-19 12-01-83 17-135 03-24-88
- 4. RESPONSIBILITY (1) The Director of the Department of NDE Services, Nondestructive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in.accordance with the NQAPM specified in the appli-cable SwRI Project Plan. (3) The examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Quality Assurance Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing ultrasonic examinations shall be certified in.
accordance with SwRI NQAP 11-1, "Spec.ial Process Contra 1. " 5.2 Reference'Block Reference blocks used for screen distance calibration and verifi-cation shall be of the same material as the production material; i.e., stain-less steel or carbon steel, and shall be one of the following: (1) SwRI Half Round, (2) AWS Type DC, (3) IIW, or (4) Rompus Block . SwRI Form QA 3-2 I_
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 August 1988 Page 4 of 12 Reference blocks shall be used as follows for screen distance calibration: Screen Block Distance Block Type Dimension 0.5" AYS Type DC 0.5" 1.0", 2.0" S;oRI Half-Round 1.0" AYS Type DC 0.5" or 1.0" IIW 1.0" ROMPAS 1.0" flat 2.5", 5.0" SwRI Half-Round 1.0" AYS Type DC 1.0" IIW' 1.0" ROMPAS 1.0" flat 10.0" and greater IIW 4.0" 5.3 5.4 Basic Calibration Block The basic calibration blocks to be used with this procedure shall be described in the SwRI Examination Plan. Search Units Search units shall be selected from the following: Average Weld Thickness Nominal Search Unit Size 2.0" or less 1/4" round or 3/8" round over 2.0" to 3.0" 1/2" round over 3.0" to 12.0" 3/4" round or l" round The nominal search unit frequency for ferritic materials shall be 2.25 MHz and 1.5 MHz for austenitic materials except when 1/4-inch search units are used in which case a nominal frequency of 2.25 MHz shall apply. 5.5 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1. SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 Augus*t 19 8 8 Page 5 of 12 5.6 Couplant (1) USP-grade glycerine or reactor grade water shall be used*
when performing ultrasonic calibrations.and examinations in accordanc~ with this proce.dure. (2) All couplant materials, except 'reactor grade water, shall be certified for sulfur content and total halogens. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Reactor grade water, when used, shall be supplied by the customer. (3) Couplant materials used for examinations shall be the same as used for the calibration. 5.7 Thermometer The thermometer to be used for measuring the calibration.block and component temperatures shall be calibrated and certified and shall display a valid calibration tag as required by NQAP 10~1.
- 6. CALIBRATION METHOD 6.1 The ultrasonic calibration shall be completed prior to the examination.
The centerline of the search unit shall be at least 1-1/2 inches from the nearest side of the calibration block. The REJECT control shall be maintained in the 0 position during calibration and examination. The FREQ MHZ control shall be turned to 2 when a 2.25-MHz search unit is used, and .to 1 with a 1.5-MHz search unit. 6.1.1 Temperature The calibration block temperature shall be within 25°F of the component temperature and shall be recorded bn the SwRI Sonic Instrument Cali-bration Record for the initial calibration and each verification. The surface temperature of the component to be examined shall be taken prior to and after performing each examination and shall be recorded on the applicable SwRI Exami-nation Record .
- SwR I Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 August 1988 Page 6 of 12 6.2 Calibration for Distance-Amplitude-Correction 6.2.1 Observing back.reflections~from the applicable reference block, obtain the necessary sound path distance along th~ CRT baseline. The minimum sound path distance shall be the shortest distance that includes at least .l/4t past the nominal material thickness. Screen distance shall be selected from one of the distance specified in Paragraph 5.2. 6.2.2 Distance-amplitude curves shall be constructed using the responses from the basic calibration holes. (1) Position the search unit to obtain a peak amplitude response from the calibration hole selected from the following, that produces the highest amp~itude. Calibration Hole Location l/4t l/2t (2) (3) 3/4t Set this signal to a primary reference level of 80% +/-5% FSH. Mark the amplitude and metal path distance on the CRT. Without changing the gain controls, obtain a peak amplitude response from the remaining calibration hole locations; mark and join all amplitude points with a smooth curved line which shall be extended through the thickness. 6.3 Calibration for Lamination Scan 6.3.1 Sound path distance calibration shall be as described in 6.2.1. 6.3.2 Instrument gain controls shall be adjusted to produce an initial back reflection amplitude of 80% +/-5% FSH. 6.4 Calibration Verification 6.4.l Sweep Range and Distahce-Amplitude Calibration Verification Sweep range and distance amplitude calibration shall be verified on the appropriate reference and basic calibration block when any of the follow-ing occurs: (1) Prior to a* series of examinations SwAI Form QA 3-2 (2) ~ith any substitution of the same type and length of search unit cable
- SOUTH.WEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 August: 1988 Page 7 of 12 (3) With any subst:itution utilizing the same type of power source; e.g., a change of batteries (4) At least every 4 hours during the examinat:ion *
(5) At the completion of a series of examinations (6) Whenever the validity of the calibration is in*doubt 6.4.2 Calibration Changes (1) Perform the following if any point on the DAC curve has decreased 20% or 2 dB or more in amplitude, of if any point on the DAC has moved on the sweep line more than 10% of the screen reading or 5% of full screen, whichever is greater: (a) . Void all examinations referring to the calibration in question and performed after the last valid calibration verification. (b) Conduct a new calibration. (c) Reexamine the areas for which examination have been voided. (2) Perform the following if any point on the DAC curve has increased in amplitude more than 20% or 2 dB: (a) Correct the calibration. (b) Reexamine all indications recorded since the last valid calibration verification. (c) Enter proper values on a new SwRI Examination Record. 6.4.3 Substitution of any of the following shall be cause for recalibrat:ion. (1) Search unit wedge or transducer (2) Search unit cable type or length (3) Ultrasonic instrument: (4) Examination personnel (5) Couplant SwRI Form QA 3-2
SOUTHWEST RESEAHCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 August 1988 Page 8 of 12 ( 6) Change in type *of p~wer source; e.g. , a change from direct to alternating current
- 7. EXAMINATION 7.1 Examination Volume 7.1.1. Weld Profile If necessary to determine the required examination volume for pipe weld examination, inside surface and outside surface profiles shall be taken on each weld at the Lo location as a minimum.
Profiles shall consist of ultrasonic thickness measurements and outside surface contours using a contour gage. Thickness measurements shall be taken*at a maximum interval of 1/4 inch and shall cover the material volume for a distance of 2t from the weld fusion line on each side of the weld. The "t" dimension shall be the nominal pipe wall thickness. Outside surface pro-files shall cover the same distance as the thickness measurements. Weld pro-files shall be documented on the SwRI Profile and Thickness Information Record. 7.2 Examination Vo1ilme for Planar Reflectors 7.2.l Butt Yelds in Vessels In Class 1 vessels, the examination area shall be the weld and adjacent base material for a distance of l/2t from the fusion line on each side of the weld for longitudinal, circumferential butt, and tube sheet-to-head welds, and the weld and l/2t of base material on each side of the weld for nozzle-to-vessel butt welds. In cases where the weld crown is on the inside surface, the l/2t distance shall be based upon l/2t from the fusion line of the weld crown. 7.2.2 In Class 2 vessels, the examination area shall be the weld and adjacent base material for a distance of 1/2 inch from the fusion line on each side of the weld for circumferential butt and tube sheet-to-head welds. The examination area for nozzle-to-vessel welds shall be the weld and base material for 1/3t from the inside surface of the vessel including 1/4 inch of base material on each side of the weld. In cases where the weld crown is on the inside surface, the 1/4-inch distance shall be based upon 1/4 inch from the fusion line of the weld crown. SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1
~ugust 1988 Page 9 of 12 A detailed scale drawing should be obtained to determine the exact weld con-figuration for circumferential and meridional welds in spherical Class 1 vessel heads. In cases where the weld crown is on the inside surface and the examina-tion is to be performed from the outside surface, the examiner shall determine the l/2t examination area based upon the l/2t distance on the inside surface.
7.3 Examination Volume for Laminar Reflectors Prior to initial angle-beam examination of vessel welds or piping welds, the base material through which the angle~beams will travel shall be scanned for laminar reflectors which could affect the interpretation of angle-beCl.Ill results. If performed during a PSI or prior ISI, an exainination for laminar reflectors is not required except where laminar reflectors have been previously recorded .
- 7.4 Surface Condition The contact surfaces shall be free from weld spatter, roughness, or other conditions which interfere with free movement of the search unit or impair the transmission of ultrasound.
7.5 Indication Length Zero Reference (Lo) Location Areas to be eXB.\Ilined in accordance with this procedure shall have an Lo marked in accordance with the applicable revision of SwRI Procedure IX-FE-103 for piping and IX-FE-118 for vessels; 7.6 Scanning for Planar Reflector 7.6.1 When practicable, scanning shall be performed at a minimum gain setting of 2 times the reference level sensitivity. 7.6.2 Instrument gain setting for scanning shall be determined on the basic calibration block as follows for each primary reference level utilized: (1) Yith the instrument at the primary reference level, manipu-late the search unit on the basic calibration block to obtain a signal of 40% of FSH from a calibration reflector (side-drilled hole) .
- Swnl Form QA 3*2
SOUTHWEST RESEARCH l.NSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 August 1988 Page 10 of 12 (2) Add 6 dB gain by utilizing the 6 dB switch (if present), the fine gain control, or a combination of the fine and coarse gain controls and choose any method that yields a signal response within +/-2 dB of 80% FSH. (3) This amplitude and method shall be recorded on the SwRI Sonic Instrument Calibration Record and shall be used during the valid calibration period for all scanning at 2 times the reference level sensitivity. 7.6.3 Scanning overlap shall be a minimum of 10% of the search unit piezoelectric element dimension perpendicular to the direction of the scan. 7.6.4 The search unit movement rate shall not exceed 6 inches per second. 7.7 Scanning for Laminar Reflector
- 7. 7 ..1 Scanning overlap shall be a minimum of 10% of the search unit piezoelectric dimension perpendicular to the direction of the scan .
7.7.2 7.8 The search unit movement rate shall not exceed 6 inches per second. Examination of Vessel Welds for Planar Reflectors The examination shall be conducted from the inside or outside surface of the vessel and shall cover the entire required volume of weld and base material as defined in Paragraph 7.1. 7.9 Examination of Vessels and Piping for Laminar Reflectors The examination shall be conducted from either the outside or inside of vessels and from the outside surface of piping.
- 8. RECORDING CRITERIA Indications shall be recorded in accordance with the applicable revision of IX-FE-118 or IX-FE-117 as applicable.
8.1 Planar Reflectors 8.1.1 Record all reflectors that produce a response equal to or greater than 50% of the DAC.
- 8. l .*2 The following data shall be recorded for reflectors equal to or greater than 50% DAC but less than 100% DAC.
SwA I Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1 August 1988 Page 11 of 12
% 50% DAC y MAX 50% DAC .L Lz Search Search of Unit Unit DAC 50% MAX 50% Loca- Angle DAC DAC ti on 8.1.3 The following data shall be.recorded for reflectors equal to or greater than 100% DAC:
% 1/2 MAX Y MAX 1/2 MAX L Lz s.u. I s.u.
of Yzl MP 50% DAC MAX 50% DAC Location Angle DAC I 8.2 Recording Laminar Reflectors for Interference
- 8.3 All areas giving indications equal to *or greater than the remaining back reflection shall be recorded.
Recording Laminar Reflectors for Acceotance All areas giving a continuous total loss of back reflection accom-panied by continuous indications in the same plane shall be recorded. 8.4 Data Required for Laminar Reflectors The following data shall be recorded for each laminar reflector:
% Ind Position 1 Position Position Position 2 Loss Amp Search of % Unit BW F.S. Location I
It is recognized that not all ultrasonic reflectors indicate flaws; certain metallurgical discontinuities and geometric conditions may produce indications that are not relevant. Included in this category are plate segregates in the
*heat-affected zone, clad interface, and backwall reflections. These indications shall not be considered reportable conditions.
SwRI Form QA 3*2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJE<!TS OPERATING PROCEDURE SwRI-NDT-600-49 Revision 1
-August 1988 Page 12 of 12 8.5 Recordable indications not attributable to geometry shall be compared with the flaw indication characterization rules and acceptance stan-dards of IWA-3000, and shall be reported to' the customer.
8.6 Scanning limitations shall be recorded.
- 9. EVALUATION Initial evaluation of reportable indicacions shall be performed by SwRI personnel. Final disposition of reportable indications shal~ be the respon-sibility of the customer;
- 10. RECORDS Documents generated in accordance with this procedure shall be stored as specified in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan.
SwRI Form QA 3-2
SwRI-NDT-800-lOt;
~ SOUTHWEST RESEARCH INSTITUTE Revision 2 NUCLEAR PROJECTS December 1987
. OPERATING PROCEDURE Page 1 of 10 Title INNER SURFACE EXAMINATION OF THE ACCESS HOLES IN PRESSURE-RETAINING STUDS 2 INCHES AND GREATER IN DIAMETER EFFECTIVITY AND APPROVAL Revision 2 of this procedure became effective on Dec 21 , 1987. Other revisions of the base document may be effective concurrently.
SA Approvals fW . sv ~ ~e 1=T~c rJdt_J~.zzruT written Date Date **-
~~ 17 DtU.# /7 l)c:c i7
\({S1 Manager of Q.A~ Date Cogni ~t Director Date r:U:e#,£L '-£ nr 1z!1Jj.P7 'ii /Ufftl/ - f _i!tttt' 1 J/J1/r1 tJ / .
The following information may be used for convenience. Co
,J - I letion of this portion is not mandatory.
Deviation No. Date Effective Procedure Section(s) Affected Notes:
- SwRI Form QA-40A*O
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPESATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 2 of 10 INNER SURFACE EXAMINATION OF THE ACCESS HOLES' IN PRESSURE-RETAIN°ING STUDS *2 INCHES AND GREATER IN DIAMETER SwRI-NDT-800-104
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure a proper ultrasonic examination of the surface of the access holes in pressure-retaining studs in accordance with the applicable American Society of_ Mechanical Engineers (ASME) Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION (1) The surface of access holes in pressure-retaining stud;s 2. 0 inc.hes and greater in diameter shall be examined as specified in the applicable Southwest Research Institute (SwRI) Examination Plan.
(2) High-angle.longitudinal, manual, contact pulse-echo ultrasonic exam-ination techniques utilizing the SwRI Manual Stud Longitudinal Exam-ination Probe shall be used to locate inner surface flaws that are oriented perpendicular to the axis of the stud. (3) In order to comply with the requirements of Code Case N-307-1, an ultrasonic shear-wave examination of the threaded and unthreaded outside area shall be performed with the applicable SwRI Nuclear Projects Operating Procedure. 3.* APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, -1983 Edition with Addenda through Summer 1983, "Rules for Inservice Inspection of Nuclea~ Power Plant Components" (2) ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition with Addenda through Summer 1983, "Nondestructive Examination" (3) ASME Boiler and Pressure Vessel Code, Case N-307-1 (4) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Applicable Calibration and Examination Records SwRI NDTR Form No. Revision Date 17-19 12-01-83 17-27 2-03-82 17-37 2-18-80 SwRI Form QA 3-2
- - SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 3 of 10
- 4. RESPONSIBILITY
- Cl) The Director of th~ Department-of Engineering Services, Nondestruc-tive Evaluation Science and Technology Pivision, shall be respon-sible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan. (3) The*examiner shall be responsible for implementing the requirements of this procedure. (4) The Manager of the Support and Admi~istration Section, Nondestruc-tive Evaluation Science and Technology Division, shall be respon-sible for storage of records generated in accordance with this procedure .
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-1, "Special Process Control."
5.2 Basic Calibration Block The basic calibration block shall be fabricated from material of the same material specification, product form, and heat treatment as the compo-nent to be examined. It shall be threaded as the component and have an access hole equal in size to that of the component to be examined. The basic calibration reflector shall be a notch machined one thread deep, or 1/8-inch deep, whichever is smaller. The notch shall be placed on the inside surface on the access hole . . The particular notch utilized for the calibration shall be identified on the SwRI Sonic Inst'!'UI!lent Calibration Record. Approved drawings of the basic calibration block are contained in the applicable SwRI Examination Plan. 5.3 Search Units (1) The search unit shall have an active element size of 1/4 x 1/4 inch or 1/4 inch round .
- SwRI Form QA 3-2 (2) A special search unit wedge shall be used to produce a high angle longitudinal wave. The nominal search unit angle is 88°.
SOUTHWEST RESEARCH *INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 4 of 10 (3) The nominal search unit frequency shall be 2.25 MHz. (4) The exit point shall be the scribe line made on the wedge during fabrication: If the exit point is not marked or undis-cernible, it shall be dete*rmined ~s follows: The signal from the end of a calibration block or a near surf ace notch shall be maximized. The exit point will be at*the near side of the notch on the edge of the calibration block. 5.4 Ultrasonic Instrument The examiner shall use a Sonic FTS Mark I ultrasonic instrument which shall be aligned and shall display a valid alignment calibration tag as required by NQAP 10-1.
?.5 Couplant (1) USP-grade glycerine or reactor grade water shall be used when performing ultrasonic calibrations and examinations in accor-dance with this procedure.
(2) USP-grade glycerine shall be certified for sulfur content and total halogens in accordance with SD-129 and SD-808 of Arti-cle 24, Section V. The residual amount of total sulfur or halogens shall not exceed 1% by weight. Reactor grade water, when used, shall be supplied by the customer. (3) Couplant materials used for examinations shall be the same as used for the calibration. 5.6 Thermometer The thermometer to be used for measuring the calibration block and component temperatures shall be calibrated and certified and shall display a valid calibration tag a~ required by NQAP 10-1.
- 6. CALIBRATION 6.1 Instrument Linearity Ultrasonic instrument linearity shall be verified prior to each period of extended use or every three months, whichever is less, in accordance with Paragraphs 6.1.l and 6.1.2. Data required shall be recorded on the SwRI Instrument Linearity Verification Record and the sheet number shall be refer-enced on each applicable SwRI Sonic Instrument Calibration Record.
SwAI Form QA 3-2
- SOUTHWEST RESEARC.H INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 5 of 10 The setting of the damping control shall be recorded in REMARKS on the SwRI Instrument Linearity Verification Record. The damping control shall be in* the same position during linearity verification, calibrations and examinations or a new linearity verification shall be performed.
6.1.1 Screen Height Linearity (1) Position a shear-wave search unit on a calibration block to obtain indications from the l/2T and 3/4T holes or use a straight-beam search unit on any calibration block that pro-vides amplitude differences. (2) Adjust the search unit position to give a 2:1 ratio between two indications, with the larger indication set at 80% of full screen height (FSH) and the smaller indication at 40% of FSH. (3) ~ithout moving the search unit, se the larger indication to 100% of FSH; record the amplitude of the smaller indication, estimated to the nearest 1% of FSH. (4) Successively set the larger indication from 100% to 20% of FSH in 10% increm:ents (or 2 dB steps if a fine control is not available); observe and record the smaller indication estimated to the nearest 1% of FSH at each setting. The reading must be 50% of the larger amplitude within 5% of FSH. 6 .1.2 Amplitude Control Linearity (1) Position an angle-beam or a straight-beam search unit on a calibration block to obtain maximum amplitude from an appli-cable reflector. The primary reference level sensitivity should be within the highest and lowest gain settings used during amplitude control linearity verifications. The highest and lowest gain settings used during the amplitude control linearity verifications shall be recorded in the Remarks column of the applicable SwRI Linearity Verification Records. (2) ~ithout moving the search unit, set the indication to the required percent of FSH and increase or decrease the dB as specified below. The estimated signal shall be recorded to the nearest 1% of FSH and shall fall within the limits of the following table: SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 6 of 10 Indication dB Control Indication Set at % of FSH . Change* Limits. % of FSH 80% -6 dB 32 to 48%* 80% -12 dB 16 to 24% 40% + 6 dB 64 to 96% 20% +12 dB 64 to 96%
*Minus denotes decrease in amplitude; plus denotes increase.
6.2 Calibration Method The ultrasonic calibration shall be completed prior to the examination. The REJECT control shall be maintained in the 0 position during calibration and examination. The FREQ MHz control shall be turned to 2. The type and length of, the search unit cable shall be recorded on the SwRI Sonic Instrument Calibration Record, and all other information blocks on the form shall be .filled in. 6.2.1 Temperatute The calibration block temperature shall be within 25°F of the component temperature and shall be recorded on the SwRI Sonic Instrument Cali-bration Record for the initial calibration and each verification. The surface temperature of the component to be examined shall be taken prior to performing and upon completion of each examination and shall be recorded on the appropriate SwRI Ultrasonic Examination Record. 6.3 Screen Distance Using the basic calibration block, set up the required sound path distance along the screen baseline. The screen distance shall be sufficiently long to posltion the initial pulse at 0 screen division and notch indication at 5 divisions on the screen baseline. 6.3.l Distance Amplitude Correction for the Examination of the Heater-Hole Portion*of the Stud (1) Position the SwRI Manual Stud Longitudinal Examination Probe in the access hole of the basic calibration block to obtain maximum response from the notch reflector on the inside surface of the access hole.
- SwRI Form QA 3*2
- SOUTHWES.T RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 7 of 10 (2) Set this signal to 80% +/-5% of full screen height (FSH) and mark this amplitude on the screen. The gain controls shall not be adjusted once this primary reference response has been estab~
lished. Indications shall be recorded as a percentage of this signal amplitude.
'(3) A line shall be drawn on the instrument screen at the primary reference amplitude extending from screen division 4 to screen division 6.
6.4 Calibration Verifications 6.4.1 Sweep-Range and Distance-Amplitude Calibration Verification Sweep-range and distance-amplitud*e calibrations shall be verified on the appropriate basic* calibration block when any of the following occurs: **'
*(l) Prior to a series of e~aminati~ns (2) With any substitution of the same type and length of se~rch unit cable (3) With any substitution utilizing the same type of power source; e.g., a change of batteries (4) At least every 4 hours during the examination (5) At the completion of a series of examinations (6) Whenever the validity of the calibration is in doubt 6.4.2 Verification of Calibration Reflectors at Scanning Speed The examiner shall verify the presence of the calibration reflector at scanning speed.
It *is not necessary to assure that this check confirms the signal amplitude at 100% of reference level, but merely to*demonstrate that the signal from the calibration reflectors are readily observable at scanning speed. The following statement shall be documented on the SwRI Calibration Record Sheet and initiated:
"Calibration reflectors have been verified at scanning speed."
- SwRI Form QA 3-2
SOUTHWEST*RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 8 of 10 6.4.3 Calibration Changes (1) Perform the following if the amplitude of the calibration reflector has decreased more than 20% or 2 dB or the reflector has moved on the sweep line more than 10% of the sweep division reading or 5% of full sweep, whichever is greater: (a) Void all examinations referring to the calibration in question and performed after the last valid calibration verification. (b) Conduct a new calibration. (c) Reexamine the areas for which examinations have been voided. (2) Perform the following if the signal from the calibration reflector has increased in amplitude more than 20% or 2 dB: (a) Correct the calibration. (b) Reexamine all indications recorded since the last valid calibration verification. (c) Enter proper values on a new SwRI Ultrasonic Examination Record for Bolting. 6.4.4 Recalibration Substitution of any of the following shall be cause for recalibration: (1) Search unit wedge or transducer (2) Search unit cable type or length (3) Ultrasonic instrument (4) Examination personnel (5) Couplant (6) Change in type of power source; e.g., a change from direct to alternating current SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 9 of 10
- 7. EXAMINATION 7.1 Examination of Pressure-Retaining Studs Forged studs shall be examined from the inside surface of the access hole. The examination area shall include the inside surface of the central bore.
7.2 Surface Conditions The contact surfaces must be free from roughness or other conditions that interfere with free movement of the search unit or impair the transmission of ultrasound. 7.3 Scanning Parameters When practicable, scanning shall be performed at a minimum gain setting of 2 times the reference level sensitivity. Instrument gain setting for scanning sh~ll be determined on the basic calibration block as follows: (1) ~ith the instrument at the primary reference level, manipulate the search unit on the basic calibration block to obtain a signal from a calibration reflector (notch) of 40% FSH. (2) Add 6 dB of gain by utilizing the 6 dB_switch (if present), the fine gain control, or a combination of the fine and coarse gain controls and choose any method which yields a signal
- response within +/-2 dB of 80% FSH.
(3) This amplitude and method shall be recorded on the SwRI Sonic Instrument Calibration Record and shall be used during the valid calibration period for all scanning at 2 times the reference level sensitivity. The search unit movement rate shall not exceed 6 inches per second during the examination unless the calibration is verified at the scanning speed to be used. Scanning overlap shall be a minimum of 10% of the search unit piezoelectric element dimension perpendicular to the.direction of scan. 7.4 Postexamination Cleanin~ Arrangements shall be made with the customer for postexamination removal of couplant materials. SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-104 Revision 2 December 1987 Page 10 of 10
- 8. RECORDING CRITERIA In~ications shall be recorded in accordance with the techniques- outlined in the applicable revision of SwRI Procedure IX-FE-117.
Ultrasonic reflectors producing a response greater than 50% of the reference level shall be recorded on the appropriate SwRI Ultrasonic Examination Record for Bolting. Indications producing a response greater than 100% of the reference level shall be investigated by a Level II or a Level III examiner to determine the shape, identity, and location of the reflector. Indications greater than 100% of the reference level, investigated and found to be other than geometrical in nature, shall be reporte~ to the customer for evaluation. Scanning limitations shall be rec9rded.
- 9. EVALUATION Initial evaluation of reportable indications shall be performed by SwRI personnel, and shall be conducted in accordance with the applicable ASME Boile'r and Pressure Vessel Code, Section XI, IYA-3000. Final evaluation and disposi-tion of reportable indications shall be the responsibility of the customer.
- 10. RECORDS Documents generated in accordance with this procedure shall be stored as specified in the SwRI Project Plan. The customer shall receive copies of these documents in the Examination Report, unless specified other"1ise in the *swRI Project Plan.
SwRI Form QA 3-2
*~
PROCEDURE DEVJATJON
- Page 1 of 1 Pages Procedure 800-122 IRevision No. 2 I Deviation No. 1 I SwRl-NDT- I The following examination areas are affected by this deviation:
Thickness examination grid marking for examinations performed in accordance with this procedure. The following paragraphs shall be deviated from as indicated:
- 7. EXAMINATION Change the third sentence to read as follows:
The grid pattern will be as specified by the customer and applied to the examination areas in accordance with the applicable revision ofIX-FE-138. Rationale for deviation: To incorporate IX-FE-138 for definition of the grid system, "Xw and "Y" coordinates, and direction of gridding used in examination area marking. If the deviation is determined to ai'fect the procedure Deviation Affects Qualification YES D NO Gj qualification, the deviation shall be qualified in accordance with ?rocedi;re IX-FE-107. APPROVALS Date: Technical Review: ,* :c,J. I Date:.. ,
.-;...:-11 /\t, Date:
Verbal Approval Given? Man~er of Q.A.: ~_/ Date: Cognizant Direc~or: Date: J@Y~ SwF!I FOAM FE*4-0
SwRI-NDT-800-122
~.SOUTHWEST RES.EARCH INSTITUTE Revision 2
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- NUCLEAR PROJECTS July 1988 OPERATING PROCEDURE Page 1of10 Title CALIBRATION AND ULTRASONIC TIIlCKNESS MEASUREMENT OF FERRmC PIPINQ, VESSELS, AND COMPONENTS USING THE SwRI TIIlCKNESS DATA ACQUISmON SYSTEM EFFECTIVl"'fYAND APPROVAL Revision 2 of this procedure became effective on July 15; 19~lbther revisions of the base dc;icument may be effective concurrently; sftJ)
Approvals Written By , /"" Date T~nical Redew . Date
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Deviation No. Date Effective Procedure Section(s) Affected Notes: SwRI Form QA-40A*O
. SOUTHWEST.RESEARCH INSTITUTE*
SwRI-NDT-800-122 Revision 2 July 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 2qf10 CALIBRATION AND ULTRASONIC TIIlCKNESS MEASUREMENT OF FERRITIC PIPING, VESSELS, AND COMPONENTS us~q THE SwRI TIIlCKNESS DATAACQUISmON SYSTEM SwRI-NDT-800-122 L PURPOSE This procedure provides the technical information and detailed steps required to ensure proper cahoration, ultrasonic (UT) thickness measurement and data acquisition using the SwRI Thickness Data
. Acquisition System (TDAS).
- 2. SCOPE AND APPUCATION Manual, contact, straight-beam longitudinal-wave UT calibration and thickness measurement of steel piping. vessels, and components in the nominal thickness range of 0.05 to 2.5 inches shall be utilized in accordance with this procedure.
- 3. APPUCABLE DOCUMENTS SwRI Nuclear Quality Assurance Manual (NQAPM) 3.1 Applicable .Erimination Records SwRI NDTR Form No. Revision Date 17-133 05-23-88
- 4. RFSPONSIBD..ITY (1) The Director of the Department of NDE Services, Nondestructive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manager shall be responsible for the implementation and control of this procedure in accordance with the NQAPM specified in the applicable SwRI Project Plan. (3) The examiner shall be responsible for implementing the requirements of this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 . Personnel
- Personnel performing ultrasonic thickness measurements shall be certified in accordance with NQAP 11-1, "Special Process Control."
SwRI Form QA 3-2
SwRI-NDT-800-122 SOUTHWEST RESEARCH INSTITUTE Revision 2 July 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page3of10 5.2 Equipment for Ultrasonic Measurements The following equipment comprises the TDAS: (1) Sonic FfS Mark I U'.I' instrument aligned and displaying a valid alignment calibra-tion tag. (2) TDAS Digital Interface unit shall be attached to the UT instrument and provide the necessary signal processing and output for recording of thickness measure-ments. * (3) Polycorder data storage unit attached to the TDAS Digital Interface for recording of thickness data. (4) Record Command Switch which will allow the operator to control the recording**(,( data. . 5.21 . Calibration Bloda
- Step thickness blocks shall be used for screen distance calibration and verification.
The block used for calibration/verification shall be of the same basic material, i.e., carbon steel, as the material to be measured. The step thickness block(s) shall provide a minimum of two calibration points within the full screen distance size chosen (see Paragraph 6.3). When a contoured wear face is used on the transducer, the step thickness block shall be curved. 5.22 Seardl Umt Search units shall be select_ed from the following sizes: 11s* Round 1/4* Round 3/s* Round The nominal search unit frequency should be 2.25, 5.0, or 10.0 MHz. A dual-element search unit shall be used for nominal thicknesses less than 0.3". For thicknesses 0.3" and greater a single-element search unit should be used. Other frequencies may be selected dependent on material properties or surfaces. On dual-element search units the wear face shall be flat and straight unless the component curvature prevents adequate contact with the surface, in which case a contoured wear face shall be used. NOTE
- Adequate contact may not be possible on pitted surfaces. Where possible, arrangements shall be made for removal of any surface condition which prevents adequate contact.
SwAI Form QA 3*2
SOUTHWEST R~SEARCH INSTITUTE SwRI-NDT-800-122 Revision 2 July 1988. NUCLEAR PROJECTS OPERATING PROCEDURE Page 4of 10
- 5.3 Couplant (1) Soliotrace 30, Sonotrace 40, Ultragel II or other couplants approved by the customer shall be used when performing UT calibrations and examinations in
. accordance with this procedure. For high temperature applications, Thermasonic 50, Krautkramer GmbH, or other approved couplant may be used.
(2) Couplant materials shall be certified for sulfur content and total halogens in accordance with SD-129 and SD-808* of Article 24, Section V. The residual amount of total sulfur or halogens shall not exceed 1% by weight. 5_4 Temperature Requirements The basic cah'bration block and component temperature shall be the same nominal range.
- 6. CALIBRATION 6.1 Preliminary UT Instrument Setup The examiner shall ~ure the "Low Battery" charge indicators are out during instru-
- ment use.
The ~trument shall be warmed up a minimum of 10 minutes prior to use. Th~ TDAS record cable jack must be plugged into the TDAS unit. The controls on the Sonic FTS Mark I shall be set as follows prior to cah'bration: NOTE
. The following instrument settings are initial settings. The examiner may require different settings for some instrument and search unit combinations. It is imperative that the Sonic controls be used as necessary to obtain a straight and vertical leading edge for the reflected signal.
(1) POWER/OFF switch set to power (2) RANGE switch set as required (3) DELA.Y coarse switch set to position 1 (4) DAMPING switch initially set to M1N (5) Mode switch set to THRU TRANS or NORMAL as appropriate (6) REP RATE switch set to 3K (7) FILTER switch set to HI SwRI Form QA 3-2
- SOUTHWEST RESEARC.H INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-122 Revision2 July 1988 Page 5of10 (8) VIDEO/DIFF as necessary (9) DEC START, if applicable, turned all the way counterclockwise (10) DEC SLOPE, if applicable, turned to OFF (11) REJECT CONTROL to be used as necessary to provide a clean baseline 6.2 Sonic FI'S MK I CalibraD.on The full saeen distance size shall be at least 0.200 inch beyond the anticipated exam-ination range. The appropriate step thickness block shall be utilized to construct a linear sound path using a minimum of three steps that encompass_ the thickness of the component to be examined.
6.3 TDAS c3Iibration
.6.3.1 Mode Switch
- Position the MODE switch to the "single" (single backwall) position. This means that the* digital electronic circuit will start the "clock" at the beginning of the gate and stop the "clock" at the leading edge of the first signal within the gate to break the threshold level.
6.3.2 Gate Position and W"u:llh Whereas the Sonic instrument saeen can be linearly calibrated over a very large thickness range including "O" thickness, the TDAS instrument circuitry is currently designed to only be cahorated over a narrow range (gated region). This range varies slightly from instrument to instrument, but for the purpose of this procedure it should be considered to be a maximum of 1.500 inches. The position of the gate, however, can be moved over a very broad range, easily including the limits specified in this procedure. The purpose of the following paragraphs is to provide instruction as to the proper positioning and width adjustment of the TDAS gate. Adjust the Gate Position and Width as follows: (1) The position of the TDAS gate is indicated on the Sonic cathode-ray tube (CRT) screen by the portion of the baseline that is raised. Tum the TDAS gate marker switch to the ON position. (2) Set the Sonic Range switch on a range that allows both ends of the gate marker tO be visible in the Sonic saeen. It may also be necessary to adjust the Sonic Delay control and/or to use the TDAS Pulse Delay control to bring the gate marker left edge into view. Use the Pulse Delay knob on the TDAS to adjust the left side of the gate approximately 0.200 inch to the left side of the signal received from the thickness step used for the lower end of the TDAS calibration range. For a 0.100- to 0.500-inch TDAS calibration, the FINAL position of gate left edge will be just off the left side of the Sonic screen. SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-122 Revision 2 July 1988 Page 6of10 (3) Using the. TDAS Pulse Width knob, adjust the right side of the gate to approx-imately 0.200 inch past the anticipated thickness range. If the Sonic coarse Range control has to be positioned at more than one position greater than the final calibration position, it will be appropriate to decrease the coarse* Range as the gate width decreases; i.e., follow the gate at appropriate intervals as it narrows. The total gate width should in no case be greater than 1.500 inches and should be the smallest width necessary. This will assure the greatest possible TDAS accuracy. (4) Return the Sonic RANGE and DEI.AY Controls to the settings previously estab-
- lished for screen cah'bration.
Adjust the Threshold as follows: Place the transdu~er on an .appropriate step thickness at the lower end of the calibra-tion range and adjust the amplitude to within the range of 30% to 40% full screen height (FSH). Using the threshold knob, adjust the threshold such that the digital meter glows brightly with the
- signal between 30% and 40% FSH but goes blank with signal below 30% FSH.
6.3.4 Fuuli Gau Adjustment Make final gate adjustments as follows: (1) With no further change of the Sonic Range or Delay controls, place the trans-ducer on the thickness step used for the lowest end of the calibration range and adjust the signal amplitude to at least 80% FSH. (2) Adjust the left side of the gate using the TDAS Pulse Delay knob until the lowest stabilized number appears in the digital display. As the gate is adjusted, the numbers in the display will decrease to the point where they begin to flicker and then blank out. The adjustment is correct when the number appearing in the display is as low a value as possible while remaining bright and stable. 6.3.5 1DAS Digital Display Calibration Calibrate the Digital Display as follows: (1) By observing the TDAS digital display as the transducer is applied to at least three step block thicknesses (including the lowest thickness), assure that the digital readings are positive rather than negative. If any step yields a negative number, use the TDAS "Zero" control to correct this situation. (2) Place the transducer alternately on *two steps which encompass the expected
- examination range. With each signal at least 80% FSH, make note of the digital display. Using the TDAS range, adjust the digital display to obtain the SwRI Form QA 3*2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-122 Revision2 July 1988 Page 7of10 appropriate digital reading spread. Repeat this cah'bration on an additional step .
within the gate and one of the first steps to insure linearity. (3) After the digital reading spread is obtained, place* the transducer on the lowest step used and adjust the TDAS "Zero" control so
- that the display indicates the correct thickness. Note: When the anticipated thickness to be measured cannot be encompassed with the available step wedge, the steps closest in thickness to the component being measured may be used for calibration.
(4) Verify that all gated steps produce a .readout within +/-.005 inch on the digital display. Each signal should be set at a minimum of 80% FSH. If any step readout fails to be within the +/- .005-inch toforance, return to step (2) . above.
;rhese readings shall be* recorded on the applica.ble SwRI calibration sheet.
6.4 Polycorder Programming for Data Collection NOTES
- At any time during steps (2) through (11), entry errors (errors that are entered by depressing the "ENTER" key) may be corrected by returning to step (4). To return to step (4), press "ESC".
Key stroke errors that have not yet been entered can normally be corrected by depressing the left hand arrow key.
- Perform the following steps to program the Polycorder for data collection:
(1). To assure that a false reading is not recorded in the first line of the Polycorder data file, it is recommended that the TDAS POWER switch be cycled to OFF and ON before proceeding with Polycorder setup steps. (2) Turn the Polycorder on by depressing the "ON" key. The Polycorder will initially display a log-on message which includes either "516B" or "516C". This is the model number. The display window will then show "MODE ?_". (3) Upon initial use of the Polycorder, i.e., first site to be measured after the
- Polycorder memory has been transferred to the computer, the examiner must assure that "data are cleared by executing Mode 4-3 as follows:
Display (a) Press 4 "FILE 1, 2, 3 DIR, ERA-F, ERA-D" (b) Press 3 "ERASE DATAFILE= PDATA ( c) Press ENTER "SURE? (Y/N)" ( d) PreiS SHF "ERASE DATA FILE"
- (e) Press Y "DONE" (t) ESC "MODE?"
'(4) Depress the "O" and use the up arrow key to select "EXECUTE PROGRAM FILE:
Record." SwAI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-800-122 Revision 2 July 1988' NUCLEAR PROJECTS OPERATING PROCEDURE Page 8 oflO (5) Press the "ENTER~ key. (6) The display window now indicates "FILE CODE=". The File Code will be selected by the Team Supervisor for the specific area to be examined. :rress the one-digit key corresponding to the desired code, 0-9, and press "ENTER". (7) The display Window now indicates START X =
- Enter the starting "X" position. (The starting position will normally be "O".) P;ess the "ENTER" key.
(8) The display window now indieates "END X = _.. Enter the applicable "X" cor-responding to the last "X" on the grid pattern. Press the "E;NTER" key. (9) The display window now indi~tes '"GRID = ". Enter the number corresponding to the grid size in inches (1, 2, 3, or 4) and press the "ENTER" key. (10) The display window now indicates "START Y = _". Enter the appropriate "Y" data following the same steps as (7) and (8) above. ' (11) On completion of "Y" data entry, the display will indicate FLAG = *. Enter the three-digit minimum wall thickness (wich no decimal point) as specifi~d for the area being examined. Press the "ENTER" key. (12) The display window now indicates "DIR l=X O=Y ". Enter a "l" if the scan direction is in the X direction or enter "0" if che scan direction is in the Y direction (for piping and vessels, "X" is typically in circumferential direction, while "Y" is in che axial or longitudinal direction). Press the "ENTER" key. The Polycotder is now ready to accept data. The screen prompts will be '.displayed until the first measurement is recorded at which time che thickness measurement and its associated parameters will also be displayed. (13) You can now take measurements by placing the search unit on che examination surface, observing the Sonic CRT screen and depressing the Record switch. (14) When done taking measurements, turn the Polycorder off, depress "ESC" and then the "9." (15) The Polycorder must NOT be disconnected from the TDAS unit while data are being taken or the unit is on. Disconnection of the Polycorder may result in the loss of data. 6.5 Calibration Verification Calibration shall be verified as stated in Paragraph 6.4.5(4): (1) Prior to a series of measurements (2) At the completion of a series of measurements SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-800-122 Revision 2 July 1988 Page 9of10 (3) With a change in personnel, power source, or search unit.
(4) Whenever the validity of the cah'bration is in doubt 6.6 Recalibration Perform the following if a change of +/-0.005 inch from the actual thickness value is noted. (1) Void all measurements performed after the last valid calibration verification. (2) Correct* the calibration. (3) Remeasure the voided measurement areas.
- 7. EXAMINATION Areas to be examined will be identified by the customer. The entire area of examination will be marked by *a grid pattern drawn on the surface of the component with a customer-approved marker..
The grid pattern will be as specified by the customer. If the total number exceeds 1,720 for a 516B Polycorder (large LCD display) or 3,500 for a 516C Polycorder (small LCD display), the polycorder software is designed to terminate data recording just prior to reaching full capacity. In such cases a "NO MORE ROOM" message will be displayed and the TDAS display will no longer respond to valid UT signals until execution of the "RECORD" program is terminated. (1) Place the TDAS search unit on the pipe at the starting X/Y. location. Obtain a valid backwall signal and digital display reading. Press the Record Command Switch to enter the data. (2) Continue taking readings as in (1), advancing Scan Direction as entered in the Polycorder [see Paragraph 6.4(12)]. (3) For any location where a measurement cannot. be obtained, enter a "O" reading by lifting the transdueer from the examination surface (making sure that the couplant doesn't cause a spurious signal) and depressing the Record switch. (4) Upon reaching the limits of the grid established in the Polycorder under Section 6.4 above, the Polycorder software will display the fmal recorded thickness measurement and its associated parameters. If the record command switch is depressed again, the TDAS digital meter will be unable to respond to valid signals until the TDAS power switch is cycled, or until the Polycorder is reset for further data recording. After completion of a grid or grid segment. further measurements may be recorded (subject to the memory capacity) by pressing ESC and then proceeding to the polycorder setup steps beginning with Paragraph 6.4( 4) . SwRI Form QA 3*2
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SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-800-122 Revision 2
~
July 1988 NUCLEAR PROJECTS OPERATING PROCEDURE Page 10of10 NOTE After the first reading is taken, the Polycorder will indicate the "X" and "Y" coordinate location, X = O and Y =O, and the thickness reading recorded. For each successive data poin~, the Polycorder will indicate the last coordinate location and the thickness recorded.
- 8. EVALUATION The thickness measurements taken in accordance' with this procedure shall be evaluated by the customer or the customer's representative.
- 9. RECORDS Data generated in accordance with this procedure will be in the form of computer printouts.
Additionally, all computer report files (* .RPT) will be recorded on floppy diskettes for future refer-ence and shall be stored as specified in the Project Plan. A copy of each data diskette will also be made available to the customer if so desired. An examination report and location of record storage is at the option of the customer. SwRI .Form QA 3-2
PROCEDURE DEV1ATION Page 1 of Pages
- Procedure SwRl-NDT-900-7 The following examination areas are affected by this deviation:
Visual examinations performed in accordance with this procedure. I Revision ~o. 14 I Deviation No. 1 The following paragraphs shall be deviated from-as indicated: Change 7.1 Surface Cleaning to read as follows: 7.1 Surface Cleaning Visual examinations which require clean surfaces or decontamination for valid interpretation of results shall be preceded by appropriate cleaning processes. The surface of welds and adjacent base material to be examined shall be free from scale, slag, dirt, paints, or other extraneous matter that obscures the surface or interferes with the visual examination. Examinations on components with painted or coated surfaces are permitted when looking for general :.:* conditions such as misalignment, movement or other abnormalities on supports, hangers, snubbers, and shock observers, or loose, missing and damaged bolting. Rationale for deviation: This deviation provides clarification for the examination of components when painted as requested by Public Service Electric and Gas Company. Deviation Affects I If the deviatio*n is cietermined to aHect :he proceoure ' Qualification YES D NO qualification. the deviation shall be qualified in I accordance with ?rocedure IX*Fc-107. , APPROVALS SAfL.)) l SwRI FORM FE-4-6 u (/ ()
SwRI-NDT-900-7
~SOUTHWEST RESEARCH INSTITUTE Revision i4
*. NUCLEAR P.ROJECTS July 1987 OPERATING PROCEDURE Page 1 of 9 Title VISUAL EXAMINATION OF NUCLEAR POWER PLANT COMPONENTS EFFECTlVJT'I' AND APPROVAL Revision 14 of this procedure became effective on 15/7/1987 . Other revisions of the. base document may be effective concurrently.
SA Approvals
~QA-Written By Date Technical Review Date c:&z~!
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The following information may be used for convenience. Co pletion of this portion is not mandatory.
~%1 Date Effective Procedure Section(s)
Affected Notes:
- Swl'll Form QA-1.0A-O
SOUTHWEST RESEARCH INSTITUTE SwRI-NDT-900-7 Revision 14
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July 1987
~ R!I!,~ ... \ .c1 NUCLEAR PROJECTS OPERATING PROCEDURE
~ 1111111' ~ J_ _A II Page 2 of 9
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VISUAL EXAMINATION OF NUCLEAR POWER PLANT COMPONENTS SwRI-NDT-900-7
- 1. PURPOSE This procedure provides the technical information and detailed steps required to ensure a proper visual examination of nuclear power plant com-ponents in accordance with the applicable American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Codes.
- 2. SCOPE AND APPLICATION Direct and remote visual techniques shall be applied, as described in this procedure, for the examination of nuclear power plant components, including nuclear reactor internals.
Components, parts and areas to be examined shall be as specified in the applicable Southwest Research Institut~ (SwRI) Examination Plan.
- 3. APPLICABLE DOCUMENTS (1) ASME Boiler and Pressure Vessel Code, Section XI, 1983 Edition with
~ddenda through Summer 1983, "Rules for Inservice Inspection of*
Nuclear Power Plant Components" (2) SwRI Nuclear Quality Assurance Program Manual (NQAPM) 3.1 Applicable Examination Record SwRI NDTR Form No. Revision Date 17-28 07-30-80 17-29 07-31-75 17-54 (if required by 03-15-79 that applicable SwRI Examination Plan)
- 4. RESPONSIBILITY (1) The Director cf the Department of Engineering Services, Nondestruc-tive Evaluation Science and Technology Division, shall be responsible for the preparation, review, approval, and control of this procedure.
(2) The Project Manage~ shall be responsible for the implementation of this procedure in accordance with the NQAPM specified in the appli-cable SwRI Project Plan. SwRI Form QA 3-2
- SOUTHWES-T RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-900-7 Revision 14 July 1987 Page 3 of 9 (3) The examiner shall be responsible for implementing the requirements of this procedure.
(4)
- The Manager of the Support and Administration Section, Nondestructive Evaluation Science and Technology Division, shall be responsible for storage of records generated in accordance with this procedure.
- 5. PERSONNEL AND EQUIPMENT 5.1 Personnel Certification Personnel performing examinations shall be certified in accordance with SwRI NQAP 11-2, "Procedure For Certifying Visual Examination Personnel."
s.2 Equipment The Visual Examination Acceptability Test Card shall be made from Kodak Neutral Test Card No. R-27 or an equivalent, with an 18% neutral grey side having a 1/32-inch-wide black line across its center
- Commercially available equipment shall be used as required for the per-formance of examinations or operations by the techniques described in Para-graphs 6.1, 6.2, 6.3, and 6.4.
- 6. EXAMINATION METHODS 6.1 VT-1 Examinations The examiner shall determine the condition of the part, component, or surface with respect to indications such as, but not limited to:
(a) cracks (b) wear (c) corrosion or errosion (d) physical damage to the surface of the component "6.1.1 Direct Visual Direct visual examination shall be performed by placing the eyes at an angle of no less than 30 degrees within 24 inches of the surf ace to be examined. Mirrors may be used to improve the angle of vision, and aids* such as magnifying lenses may be used. In addition to the general lighting, illumination of the area to be examined shall be provided at right and oblique angles to expose cracks or
- evidence of corrosion or erosion
- SwRI Form QA 3-2
I SwRI-NDT-900-7 SOUTH.WEST RESEARCH INST*ITUTE Revision 14 SJ_ July 1987
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I ;r ""'"" I 1:4 NUCLEAR PROJECTS OPERATING PROCEDURE Page 4 of 9
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Resolution for direct VT-1* shall be considered adequate when the combination of access, lighting, and angles of vision, either unaided or cor-rected, can resolve a 1/32-inch-wide black line on an 18% neutral grey card placed on the surface to be examined. 6.1.2 Remote Visual Technique Remote visual examination may be used where conditions exist that do not permit direct visual examination. Remote visual*examination may include visual aids such as telescopes, periscopes, borescopes, fiber optics, or video cameras and monitoring systems, with or without attachments for permanent recording. Remote techniques shall demonstrate the ability to provide a reso-lution at least equivalent to that obtainable by direct visual examination. Mirrors, movable lights, o.r rotating optics, or any combination thereof, may be employed to display cracks, evidence of wear, corrosion, erosion, or physical damage. Scanning paramete~s, if required, for the remote visual examination shall be included in the applicable SwRI Scan Plan. Resolution for remote VT-1 shall be considered adequate when the combination of access*, lighting, and angles of vision, either unaided or cor-rected, can resolve a 1/32-inch-wide black line on an 18% neutral grey card placed on the surface to be examined or on a surface of the component that is similar to the area to be visually examined. Other resolution methods that pro-. duce equivalent or better results are.acceptable. 6.2 VT-2 Examinations The examiner shall locate and record evidence of leakage from pressure-retaining components, or abnormal leakage from components with or with-out leakage collection systems as required during system pressure or functional tests. 6.2.1 Noninsulated Components The accessible external exposed surfaces of pressure-retaining components shall be examined for evidence of leakage.
- Examination of the surrounding area, including the floor or equip-ment located underneath the component, shall be required for components with inaccessible external surfaces.
6.2.2 Insulated Components Examinations may be conducted without the removal of insulation by examining the accessible exposed surf aces and joints of. the insulation. Ver-tical surfaces of insulation need to be examined only at the lowest elevation where leakage may be detectable. Horizontal surfaces of insulation shall be examined at each insulation joint. SwRI Form QA 3*2 *
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-900-7 Revision 14 July 1987 Page 5 of 9 Inaccessible piping and components shall require an.exanination for evidence of leakage on the surrounding floor areas, equipment surfaces located underneath the component, or other areas where leak.age may be channeled.
Discoloration or residue on surfaces examined shall be given par-ticular attention to detect possible boric acid accumulations from borated reactor coolant leakage~ 6.2.3 Components With Leakage Collection Systems When leakages from components- are normally expected and collected (such as valve stems, pump seals, or vessel flange gaskets) the examination shall be conducted by verify.i~g that the leakage collection system is operative. 6.2.4 Repaired or Replaced Components and Alteration of ~ System The visual examination following a repair or replacement bf a com-ponent, or the alteration of a system, may be limited to the repair or replaced components, or the altered portion of the system, but shall include any connec-tion made to the existing system. 6.3 VT-3 Examinations The examiner shall determine and record the general mechanical and structural conditions of components and their supports, such as the presence of loose parts, debris or abnormal corrosion products, wear, cracks, erosion, cor-rosion, and the loss of integrity at bolted or welded connections. 6.3.1 Vessel Internals The areas to be examined shall include major load-bearing elements of the reactor internals that retain the core structure in position; the lateral vertical, and horizontal restraints within the reactor vessel; the locking and bolting devices whose failure could adversely affect the structural integrity of the internals; surfaces that are known to be or may become contact surfaces during operation; critical locations on reactor internal components as identi-fied from the vibration analyses; and the interior of the reactor vessel for evidence of loose *parts or foreign material *. 6.4 VT-4 Examinations This examination shall be performed to determine conditions relat-ing to the operability of components or devices such as mechanical and hydraulic snubbers, component supports, pumps, valves, spring-loaded hangers and constant supports. Functional adequacy, verification of settings, or freedom of motion shall be determined. SwRI Form QA 3-2
SwRI-NDT-900-7 SOUTHWEST RESEARCH INSTITUTE Revision 14 July 1987 NUCLEAR PROJECTS OPERATING PROCEDURE Page 6 of 9 The su~port settings of constant and variable spring-type hangers, snubbers, and shock absorbers shall be recorded in the .REMARKS section of the SwRI Visual Examination RP.cord. The scale reading of .h.angers having calibrated load indicators shall be recorded in the REi.'\fARKS section of the SwRI Visual Examination Record. Hydraulic snubbers shall be examined for signs of fluid leakage at shaft seals, joints, and couplings. Shaft extensions shall be exami.ned for scratches, cuts, and gouges. Hanger springs shall be examined for integrity to ensure that springs have not sheared. Pipe clamps and U-bolts ,shall be examined to ensure that they are securely attached to the pipe.
- 7. Examination 7.1 Surface Cleaning Visual examinations which require clean surfaces or decontamination for valid interpretation of results shall be preceded by appropriate cleaning processes.
Examinations may be required where the surface is painted or has other types of coatings. This shall be permitted if it is determined. that such coatings do not interfere with a valid interpretation of results. 7.2 Examination Areas Components, parts, and areas to be examined shall be as specified in the applicable SwRI Examination Plan. Remote visual examinations utilizing mechanized scanning devices shall be as specified in the applicable Scan Plan. Scanning parameters, if required, for the remote visual examination, shall be included in the applicable SwRI Scan Plan. Visual examination of flange surfaces of vessels, pumps, valves and piping, when the connection ~s disassembled, shall include 1.0 inch annular surface of flange surrounding each stud. NOTE Bolting may be examined: (a) in place under tension (b) when the connection is disassembled (c) when the bolting is removed SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROjECTS OPERATING PROCEDURE SwRI-NDT-900-7 Revision 14.
July 1987 Page 7 of 9
- 8. RECORDING CRITERIA Indications*shall be recorded in accordance with the techniques outlined in the applicable revision of SwRI Nuclear Projects Operating Procedure IX-FE-116 for direct visual examinations.
Indications detected during remote visual examinations shall be recorded in accordance with the customer's specifications, remote equipment manufacturer's specifications, or the SwRI Scan Plan, if applicable. All visual abnormalities shall be recorded on the SwRI Visual Examination Record and reported to the customer. 8.1 Pressure Retaining Bolting Crack-like linear surface indications which exceed the following limits shall be recorded and reported to the customers: (a) nonaxial indications, 1/4 inch in length (b) axial indications, 1 inch in length The following conditions shall also be recorded and reported to the customer: (c) deformed or sheared threads in the zone of thread engagement of bolts, studs, or nuts (d) localized general corrosion that reduces the bolt or stud cross-sectional area (e) bending, twisting, or deformation of bolts or studs (f) missing or loose bolts, studs, nuts, or washers (g) fractured bolts, studs, or nuts (h) degradation of protective coatings on bolting surfaces (i) evidence of coolant leakage near bolting 8.2. Pump Casing and Valve Bodies The following conditions shall be recorded and reported to the customer: SwRI Form QA 3-2
SOUTHWEST RESEARCH INSTITUTE NUCLEAR PRa°JECTS OPERATING PROCEDURE SwRI-NDT-900-7 Revision 14 July 1987 Page 8 of 9
<a) corrosion or erosion that reduces the pressure retaining wall thickness (b) wear of mating surfaces
)
(c) crack-like surface indications which exceed 1/16 inch 8.3 Interior Attachment-to-Vessel Welds The following indications shall be recorded and reported to the customer: (a) crack-like linear surface indications on the welds joining the attachment to the vessel wall that exceed 3/8 inch in length (b) structural degradation of attachment welds 8.4 Reactor Vessel Interior and Interior Attachments The following indications shall be recorded and reported to the customer: (a) structural distortion or displacement of parts (b) loose, missing, cracked, or fractured parts, bolting, or fasteners (c) foreign materials or accumulation of corrosion products that could interfere with control rod motion or could result in blockage of coolant flow through fuel (d) corrosion or erosion that reduces the nominal section thick-ness (e) wear of mating surfaces (f) structural degradation of interior attachments
- 9. EVAtUATION Initial evaluation of reportable indications shall be performed by SwRI personnel in accordance with Article IWA-3000, Section XI, of the applicable ASME Boiler and Pressure Vessel Code. Final evaluation o'f reportable indica-tions shall be the responsibility of the customer.
SwRI Form QA 3-2
- SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPERATING PROCEDURE SwRI-NDT-900-7 Revision 14 July 1987 Page 9 of 9 lO.* RECORDS Documents generated in .accordance with this procedure shall be sto.red as specified in ~he SwRI Project Plan *. The customer shall receive copies of these documents in the Examination Report, unless specified otherwise in the SwRI Project Plan *
- SwRI Form QA 3-2
APPENDIX E * , ULTRASONIC CALIBRATION BLOCK DRAWINGS
- APPENDIXE ULTRASONIC CALIBRATION BLOCK DRAWINGS Table of Contents
*Block No.
12-SS-160-1.283-21-SAM E-1 8-SS-XX-.860-23-SAM . E-2 6-SS-160-.764-25-SAM E-3 4-SS-XXS-.689-27-SAM E-4 4-SS-160-.533-28-SAM-R E-5 3-SS-160-.451-30-SAM E-6. 12-SS-40-.377-31-SAM E-7 8-SS-80-.484-32-SAM E-8 5-CSCL-42-SAM E-9 8-CS-160-.906-46-SAM E-10 6-CS-80-.432-49-SAM E-11 7-CSCL.;50-SAM E-12 PL-3-CS-51-SAM E-13 7-1.125-8-CS-60-SAM E-14 PL-l.5-CS-65-SAM E-15
- 4.5-.75-8-CS-70-SAM 14-SS-140-1.25-77-SAM 14-SS-160-1.40-78-SAM 14-SS-40-.438-79-SAM 2.563-8-12-MSIV-82-SAM PL-SS-.750-85-SAM E-16
. E-17 E-18 E-19 E-20 E-21 9.5-SS-.750-86-SAM E-22 14-SS-10-.250-96-SAM E-23 PL-SS-.250-97-SAM E-24 1.5-SS-COUP-111-SAM E-25 10-SS-140-1.0-8-REG E-26
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Sw.R. I SONIC INSTRUMENT CALIBRATION RECORD PROJECT No.: I 1- ,1 f.:?. ?' - lfJ 19 t SITE: L-1~I DATE :(DAY- MON.-YR.) At) r"J-6 ?. ~ ITIME= (24 HR. CLOCK) I SHEETc9ob O / I.) EX~ER= (SIG~?~.../~ SNT% PROCEDUf?E INSTRUMENT: SERIAL No. Cf'LIBRATION VERIFICATION
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APPENDIXF CERTIFICATES OF PERSONNEL QUALIFICATIONS
APPENDIX F CERTIFICATES OF PERSONNEL QUALIFICATIONS Table of Contents Name UT PT MT VT Page Dietrich, Bill* I II I . II F-1 Duran, Leroy II I I II F-6. Freeland, Stacy* I I F-11 Garcia, David G.* II II II II F-13 Hanes, Jeffrey L.
- I I I F-18 Ingamells, John R. I** I** I** I** F-21 Kleinjan, Michael W. II II II II F-25 Long, Jeffrey W.
- I I** I F-30
- Long, Richard P.
- May, Rickey L.
- Minor, Christopher A.
I II II I II II. I II II I II II F-33 F-38 F-44 Morton, Victor ill m ill m F-49
*Sonic Systems International, Inc., Technician **Level I Trainee .
- F-i
* '~~;;;.\ Sonic Systems International, Inc.
~*l~!.r Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR BILL DIETRICH The aforementioned *individual is qualified in accordance with Sonic Systems International 1 s Training, Qualificatio*n aad Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number
- SNT-TC-lA.
ULTRASONIC This certification is based on background training, examination, and evaluation method indicated
- I 1/26/89 1/26/92 NOE Method Level Date Expires Examination Results Genera 1 77 .5% x .3 = 23.2 Specific 96% x .2 = 19.2 Practical 85% x .5 = 42 *.5 Composite Score = 84 .. 9
- xami ner Manager F-1
Sonic Systems International, Inc. Specialists in Ultrasonic T(!Sting and Consulting CERTIFICATE OF QUALIFICATION FOR. BILL DIETRICH The aforementioned individual is qualified in accordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-005, which comp.lie*s with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated. LIQUID PENETRANT NOE Method II Level 1/2 6/89 Date 1/26/92 Expires Examination Results* General 80% x .3 = 24.Q Specific 100% x .2 = 20.0 Practical 95% x .5 = 47.5 Composite Score = -- 91.5 Cert xami ner Manager F-2
- !~m*=~,., Sonic Systems International, Inc .
*, II' , I ', f
****=-=:s~*
Spcciolisls in Ultrasonic Testing and Consu I ring CERTIFICATE OF QUALIFICATION FOR BILL DIETRICH The aforementioned individual is qualified in acordance with Sonic Systems International's Training, Qualification and Certification Procedure Nuniber SSI-A-005, which complies with the requirements of the
*American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on- background training, examination, and evaluation method indicated
- MAGNETIC PARTICLE I 1/26/89 1/26/92 NOE Method Level Date Expires Examination Results General 83.5% x .3 = 25.0 Specific 85% x .2 = 17.0 Practical 80% x .5 = 40.0 Composite Score = 82.0 w~~
Certified~xaminer
- ssurance Manager F-3
Sonic Sys tcms International, fnc. Spt?<:iulists in U/trnsonrc Testing und C:o11su/ti11g CERTIFICATE OF QUALIFICATION FOR
)
BILL DIETRICH The aforementioned individual is qualified in accor.dance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is *based on background training, examinat1on, and evaluation method indicated. VISUAL, VT-1 II 1/26/89 1/26/92 NOE Method Level Date Expires Examination Results General 93.4% x .3 = 28.0 Specific 100% x .2 = 20.0 Practical 100% x .5 = 50.0 Compos 1te Score = 98. 0 ~t~e~I ~xami 11 ner Manager F-4
Sonic Sys tcms In tern a tional, .Inc. Sp(?c:iu/ists in LJ/trason1c Testing nnc/ Consulting CERTIFICATE OF QUALIFICATION FOR BILL DIETRICH The aforementioned individual is qualified in accordance with Sonic Systems International's Training, Qualification and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification. is based on background training, examination, and evaluation method indicated *
- VISUAL,VT-3 NOE Method II Level
. 1/26/89 Date 1/26 /92 Expires Examination Results General 88% x .3 = 26.4 Specific 90% x .2 = 18.0 Practical 100% x .5 = 50.0 Composite Score = 94.4
*Certified NOE Level III Examiner F-5
~.'-
-*~ SOUTHWEST RESEARGH INSTITUTE
~ NONDEST.RUCTIVE EXAMINATION l rt;:'.:? *.: STATEMENT OF CERTIFICATION The Director of the Deoartment of Engineering Services, Nondestructive Evaluation Science and Technology Division. certifies tnat Leroy Duran is Qualified as Level II in Ultrasonic Testing in accordance with the requirements oi SwRI Nuclear Quality Assurance Procedure 11*1, which incoroc;1rates tne guidelines of SNT*
TC-tA, 1975 ar.d 1980 Editions. Certification Limitations: Certification valid only while employed by SwRI
- Soecial Qualifications lit anyl:
None* Exoirat1on Date: I Oln.3J90 Signed: ~- f .1/!;,11/ Date: ~~;qgz Dit}Ctor. Department of Engineering Services EDUCATION. TRAINING. ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING (This metnod and levell: High School Commonwealth of Va. 4 GRAD Date Completed 1/15/87 Additional: Hours: 44 Location: SwRI Major Field of Study Date employed by SwRI: 7/30/84 Previous NOE experience (if used for Qualification!: The individual has been credited with 11 of experience in this examination method on the date of certification. Some of the experience may have been accrued simultaneously with other NOE methods tat least 25% was in this methcdl. months VISUAL ACUITY ANO COLOR PERCEPTION None COMPANY FROM TO The individual is capable of reading Jaeger Number 1 letters at 12 inches in at least o;,e eye (using corrective lenses if specified betowl, and can distinguish and differennate contrast between colors used in this method. 8/£~786 Corr. Req. No Verified by* Heidi Gutierrez_ J.J.q Date Corr. Req. Verified by 7/17/87 No Heidi Gutierrez ,~g{d~ 7/5/88 No Bett;! Aldridge :t/_I/ r MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT DATE General:
- 70.00 0.3 Initial Certification: i/23/87 Specific: ** 75.00 0.3 Recertification:
Practical: *** ~~.rm i'.'.i .4 Composite so.jo 1.0 Recertification: Recertification: Recertification: Date: *1/7/87; **l/15/87; ***1/16/87 Recertification: Resoons1ble Level Ill: n 4-~ 1/._u/~7 E. n. uescner Recertification: REMARKS SwRI Form QA-11-7 F-6
~ .....
-~~ SOUTHWEST RESEARCH INSTITUTE
~~-::...~~--...
NONDESTRUCTIVE EXAMINATION I I . : . _ _.....:._*
--.a - - -
__ _L _ _ _ STATEMENT OF CERTIFICATION
--=:-.:--.
The Directer ot tne Oecanment ct Engineenng Servicm. Noncesuucuve Eveluanon Science anc Te.:nno1oc;v Division. c:emfies mat LEROY DURAN is aualitiect as UiwH I in LIQUID PEHEIRMU Tesnng 1n acccraance .,,,,n tne reauiremena ot SwRI Nuclur ~itv Asaur.11nce Proaiaunt 11*~. which inccrt1orates tne gu10111ines ot SNT* TC- l A. 1975 ar.d 1980 Editions. Carntreauon 1..Jmttanons: Certification valid onl~ while ~me o:i:esJ b:i: l S:i:tBI Soecia1 Qualificanons lit anv1: None E.xcrrauon Cate* Aor11 5, I~~I Signea: ~ ~ !W Oin1C1cr. Oeoanmem of Engine.ing Servic8s Cua: i/..'1 !_gz EDUCATION. T'FIAINING. ANO EX?ERIENCE HISTORY I EDU~TION: NAME YEARS DEGREE T'FIAINING !This metnocs ana levell: Hign Scnoc1 Commonwealth of VA 4 GB8Q Cate CQmci.iea 10/09/84: 12/10/87 Aaamona1: Hou~: 6; 8 Loi:at1cn: SwRI Maier Fie4d of Studv I Cata emcloved bV SwRI: July 30, 1984 Pnr.rioua NOE exoenence lit u:sea for auaiificaucnl: 6 The individual nu been creditea wnn rnontns COMPANY FROM TO ot exoenenca in tnis e.ummaaon m.mccs on tn* dlne of certification. None Some ot tne exoenenc8 mav h*- be9r'I ac::n.ied simuttanecusav wim cmer NOE metnoas lat lust 2!i'l& - in tnis memodl. i V1SlJAL ACUITY ANO COLOR PERCE?TTON I The 1naividua1 is c:acaOI* of reaaing Jaeger Numcer 1 lenens n 12 inc:nes inn 1.._ one eve lusng ccm9Ct!Ve lenses if scecmed betowt. ana c:an aisnnguasn ana differemiace ccnt:r21st ~ ccior.s us.ea in tnis memoca. .* I I Date *corT. Rea. Verified bv ~ Date Col'T. AeQ. Verified bv. 0707187 No Bettv Aldridae
- 7/5/88 No Bett~ Al dri da~ E I I
MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL I SCORES WEIGHT DATE Genent:
- 91. 42 0.3 Initial CMtifiation: 4/5/88 Sgec1tic: 92.00 0.3 Recenffiation:
Praet1ca1: 98.00 0.4 Recarnfic3DOn: Comoosrce
~4;~~ LO Recaruticat!On:
Recat atic:n:icn: Date: 12/11/87 r#1J-<.
- - . ./~ 'I 1~-S?R-Recemftc::mon:
I Resconsrole Level 111* r H i l fl f-' r *- Recertrficaaon~ REMARKS
- SwtRI Form QA-11*7 F-7
~\. .
~--*~4 SOUTHWEST RESEARGH INSTITUTE NONDESTRUCTIVE EXAMINATION l I : L-
. . L.
--,-:._* STATEMENT OF CERTIFlCATION The Director of the Department of Engineering Services, Nondestructive Evaluation Science and Technology Division, certifies tnat Leroy Duran is qualified as Level I in Magnetic Particle Testing in accordance with the requirements of SwRI Nuclear Quality Assurance Procedure 11-:. which incorporates the guidelines of SNT*
TC-1A, 1975 ar.d 1980 Editions. Certification Limitations: Certification valid only while employed by SwRI Special Qualifications lif anyl: None E.xpirauon Date: ~ I 07/23/90 Signed: 1)1/{IJMI/. I _J _4/o/11 Date: ~-1.I-!! Dir,ftor. Department of Engineering Services
. EDUCATION. TRAINING. ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING (This method and levell:
High School
*commonwealth of Va. 4 GRAD Date Comcleted 7/10/87 .
Additional:* Hours: 18 Location: SwRI I Major Field of Study I Date employed by SwRI: 7/30/84 Pl"l!Yious NOE experience lif used for qualification!: The individual has been credited with 4 of experience in this examination method on the date of certification. Some of the experience mev have been accrued simultaneously with other NOE methods lat least 25% was in this methodl. months VISUAL ACUITY ANO COLOR PERCEPTION None COMPANY FROM TO The inaividual is capable of reading Jaeger Number 1 letters at 12 inches in at least one eve (using corrective lenses if specified belowl. ana can distinguish and differentiate contrast between colors used in this method. Date Corr. Req. Verified by Date Corr. Req. Verified by 7/17/87 No Heidi Gutierrez Lh 7l5l88 No B~tt~ AJdcjdge I b£. MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL I SCORES WEIGHT DATE General: 94.00 0.3 Initial Certification: 07l23l87 Specific: 79.10 0.3 Recertification: Practical: 100.00 0.4 Recertification: Composite 91.93 LO Recertification: Recertification: , Date: 7/10/87 Recertification: Responsible Level Ill:
~~-- li ,"J..~,.;9"$' Recertification:
REMARKS SwRI Form QA-11-7 F-8
- SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION The Director of the Oeoanment of Engineering Services. NondestrUetive Evaluation Science and Technology Division. certifies tnat _ __
Leroy Duran is qualified as Level* II in Visual Testing tVTI. categories VT-l, VT- 2 ' VT-3
- VT- 4 in accordanca with tne requirements of SwAI Nuclear Quality Assurance Procedure 11-2.
v..;;e;.;;d;....;b:.v.;.._.-S.-w~R"'I.___________ Certification Limitationa: _...;;C..;;e:.;:r:..t::;;1::;*f=i.;;;c.;;;a..;;t;.;;i:.;:o:.;:n;;._v.;..a=l;:;:i.;;;d;.....;;o..;;n;:;:l:.v._*_w.;..h;.;;i=l.;;;e;.....;;e:.;:mo=l=o... I Expiration Oat{}/,
- o9 I 211 ~O -
Sig~~;--*--, ff IF;'JM.//-* -1 .;/-/tJJt/. *-* - Oaai: -41//UWd.~E.Hh//..t.'l'J
~irectar. Oepartrne ol Engineering Services I EDUCATION, TRAINING. ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING (This memod and leileU:
High School Commonweal th of Va. 4 GRAD Cate Completed __ 9_/_l_0_/_8_7_______ Hours: __2.;;.2;;...___ Locanon: _S_w_R_I_ _ __ Additional: - - - - - - - - - - - - - - - - - - - - - - - Major Field of Study _ _ _ _ _ _ _ _ _ - - - - - - - - Oat* emp1oyed by SwAl:_ _ _ _ _ 0_7..;./..;3..;0..;./..;.8;...4..;._______ Previous NOE expenence (if used for ouatificationl: The individual has been credited with 10 months FROM TO COMPANY of exi::ierience in this examination mmod on the date of certitic3tion. None Some of. the experience may have been accrued simultaneously with other NOE metnods tat least 2S% was in this method!. VISUAL ACUITI ANO COLOR PERCEPTION The individual is caoable of reaaing Jaeger Number 1 letters at 12 im:hes in at leait one eve lusing corrective lenses if sgecitied below!, and can distinguish and differentiate contrast between colors used in this mmod. Oate Corr. Aeq. Verified by Cata Corr. Aeci. Verified by 7/17/87 N'o Heidi Gutierrez.~ hkf 7/5/88* No Betty Aldridge MOST RECENT EXAMINATION GRACES
-------- ---------------- CSRTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT OAT'E General: *85.00 .33-1/3 Initial Certification: 09/21/87 Soeciftc: **91. 66 .33-1/3 Recertification:
~ractical: ***98.00 .33-1/3 Recanific:ation:
Comoosite 91.54 i.oo Recertification: Recertification: Oat~
*9/10/87***8/3/87* ' '
***8/4/87 Recertification:
Resi::ions1llle Levet Ill: ?'k.q i:.. n. uescner
~..-=
REMARKS
- SwAI Form QA-42-2 F-9
SOtl"l"HtJE5T_RESF.AR.CH INSTI'IUTE CERTIFICATION OF PERSONNEL QUALIFICATION FOR NUCLEAR INSPECTION AND TESTING ~-*-~ ____________~ __r_o_y_D_u_r_an is cer~ified- Level I for the performance of inspection and testing in accordance with SwRI Nuclear Project Operating Pro-cedure. X-FE-107 and ANSI N45.2.6 in VT-2, VT-3, Vi.-4
~-------------------------------------
Certification Limitations: Certification valid only while employed by SwRI. Physical Requirements: Verified by: Date: Correction Req'd: Jae2er Ill at 12" Bonnie Caudle( 7/17/87 No Jaeger #1 at 12" Betty Aldridge~ 7/5/88 No Certified by: Director* or Levels I, II or Vice Pre ident for Level III Expires: 11/23/90 Remarks: SwRI Form QA 51-1 F-10
Sonic Sys terns In tern a tional, Inc . Spcc:inlisls in Ulrrosonir: Tcsling and Ccrns11lling CERTIFICATE OF QUALIFICATION FOR STACY FREELAND Th e a fo re men t i o ne d i nd i vi du a 1 i s q u a* 1i f i e d i n a cc o r da nc e wi t h So n i c Systems lnternational's Training, Qualification and Certification Procedure Number SS!-A-005, which complies with the requirernents of the American Society for Non destructive Testing Recornniended Practice Numhe r SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated *
- UT .
NOE Method I Level 8/9/88 Date 8/9/91 Expires Examination Results 97.5 .3 29.25 General x = Specific 88 x .2 = 17.6 Practical 80 x .5 = 40 Composite Score = 86.85 xami ne r F-11
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Systems International, Inc. Sp1!c:10/1s1s 111 li/lrnso111e: Tt!sl111)l nml ~~~~~~~~~--~* CERTIFICATE OF QUALIFICATION FOR STACY FREELAND The a forernent i oned i ndi vi dual is qualified in accordance with Sonic Systems International 1 s Training, Qualification and* Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification* is based on background training, examination, and evaluation methoci inciicated. PT I 8/9/88 8/9/91. NOE Method Level Date Expires Examination Results General 100 x .3 = 30 Specific 98 x .2 = 19.6 Practical 90 x .5 = 45 Composite Score = 94.6 c F-12
- Sonic Systems Jnternational, Inc.
Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION
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FOR DAVID GARCIA The aforementioned individual is qualified in accordance with _Sonic 0 Systems International 's Training, Qualification and Certification Procedu*re Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on backgroun*d training, examination, and evaluation method indicated
- Ultrasonic II 7/08/88 7/08/91 NOE Method level Date Expires Examination Results 92.5 .3 27 .75 General x =
98 .2 19.6 Specific x = 100 *5 50 Practical x = 97.35 Composite Score =
- xaminer Manager F-13
~~ii Sonic Systems International, Inc.
'~-~) Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR DAVID GARCIA The aforementioned individual is qualified in accordance with Sonic Systems International 1 s Training,' Qualification and Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on *background training, examination, and evaluation method* indicated.
Liquid Penetrant II 7/08/88 7/08/91 NOE Method Level Date Expires Examination Results Genera 1 83.5 x .3 = 25.05 Specific 100 x .2 = 20 Practical 100 x .5 = 50 Composite Score = 95.05 xami ner Manager F-14
- Sonic Systems International, Inc.
Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR DAVID*GARCIA The aforementioned individual is qualified in accordance with Sonic Systems International 's Training, Qualification and Certification* Procedure *Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation .. method indicated
- Magnetic Particle II 7/08/88 7/08/91 NOE Method Level Date Expires Examination Results Genera 1 96.7 x .3 = 29 Specific 85 x .2 =
17 Practical 95 x .5 = 47.5 Composite Score = 93.5
- Examiner F-15
nnlt\ fl'QJ.'1' Sonic Systems International, Inc . Specialists in Ultrasonic Testing and Consulting
~~~~~~~------~--------~*
CERTIFICATE OF QUALIFICATION FOR DAVID G. GARCIA Th.e. aforementioned individual is qualified in accordance with Sonic Systems International 's Training; Qualification and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background. training, examination, and evaluation method indicated. VISUAL, VT-1 NOE Method II Level 7 /08/88 Date 7/08/91 Expires Examination Results General 96. 7 x .3 = 29 Specific 98 x *2 = 19.6 Practical 100 x .5 = 50 Composite Score = 98.6 Certified NOE Level III Examiner Manager F-16
- Sonic Systems International, Inc.
Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR DAVID GARCIA The aforementioned individual is qualified in accordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training,
- . *examination, and evaluation method indicated
- Vis ua 1, VT -3 NOE Method II Level 7/08/88 Date 7/08/91 Expires Examination Results 82.5 x .3 24.75 Genera 1 =
90 x .2 18 Specific = 87.. 5 x .5 43.75 Practical = 86.5 Composite. Score =
- Certified NOE Level I II Examiner Manager F-17
*~~j§~ i Sonic Systems International, Inc.
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CERTIFICATE OF QUALIFICATION FOR JEFFERY L. HANES The aforementioned individual is qualified in accordance with Sonic Systems International 's Training, Qualification and Certification Procedure Number SSI-A-005, which complies with the requir'ements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated. i ULTRASONIC I 02/17/89 02/17/92 NOE Method Level Date Expires Examination Results General 75.0 % x .3 = 22.5 Specific 87. 5 x .2 = 17.5 Practical 95.0 x .5 = 47.5
. Composite Score = 87.5 %
c1d:r~N~ Examiner. F-18
- Sonic Systems International, Inc.
Specialists ~n Ultrosoni.c Testing and Consulting_ CERTIFICATE OF QUALIFICATinN FOR JEFFERY L. HANES The aforementioned ind.ividual is .qualified in accordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated
- LIQUID PENETRANT I 02/17/89 02/17/92 NOE Method Level Date Expires Examination Results General 70 x .3 = 21 Specific 70 x *2 = 14 Practical 95 x .5 = 47.50 Composite Score = 82.50
- Certified NOE Level III Examiner F-19
Sonic Systems International, Inc. Specialists in Ultrasonic Testing and Consulting CERTIFICATE dF QUALIFICATION FOR JEFFERY L. HANES Th*e aforementioned individual is qualified in ac.cordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestyuctive Testing Recommended Practice Number SNT-TC-lA. This certification is based on, background training, examination, and evaluation method indicated. MAGNETIC PARTICLE I 0/17/89 02/17/92 NDE Method Level Date Expires Examination Results General 90 x .3 = Specific 80 x .2 = 16 Practical 95 x .5 = 47.50 Composite Score = 90.50 Certified NDE Level III Examiner F-20
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SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION The Director of the Department of Engineering Services. Nondestructive Evaluation Science and Te.::hnology Division. certifies tnat John R. Ingamells is Qualified as Level I-Traineen Ultrasonic Testing in accordance with the requirement.s of SwRl_Nuclear Quality Assurance Pro!'.edure 11-1. which incorporates the guidelines of SNT-TC-lA. 1975 and 1980 Editions. Certification Limitations: Certification valid only while em:eloved bz SwRI I Special Qualifications lif anyl: None Exoi*~o"/l 09/30/90 signed: _:dtti*l:ir;;1r.k ,rC~( /rz. t1/1r Date: 7 I~() /17 Director. Department of'fngineering Services EDUCATION. TRAINING. ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING (This method and level): High School Fulton H. s. (NY) 4 GRAD Date Completed 6/25/81 Additional: Union Coll/Univ. of Wvo. 6 B. S.* & M.S - Hours: 4 Location: SwRI Major Field of Study Civil En~ineerin~ Date employed by SwRI: 08/17/81 Previous NOE experience (if used for Qualificationl: The individual has been credited with N/A months COMPANY FROM TO of experience in this examination method on the data of certification. None Some of the experience may have been accrued simultaneously with other NOE methods lat least 25% was in this methodl. VISUAL ACUITY AND COLOR PERCEPTION The individual is capable of reading Jaeger Number 1 letters at 12 inches in at least one eye (using corrective lenses_ if specified belowi. and can distinguish and differentiate contrast between colors used in this method. Dai 6/24 87 Corr. ReQ. Yes Heidi Verified by Gutierrez~ I Date Corr. Req. Verified by 6/ 2£'.'.88 Yes Betti'. A1dri dge ,.......f MOST RECENT EXAMINATION GRACES CERTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT DATE General: N/A Initial Certification: 09 L22.::'.81 Specific: N.::'.A Recertification: 09/21/84 Practical: N.::'.A Recertification: 09.::'.30.::'.87 Composite N.::'.A Recertification: Recertification: Date: N/A Recertification: Resoons1ble Level Ill: NIA Recertification: REMARKS SwRI Form QA-11-7 F-21
*SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION The Director at the Department of Engineering Services, Nondestructive Evaluation Science and Technology Division. certifies tnat John R. Ingamells is qualified as Level I-Trainei;n Testing in accordance 'l':ith the reouiremems of SwAI Nuclear Quality Assurance Procedure 1~-1. which incorporates the guidelines of SNT-TC-1A. 1975 ar.d 1980 Editions.
Liquid Penetrant Certification Limitations: _ _' --~C_e_r;...t;;.i_*_f_i;...c;...a_t_i_o_n.;....v_a...;.;;;l;.;:i..:d;;._o;;.n=l"'-y....;.;*w.;.;h=i;.;:1;.;e;..._e_!llP_.._l'""o_y.__e-'d;.....;b;;..y.__-"S-w-'R"'I;;...________ Special Quali.fications tif anyl: _ _....;;.N..:o;.;n.;;.e;;__.____________________________.;...._ _ _ Expiration Date: _ _ _ _ _ _ _.;;.0.:.9..:../..::3..;::0..:/..:9..:0;;..'_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
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j' /. *I ' I , : ' ,,.... 1 /_ I "- Signed:_~/-,*~,{~*;~*~*~~f~_......*~-*~&;_;';~~..:,./._:;_-'_;V;_'~;;_U..:,.V';_l;;_v_'l_J_ _v_V_;...//_ _ _ _ _ __ 1 Date: _.._<J._/_3.,.,..')_~_7...._ _________ Di~tor. Department of Engineering Services EOUCAT10N. TRAINING, AND EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING (This method and levell: Fulton H. S. (NY.) 4 GRAD High S chool Date Completed --'6"-'/-'2:;.;5-../..;8;;.;l=-------- Additional: Union Coll/Univ. of Wvo__,._ _6__ B.S. & M.S Hour.s: _ _4 _____ Location: SwRI Major Field of Study Civil Ens;ineering Date employed by SwRI: _ __,0_8_/_,1-..7_/_8-..l=----------- Previous NOE experience !if used for qualificationl: The individual* has been credited with _ _ _ _N ......./_A_____ months ) COMPANY FROM TO of exgerience in this examination method on the date of certification. None Some of the exgerience may have been accrued simultaneously with other NOE methods tat least 25% was in this methodl. VISUAL ACUITY ANO COLOR PERCEPTION The individual is cagable of reading Jaeger Number 1 letter.sat 12 inches in at least one eye !using corrective lenses if scecified belowl. and can distinguis'1 and differentiate contrast between color.s used in this metnod. 6 / ~4i 8 7 Corr. ~:S Verified by j Date Corr. Reci. Verified bV Heidi Gutierrez :~ 6/2/88 Yes Betty Aldridqe ~~ MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT DATE General: N/A Initial Certification: 09/22/81 Scecific: NIA Recertification: 09/21/84 Practical: N/A Recertification: 09/30/87 Comgosite NIA Recertification: Recertification: Date: _ _ _ _ _ _ _N_/A ___________ Recertification: Rescons1ble Level Ill: _ ...".'1-.'._/..._A_ _ _ _ _ _ _ _ _ _ __ Recertification: REMARKS SwRI Form QA-11-7 F-22
SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION The Director of the Decanment of Engineering Services. Nondestructive Evaluation Science and Technology Division. certifies tnat
*John R. Ingamells is qualified as Level I-Trainetti Magnetic Particle Testing in accordance ll':ith the requirements of SwRI Nuclear Quality Assurance Procedure 11-1, which incorporates the guidelines of SNT-TC-1A. 1975 ar.d 1980 Editions. **
- Certification Limitations: _ _ _ _ _ c_e_r_t_i_*_f_i_c_a_t_1_*_o_n;.....v_a_l..;;....;i....;d;;.....o;..n_l....;Y..__w....;h....;1;;;;*.;;;l....;e_e_mp
........;;;l;...o_.y.._e_d_....;b""y..__S_w""R""I..._________
Special Qualifications tif anyl: _ _ _ N_o_n_e_...._--------------------------------- Expiration Date: 0 9 / 30 / 90
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___.f+-/.....~-J/:_f'_________ 7 _ Signed: /,,,Jt/f,{;7 /,'<!:t/;.:f A?':'--Ctr/' -M 1-i' / ,- Date: Directer. Department ot"Engineering Services EDUCATION. TRAINING. AND EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING !This method and levell: Fulton H. S. (NY) 4 GRAD Date Completed __6__ /_2_5_,,/_8_1_______ High School Additional: Union Major Field of Study Coll/Univ. of Wvo_._ _6__ B.S. & M.S Civil Engineering Hours: _ _ 4_____ Location: --=S-w;..:R'-"I==---- Date employed by SwRI: _ _ _0_8_/_1_7_/_8_1 _ _ _ _ _ _ _ _ __ Previous NOE experience lit used for qualificationl:
- The individual has been credited with _ _ _ _N_/_A ______ months of experience in this. examination method on the date of certification.
Some of the experience may have been accrued simultaneously with other NOE methods lat least 25% was in this methodl. VISUAL ACUITY ANO COLOR PERCEPTION. None COMPANY FROM TO The individual is capable of reading Jaeger Number 1 letters at 12 inches in at least one eye (using corrective lenses if scecitied betowl. and can distinguish and differentiate contrast between colors used in this method. 6 /~4is7 Corr.~~ Verified by Heidi Gutierreze&2;
, Date Corr. Req. Verified bv 6/2/88 Yes Betty Aldridge *'
I MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT DATE General: N/A Initial Certification: 09/22/81 Specific: NIA Recertification: 09/21/84 Practical: N/A Recertification: 09/30/87 Composite NIA Recertification: Recertification: Date: _________N_/A----------...:....-- Recertification: Resconsible Level Ill: _ _,N...._/...,A..____________ Recertification: REMARKS SwRI Form QA-11*7 F-23
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~ R l~~,d.;. NONDESTRUCTIVE EXAMINATION r-------fll:._~_::;*_:_0_;1/7'~_._,_~-------------S-TA_T_E_M_E_N_T_O_F__C_E_RT-l-Fl_C_A-Tl_O_N__________-_ _______________---!
The Director of the Department of Engineering Services. Nondestructive Evaluation Science and Technology Division, certifies that _ __ 4 John R. Ingamells isqualifiedasLevel I-TR inVisualTesting!VTJ,categories VT-1, VT-2, VT-3, VT-in accordance with the requirements of SwRI Nuclear Quality Assurance Procedure 11-2. Certification Limitations: _ _...;C:::.;e;;;.r;:...;;;t;;;i..;:f..;:i;...;c;...;a;;.t;;.;i;;..o;::.;n;...;_..;.v..::a;.;;l;;:i:.;d;;.._o;;.n=l:,:;.Y_;.W;..;h;;.;1;;.*l;;;.e~_e_m.;.p...;l;;.o...::y;...e_d __ b.._y_S_w_R_I _ _ _ _ _ _ _ _ __ Expiration D<j.':
- 09 /30 /90 sign~-::-mt.:?:l?!Attn;, _(~r.-v'/,;,_, t~ Date:
Director, Deoartment of Engineering Services EDUCATION, TRAINING. AND EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING !This method and leveU: High School Fulton H. S. (NY) 4 GRAD Date Completed_.... 6"'"/....2_s_/_8""'l...__ _ _ _ ___ Additiona1:Union Coll/Univ. of Wvo~*:...____;6;;..__B.S. & M.S. Hours: _ _....4_ _ _ _ Location: _....;S::..;w::..R=I_ __ Major Field of Study Civil Engineerin...g,___ _ _ - - - - - Date employed by SwRl:_ _ _ _ _ o..s.../_1_7....;/_8_1_ _ _ _ _ _ _ __ Previous NOE experience. !if used for qualification1: The individual has been credited with N /A months FROM TO COMPANY of experience in this examination method on the date of certification. None Some of the experience may have been accrued ~imultaneously with other NOE methods lat least 25% was in this method!. 1----------------------------------------------------. VISUAL ACUITY ANO COLOR . PERCEPTION The individual is capable of reading Jaeger Number 1 letters at 12 inches in at least one eye (using corrective lenses it specified below>. and can distinguish and differentiate contrast between colors used in this method.
. .------------------------------------------...; 1*
Date Corr. Req. Verified by Date Corr. Req. Verified by I
- 6/24/8_7____Y_e_s___H_e_1_._d1_._Gu_t1_*_er_r_e_z_;._;,:a.;;....;";.;.___
6/2/88 ____ Ye_s_ Betty Aldridge~ MOST RECENT EXAMINATION GrlAOES CERTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT DATE General: N/A Initial Certification: 09/22/81 Soecific: NIA Recertification: 09/21/84 Practical: N/A 09/30/87 Recertification: Comoosite N/A Recertification: Recertification: Date: _________N,-:""7/~A___________________ Recertification: IA________________ Resoonsible Level Ill: __N_r__ REMARKS SwRI Form QA-42-2 F-24
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V,1 / NONDE*STRUCTIVE EXAMINATION. STATEMENT OF CERTIFICATION The Director of the Department of Engineering Services; Nondestructive Evaluation Science and Technology Division, certifies that Michael w. Kleinjan is qualified as Level II in Ultrasonic Testing in accordance with the requirements of SwRI Nuclear Quality Assurance Procedure 11-1, which incorporates the guidelines of SNT* TC*lA, 1980 Edition. Certification Limitations: Certification valid only while emEloved bv S~B.I Special Qualifications !if anyt: None E.lcpiration Date: 1723790 Signed: M 1~ ~ Director, Dapartment of Engineering Services Date: '3 L I 1 'f li1 EDUCATION. TRAINING. AND EXPERIENCE HISTORY I EDUCATION: NAME YEARS DEGREE TRAINING !This method and levelt: High School Adult H.S. ~Neb) 3 Grad Date Comoieted 1 ll~LSZ Additional: S.E.Comm.ColiUniv(Nebl 1 No Hours: S? Location: ~w:BI Major Field of Study I Date employed by SwRI: 7/30/84 F'revious NOE experience iif used tor *qua1ificationl:
- The individual has been credited with q of exoerience in this examination method on the date of CP.rtitication.
Some of the experience mav have been accrued simu1taneously with otner NOE methods lat least 25% was in this methodl. months VISUAL ACUITY ANO COLOR PERCEPTION COMPANY None FROM TO I The inaividual is capable of reaaing Jaeger Number 1 letters at 12 inches in at least one eve Jusing corrective lenses 1f scec1iied belowl. ana can aistinguisn and differentiate contrast between colors used in this metnod. Date 9L22/86 Corr. Rea. No Verified by Heidi Gqrierr<>z Date 8/18/88 Corr. Rea.
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Verified Huffman w . 9/21L87 No
- He;i.i;ij, Gi.u:i~r:i:~ z 8/18/88 ::-lo Betty Aldridge MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL I SCORES WEIGHT DATE General:
- 92.~Q Q 3 Initial Certification: lL23L8Z Specific: ** 92.00 Q,3 Recertification:
Practical: *** 94.50 QI fl Recert1ticat1on: Comoos1te 93.20 l.Q Recertification: Recertification: Date:*l/7/87; *~l/15/§7; ***l/16)87 Recert1r1cat1an: L,~ )J /;-?/, ( J~1 lffe 1 7.1./ll' Resoons1ble Leve1 Ill:
/I ,J * ..). . -'*rn.* e Recert1ficat1on:
.J ' REMARKS I i
EPRI I GS CC Qualificacions Xanual Deteccion Reissued to correct: name of high school. I SwRI Form'QA-11*8 F-25
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1 STATEMENT OF CERTIFICATION The Director of the Department of Engineering Services, Nondestructive Evaluation Science and Technology Division. certifies that Michael W. Kleinjan is qualified as Level II in Lim.iid P~net:i::ant Testing in accordance with the requirements of SwRI Nuclear Quality Assurance Procedure 11*1, which incorporates the guidelines of SNT* TC- 1 A. 1980 Edition. Certification Limitations: Certification valid only while emEloyed by SwRI Special Qualifications lif anyl: None Expiration Date: 6/22/90 Signed: lhwl~ ~ Date: !(!j-/._fl Director, Dapartment of Engineering Services EDUCATION. TRAINING, AND EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING (This method and level): Adult High School(Neb) 3 Grad Date Completed 6/11/87 High School Additional: S.E.Comm.Coll/Univ.o£Neb. 1 No Hours: 18 Location: SwRI Major Field of Study Date employed by SwRI: 7/30/84 Previous NDE experience lif used for *qualification): The individual has been credit~d with 5 months COMPANY FROM TO of excerience in this examination metnod on the date of certification. None Some of the experience may have been accrued simultaneously with other NOE methods lat least 25% was in this methodl. VISUAL ACUITY AND COLOR PERCEPTION I I The inaividual is cacable of reading Jaeger Number 1 letters at-12 inches in.at least one eye tusing corrective lenses if specified belowl. and can distinguish and differentiate contrast between colors used in this method. Verified~ 9 ft2.e/86conN~ea. Verified by Date Corr. Rea. Heidi Gutierrez 8ll8l88 No B. E:uf fman 9721787 No Heidi Gutierrez 8/18/88 No Betty Aldridge MOST RECENT EXAMINATION GRADES CERTIFICATION *HISTORY: THIS LEVEL I SCORES WEIGHT DATE General: 83.35 0 * .3 Initial Certification: 6l2? L8Z 90.00 0.3 Recertification: Sceciiic: 100.00 0.4 Recertification: Practical: Comcos1te 92.00 LO Recertification: Recertification: Date: A6/ll/87
- .1 ' Recert1t1cation:
Rescons1ble Level Ill:
\.L_ _(1, i//c. (_v1 fl.ii RP.certification:
I I J *I M.--.ll>~-'lo J
- 1 REMARKS I I
Reissued to correct name of high school. SwRI Form QA-11-8 F-26
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.SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION The Director of the Department of Engineering Services, Nondestructive Evaluation Science and Technology Division, certifies that Michael W. Kleinj an is Qualified as Level II in Magnetic Particle Testing in accordance with the requirements of SwAI Nuclear Quality Assurance Procedure 11*1, which incorporates the guidelines of SNT*
TC* 1A. 1980 Edition. Certification Limitations: _ _ C_e_r_t_i_*f_i_*_c_a_t_i_o_n_v_a_l_i_d_o_n_l-'y'---w_h_i_l_e_e_m....:p._l_o_y.__e_d_b....:;y_S_w_R_I___________ Special Qualifications (if anyt: ___ N_o_n_e---------------------------------- Expiration Date: 8/26/ 89 Signed:--.............!lUd
- __._rft...__W____....__~-* _ __ Date: ---=3=-/'--t!J_....J.../~g_1_ _ _ _ _ _ __
Director, Dapartment of Engineering Services EDUCATION. TRAINING. ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING (This method and levell: High School Additional: Adult High School(Neb) 3 S.E.Comm.Coll./Univ.ofNeb.l:;......;;.;...;;... Major Field of S t u d y - - - - - - - - - - - - - - - - - - - - No __ Grad Date Completed _....;5~/:....;;.3.::.0:../..::;8..::;6_______ Hou~: ___2_0 ____ Location: __S_w_R_I___ Date employed by SwRI: _ _Z...._/... 3,..0..,/_,,8..4..____________ Previous NOE experience (if used for *c:iualificationt:
- The individual has been credited with _ _ _ _4_______ months of experience in this examination method on the date of certification.
Some of the experience may have been accrued sir:nultaneously with other NOE methods !at least 25% was in this method). VISUAL ACUITY AND COLOR PERCEPTION COMPANY None FROM TO The individual is capable of reading Jaeger Number 1 lette~ at 12 inches in at least one eye !using corrective lenses if specified belowi*. and can distinguish and differentiate contrast between colors used in this method. Oite / Corr. Req. Verified by Date Corr. Rea. Verified by 10 21 85 No Heidi Gutierrez 8/18/88_N~'~o_ _ ~B~e~t~t~y"'-~~.J~d*r~i~d~g~e=----- 9/22/86 No Heidi Gutierrez 8/18/8 8 -.:.:N=o__ _.Bw.____..H..,..u.,f.,fm...,a-..n...._,;J..:u-..,ft.___ __ 9/21/87 No Heidi Gutierrez MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL
- SCORES WEIGHT DATE 83.50 0.3 Initial Certification: 8/26/86 General:
Specific:
- 93. 40 0. 3 Recertification:
Practical: 99.00 0.4 Recertification: Comoos1te 92.67 1.0 Recertification: Recertification: Date: _ _ _ _ _ _....._ ,.,....::5'-',/.. .::3:.;:10., ,/. . ::8::.. :6..c;.,. ,._. ,. .;.,. ,__,,...
,f.,..,'-- Recerut1cation:
Aesoonsible Level Ill: _,.l..l,';H!..~*~*+
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' AP.certification:
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REMARKS Reissued to correct name of High School. I SwRI Form QA-11*8 F-27
SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION The Director of the Decianment of Engineering Services. Nondestructive Evaluation Science and Technology Division, certifies that _ __ Michael W* Kleinj an is qualified as Level II in Visual Testing IVTl, categories VT-1, VT-2, VT-3, VT-4 in accordance with the requirements of SwRI Nuclear Quality Assurance Procedure 11-2. Certification Limitations: Cert:ification valid only while emploved by SwRI Expiration D~ 8 /9 2 Signed:___ . - ~ K~
- Date:
Director. Decartment of Engineering Services EDUCATION. TRAINING. ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEG A EE TRAINING (This method and levell: High School Adult High S chool(Neb) 3 Grad Date Comcileted _ _1..1...2_z._/._8.._9..__ _ _ _ _ __ Additional: S.E.Comm.Col/Univ.ofNeb. l No Hours: 12 Location: _s....,w....R...I_ _ __ Major Field of Study _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - Date emcloved by SwRl:_ _ _ 7_/_3_0_/_8_4____________ Previous NOE experience tif useo for aualificationl: The individual has been credited with _ ...3...__ months FROM TO COMPANY of experience in this examination method on the data of certification. None Soma of the excerience mav nave bean accrued simultaneously with other NOE methods lat least 25% was in this ma1nodl. ~~~~~~~~~~~----~-V-IS_U_A_L_A_C_U-ITY __A_N_O_C_O_LO_R_P_E_R-CE-P-Tl_O_N--~~~~--~----~~~~~I The individual is capable of reading Jaeger Number 1 letters at 12 inches in at least one eye lusing corrective lenses if specified belowl. and can distinguish and differentiate contrast between colors used in this method. Date Corr. Req. Verified by Date Corr. Req. Verified by 8/18/8_8_ _:r_o_B. Huffman 4#'
~----- ----------------- ~------ --------------------
~-------------------
MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT DATE General: 76.9 .33 1/3 Initial Certific<Jtion: 2/8/89 Specific: 88.0 . 33 1/3 Recertification: Practical: 97.5 .33 1/3 Recertification: Composite 87.43 1.00 Recertification: Recertification: Date: 1'"11/27}89 . .~ ,~ Recertification: Rescons1b1e Level Ill: ~ "'y M'J. lf.f'c ( i~JIJ::.£(1( 1 .J * .JI. ;:1t...<\r.Jtae
-/ . REMARKS Reissued to correct name of high school.
SwAI Form QA-42-2 F-28
- SOUTHWEST RESF.ARCH I~STITUTE CERTIFICATION OF PERSONNEL QUALIFICATION FOR NUCLEAR INSPECTION AND TESTING
____M_i_c_h_a_e_l__Kl _________ is certified 1_e_v_e_l__I____ for the performance of __e_i_n_j_an inspection and testing in accordance with SwRI Nuclear Project Operating Pro-cedure X-FE-107 and ANSI N45.2.6 in ___v.T~--~~1..__V~T~--3....__VT--...-_4.._____________________ Certification valid only while employed by SwRI. Certification Limitations: Physical Requirements: Verified by: Date: Correction Req'd:
- Iaeaer IEJ at 12"
'Jaeger #1 at 12 11 Bonnie caudlei{'
Betty 9/21/87 Aldridge~8/18/88 No No Certified by: or Levels I, II or dent for Level III Expires: ___l_l_/_2_3_/_90~~~--------------------- Remarks:
- SwRI Form QA 51-1 F-29
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~~r~ Sonic Systems International, Inc.
Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR JEFFERY W. LONG The aforementioned individual is qualified in accordance with Sonic Systems International 's Training, Qualification and Certification* Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Test~ng Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated. ULTRASONIC I 02/16/89 02/16/92 NOE Method Level Date Expires Examination Results General 88.75 x .3 = 26.6 Specific 90.0 x *2 = 18.0 Practical 95.0 x .5 = 47.5 Composite Score = 92.1 % Certified NOE Level I I I Examiner Manager F-30
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- Sonic Systems International, Inc.
Specialists in Ultrasonic Testing and Consuliing CERTIFICATE OF QUALIFICATION FOR JEFFERY W. LONG The aforementioned indi.vidual i.s qualified in accordance with Sonic Systems International 1 s Training, -Qualification and Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated
- LIQUID PENETRANT I *T 02/16/89 02/16/92 NOE Method Level Date Expires Examination Results General 86.8 x = 26.0 Specific 90.0 x I 2 = 18.0 Practical 95.0 x .5 = 47.5 Composite Score = 91. 5 %
- Certified NOE Level III Examiner
*T Trainee until experience requirements F-31
Sonic Systems International, Inc. Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF OUAUFICATION FOR JEFFERY W. LONG The aforementioned individual is qualified in accordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-*A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examinatiorr, and evaluation method indicatedi MAGN~TIC PARTICLE I 02/16/89 02/16/92 NOE Method Level Date Expires Examination Results General 73.6 x .3 = 22.08 Specific 90.0 x .2 = 18.0 Practical 100.00 x .5 = 50.0 Composite Score = 90.08 % J~D~miner F-32
- Sonic Systems International, Inc.
Specialists in Ultrasonic Test.ing and Consulting CERTIFICATE DF QUALIFICATION FOR RICHARD P. LONG The aforementioned individual is, qualified in accordance with Sonic Systems International 's Training, Qualification and Certiffcation Procedure Number SSI-A-005, which complies with the requirernents of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certificati.on is based on background training, examination, and evaluation method indicated *
- ULTRASONIC NOE Method I
Level 09/30/87 Date 09/30/90 Expires Examination Results General 90.
--------- x .3 = 27.
Specific 85.
------- x .2 = 17.
Practical 90.
------- x .5 = 45.
Composite Score = 89. % C~ft-N~xami ner Manager F-33
Sonic Systems International, Inc. Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR RICHARD P. LONG The aforementioned individual is qualified in accordance with Sonic Systems International 's, Training, Qualification and Certification Procedure Number SSl-A-005, which c'omplies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is .based on background training, examination, and evaluation method indicated. LIQUID PENETRANT 09 /30 /90 NOE Method Level Expires Examination Results General x .3 = 25.0 Specific 80.0 x *2 = 16.0 Practical 90.0 x .5 = 45.0 Composite Score = 86.0 %
~~N~xaminer F-34
- 1 j~~Sii Sonic Systems International, Inc.
fl'Rifll:J Specialists in Ultrasonic Testing and Consulting
*'**rp!ll" CERTIFICATE OF QUALIFICATION FOR RICHARD P. LONG The aforementioned individual is qualified in accordance with Sonic Systems International 's Training, Qualification and Certification_:
Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training,
- examination, and evaluation method indicated
- MAGNETIC PARTICLE NDE Method I
Level 09/30/87 Date 09/30/90 Expires Examination Results General 72.2 x .3 = 21.66 Specific 95.0 x .2 = 19. Practical 80. x .5 = 40. Composite Score = 80.66
- Certified NOE Level 111 Examiner ssurance Manager F-35
il~~lia Sonic Systems International; Inc.
.J&Bi'IJ,:J Specialists in Ultrasonic Testing and Consulting
****11~
CERTIFICATE OF QUALIFICATION FOR RICHARD P. LONG The aforementioned individual is qualified in accordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation method.indicated. VISUAL VT-1 NOE Method I Level 03/31 /88 Date 03/31 /91 Expires
- Examination Results General 85. x .3 = 25.5 Specific 75. x .2 = 15.
Practical 92.5 x .5 = 46.25 Composite Score = 86.75 % Certified NOE Level Ill Examiner F-36
- t~~li~ Sonic Systems International, Inc.
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Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR RICHARD P. LONG The aforementioned individual is qualified in accordance with Sonic Systems Internat i ona 1 1 s Training, Qua 1ifi cat'ion and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated *
- VISUAL VT- 3 NOE Method I
Level 03/31/88 Date 03/31/91 Expires Examination Results General 95. x .3 = 28. 5 Specific 100.0 x .2 = 20.0 Practical 95.0 x .5 = 47.5 Composite Score = 96.0 %
- Certified NOE Leve 1 [I I Examiner F-37
Sonic Systems International, Inc. Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR RICKEY L. MAY The aforementioned individual is qualified in accordance with Sonic Systems International 's Training, Qualification and Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, ex~mination, and evaluation method indicated. ULTRASONIC II 3/13/89 3/13/92 NOE Method Level Date Expires Examination Results Genera 1 9~.o x .3 = 28.5 Specific 100.0
------- x .2 = 20.0 Practical 95.0 x .5 = 47.5 Composite Score = 96.0 Examiner Ouality~er F-38
.it1~=§ji Sonic Systems International, Inc.
- 'ARi1t:J .
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Specialists in Ultrasonic Testing and Consulting
. CERTIFICATE OF QUALIFICATION FOR RICKEY L. MAY The aforementioned individual is qualified in accordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated *
- LIQUID PENETRANT NOE Method II Level 3/13/89 Date 3/13/92 Expires Examination Results General 80.2
------- x .3 = 24.0 Specific lOu.O
------- x *2 = 20.0 Practical 100.0
------- x .5 = 50.0 Composite Score = 94.0%
Cer xaminer Manager F-39
f**=-*:a;tl:I
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!ald Specialists in Ultrasonic Testing and Consulting -
CE~TIFICATE OF QUALIFICATION FOR RICKEY L. MAY The aforementioned individual is qualified in accordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-005, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-lA. This certification is based on background training; examination, and evaluation method indicated. MAGNETIC PARTICLE NOE Method II level 3/13/89 Date 3/13/92 Expires
- Examination Results General
- 73.6 x .3 = 22.0-Specific 100.0 x .2 = 20.0 Practical 100.0 x .5 = 50.0 Composite Score = 92.0%
Certified NOE Level III Examiner Manager F-40
Sonic Systems International, Inc . Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR RICKEY L. MAY The aforementioned individual is qualified in accordance with Sonic Systems International 1 s Training, Qualification and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for Nonde'structive Testing Recommended Practice Number* SNT-TC-lA. This certification is based on background training, examination, and evaluation method indicated *
- VISUAL, VT-1 NOE Method II Level 3/13/89 Date
?/13/92 EX:pi res Examination Results General 86.8 x .3 = 26.0 - Specific 86.8 x .2 = 17. 3 Practical 95.0 x .5 = 47.5 Composite Scdre = 90.8%
Certified NOE Level I I I Examiner F-41
"**==1...1 b~~§ f\, SoniC Systems International,: Inc.
1Rt;;1: Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR RICKEY L. MAY The* aforement-ioned individual is qualified in accordance with Sonic Systems International's Training, Qualification and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for *Nondestructive Testing Recommended Practice Number SNT-TC-lA.
- This certification is based on background training, examination, and evaluation method indicated.
VISUAL, VT-2 II 3/13/89 3/13/92 NOE Method Level Date Expires Examination Results General 100.0 x .3 = 30.0 Specific 95.0 x .2 = 19.0 Practical 100. 0 x .5 = 50.0 Composite Score = 99.0% wti~~~ Ill Examiner F-42
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Specialists in Ultrasonic Testing and Consulting CERTIFICATE OF QUALIFICATION FOR RICKEY L. MAY The aforementioned individual is qualified in accordance with Sonic Systems International 's Training, Qualification and Certification Procedure Number SSI-A-011, which complies with the requirements of the American Society for Nondestructive Testing Recommended Practice Number SNT-TC-.lA. This certification is* based on. background training, examination, and evaluation met~od indicated *
- VISUAL, VT-3 NOE Method II Level 3/13/89 Date 3/13/92 Expires Examination Results General 90.0 x = 27.0 Specific 95.0 x *2 = 19.0 Practical 95.0 x .5 = 47.5 Composite Score = 93.53 Certified NOE Level III Examiner F-43
~~~ .SOUTHWEST RESEARCH INSTITUT.E
~~~-
~R.1 ~ NONDESTRUCTIVE EXAMINATION l g 'JL.Lv./ ./.,,..:"
1
'.; STATEMENT OF CERTIFICATION The Directer of. the Department cf Engineering Services. Nondestructive Evaluation Science and Technology Division, certifies that Cbd s tcpbe:i:: 8.. MiilQ:t: is qualified as Level II in Illt:t:aSQDi~
Testing in accordance with the requirements of SwRI Nuclear Quality Assurance Procedure 11-1, which incorporates the guidelines of SNT-TC-lA. 1980 Edition. Certification Limitation::: C~;c:tifi~ati&:m ~a lid Cill:::Z: whil~ ~milc:::z:~d .b:::z: S~B.I Special Qualifications (if anyl: NnTIP Expiration Date: 1/ 19 I 91 Signed: /)J;w;i ~ ~ Date: ; .
-z./._z(_r1
- Director, Dapartment of Engineering Services EDUCATION. TRAINING. ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING (This method and levell' High School Two Harbors H.S. 4 Grad Date Completed 2/25/852 1/13/88 Additional: Hours: 60; 11 Location: SwRI Major Field of Study Date employed by SwRI: 5116/83 Previous NOE experience !if used for *qualifi~tionl:
The individual has been credited with ?7 months COMPANY FROM TO of experience in this examination method on the date of c~rtification. ~CDe Some of the experience may have been accrued simultaneously with other NOE methods (at least 25% was in this methodl; VISUAL ACUITY AND COLOR PERCEPTION The individual is capable of reading Jaeger Number 1 letters at 12 inches in at least one eye (using corrective lenses if specified. belowl. ano can oistinguish and differentiate contrast between colors used in this method. Date Corr. Req. Verified by Date Corr. Req. Verified by 7/20/87 Yes Bonnie Caudle 7/20/88 Yes Bettz Aldridge MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT . DATE 97.67 0.3 Initial Certification: 4/9/85 General: Specific: 96.00 0.3 Recertification: 1/19!88 Practical: 95.50 0.4 Recertification: Composite 96.30 1.0 Recertification: Recertification: Date: 1/19/8§ - ., z Recert1t1cation:
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Resoonsible Level Ill:
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RP-certification: l/.J. ..1 .1 *'1.CArr1 1e
'.) REMARKS I I
EPRI I GS CC Qualifications Re-issued to revise EPRI qualification statement. SwAI Form QA-11*8 Manual Detection, Overlay Automated Detection F-44
- ~
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r-- SOUTHWEST R'ESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFlCATION The Director at the Department ct Engineering Services. Nonoestrucnve Evaluation Science ana Techno1ogy Division. certifies tnat ChristoQher A. Minor is aualitied as Level II in Liguid Penetrant Testing in accordance with the reau1rements ot SwRI Nuclear Quality Assurance Proceaure 11*1. which incorporates tne guidelines ot SNT* TC*1A. 1980 Edition. Certification Limitations: Certification valid onl;£ while emol O::£ed b;£ SwRI.
~pecial Quali~ications <if anvi: None Expiration Date: 9709791 Signed:
/)i;J ~ ku-I Date: ~!_~/1'7 Director. Department ot Engineenng Services EDUCATION. TRAINING. ANO EXPERIENCE HISTORY I EDUCATION: NAME YEARS DEGREE TRAINING IThis metnoa and levell:
High School Two Harbors H.S. 4 Gr:ad, Date Como1etea 9/25c'.85; 8/30/88 Additional: Hours: 10 i 12 Location: SwRI Major Field ot Studv I I Date employed by SwRI: 506c'.83 Previous NOE experience tit used for aualificationl:
- The individual has been credited with ?
of experience in this examination metnod on tne date of certification. Some of the expenence may have been accrued simultaneousiv with other NOE methods lat least 25% was in this metnoal. months VISUAL ACUITY ANO COLOR PERCEPTION None COMPANY FROM* TO The individual is capable of reaaing Jaeger Number 1 letters at 12 inches in at least one eve lusing correctJVe lenses if specified betowl. and can distinguish and differentiate contrast between colors used in this method. Date Corr. Rea. Verified bv Date Corr. ReQ. Verified by 7/2Q£'.88 y~~ 6e:tt:t: 8ldr:jdge MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL I SCORES WEIGHT DATE General: ~~.4Q Q,3 Initial Certification: 10/30/85 Soecific: 90.00 0.3 Recertttication: 9£'.09£'.88 Practical: 99.50 0.4 Recertification: Comoos1te 94.80 1. 0 Recernfication:
., .t Recertification:
Date: 8/30/88 /1 i~*&._
)
,I . Recerut1cat1on:
Resoons1ole Level Ill: J. J. McArdl e" - . //d, R!!Cert1ticat1on: REMARKS SwRI Form QA-11-8 F-45
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SOUTHWEST RESEARCH INSTITUTE
~R!f:::~, .~ NONDESTRUCTIVE EXAMINATION
. I
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STATEMENT OF CERTIFICATION The Director of the Department of Engineering Services. Nondestructive Evaluation Science and Technology Division. certifies that Christo12her A. Minor is qualified as Level II in M.agDetj C Pa:c:tj c: J e Testing in accordance with the requirements of SwRI Nuclear Quality Assurance Procedure 11-1, which incorporates.the guidelines of SNT* TC-1A, 1980 Edition. Certification Limitation!:: Certification valid only while em12loyed by SwRI Special Qualifications lif anyl: None e.,;,..,o" Ooi.JieJa!tua~;;(992 Signed: __yU/, ~ Date: 1/10/'l't.
' I D1rector, Dapartment of Engineering Services EDUCATION. TRAINING, ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE. TRAINING (This method and levell:
TWo Harbors H.S. 4 GRAD 1 ., L09: ms High School Additional: Date Comoleted Hours: 1? Location: SwBI .* Major Field of Study Date employed by SwRI: 05/16/83 Previous NOE experience lit used for *qualificationl: The indivi'dual has been credited with 3 of experience in this examination method on the date of certification. Some of the experience may have been accrued simultaneously with other NOE methods lat least 25% was in this method!. months VISUAL ACUITY ANO COLOR PERCEPTION COMPANY None FROM TO The inoividual is capacle of reaaing Jaeger Number 1 letters at 12 inches in at least one eye (using corrective lenses 1f specified belowi. ano can distinguish and differentiate contrast between colors used in this method. - Date Corr. Req. Verified by Date Corr. Rea. Verified by 7/20/88 Yes B. G. Huffman t.l# VIOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL SCORES WEIGHT DATE 96.6 0.3 Initial Certification: 12/12/85 General: 90.00 0.3 Recertification: 1/10/89 Specific: Practical: 99.00 0.4 Recertification: Ccmcosite 95.5 l.Q Recertification: Recertification: 01/06/89 Date: Responsible Level Ill: J. Xc.Ardle \/"'..... n CL /}J,/ / .//1 Recert1t1cation: v 11
.I I I.'-~<* -><:'f RPcertification:
REMARKS I ISwRI Form QA-11*8 F-46
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/7 SOUTHWEST RESEARCH INSTIT!JTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION .
The Director at trie Department of Engineering Services, Nondestructive Evaluation Science ana Techr:ology Division, certifies tllat Christopher A. Minor isqualifiedasLevet II inVisualTestinglVTl,categories*VT-1, VT-2, VT-3,
--- VT-4 in accordance with the requirements of SwRI Nuclear Quality Assurance Procedure 11-2:
Certification Wmitations: Certification valid only while employed by SwRI Expiration Date:
,If 01/21/90,' I /l Signed: I / /J/Jj/l;(// J ,rJ'nJI,,/, Date:~ g1
...,. . lt//R'7 I )ifecrqf'. Department o~!fineering Services (/ I f
EDUCATION. TRAINING. AND EXPERIENOE HISTORY EDUCATION: NAME YEARS DEGREE TRAINING !This method and levell: High School Two Harbors H.S. 4 GRAD Date Completed 9/18/85; 1/15/87 Additional: Hours: 12; 20 Location: SwRI Major Field of Study Date employed by SwRI: 5/16/83 Previous NOE experience lit used for oualificationl: The individual has been cradited with 6 months FROM TO COMPANY of experience ln this examination method on the date of certification. None Some of the experience may have been accrued simultaneously with other NOE methods (at least 25% was in this method). VISUAL ACUITY AND COLOR PERCEPTION The individual is capable of reeding Jaeger Number 1 letters at, 12 inches in at lesst one eye (using corrective lenses if specified belowl, and can distinguisn and differentiate cont -ast between colors used in this method. DatP Corr. Req. Verified by Oat1 Corr. Req. Verified by 7/28/86 Yes Heidi Gutierrez fu 7/20/87 Yes Heidi Gutierrez A..fw:t 7/20/88 Yes Betti'. Aldridge lrd-" MOST RECENT EXAMINATION GRADES
' - CERTIFICATION HISTORY: THIS LEVEL I
SCORES WEIGHT DATE General: 90.00 .33-1/3 Initial Certification: 10/30/85 Specitic: 96.00 .33-1/3 01/21/87 Recertification: Practical: 100.00 .33-1/3 Recertification: Composite 95.33 1.00 Recertification: Recertification: 1/15/87 Date: Recertification: I Resaonsible Level Ill:
~. ~--~~
#~ii~ ~ /..l2.2lfJJ I I REMARKS
- SwRI Form QA-42-:Z F-47 I
SOUTIBJ:EST RESF.ARCH INSTITUTE CERTIFICATION OF PERSONNEL QUALIFICATION FOR NUCLF.AR INSPECTION AND TESTING Christonher Minor is certified Level II
- for the . performance of inspection and testing in.accordance with SwRI Nuclear Project Operating Pro-cedure X-FE-107 and ANSI N45.2.6 in VT-2, VT-3, VT-4
~~~..;.._~~~~~~~~~~~~~~~--
Certification Limitations: Certification valid only while employed by SwRI. Physical Requirements: Verified by: Date: Correction Req'd: Jaeger l!l at 12" Bonnie Caudle W 7 /20/87 Yes Aldridge~7/20/88 Jaeaer #1 at 12 Betty Yes 11 Certified by: Director' or Levels I, II or Vice Pr ident for Level III Expires:~____ 1_1_12_3_/_9_o________________________ Remarks: SwRI Form QA 51-1 F-48
- SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF, CERTIFICATl.ON The Vice President, Nondestructive Evaluation Science and Technology Division, certifies that Vic tor Morton is aua1ified as Level Ill in Ultrasonic Testing in accordance with the requirements ot SwRI Nuclear QualitV Assurance Procedure 11-1; which incorporates the guidelines of SNT-TC-lA, 1980 Edition.
~ -
Certification Limitations: Certification valid only while employed b'y SwRI Special Qualifications !if any): _Nlolo,ioj.j,nn.,.P..__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Expiration Oate:_..;;8..:../,..1~0;..:/...;9;;..l=.-_ _ _ _ _~--"""'--------------------------- Signed: _*_..-/ZJ__... .~ . . . . . -----*-£_.-~--------------- Vice President, Nondestructive Evaluation Science and Technology Division Oate: _2_-_2_-Y__._7____ EDUCATION ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE Previous NOE E.xoenence lif used for oua1ificationl: COMPANY FROM TO High School Colston Senior Secondary 4 Grad GED None Additional:
- Major Field of Study _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
Oate employed by SwRI: 9/24/79 . The individual has been credited with at least in thi!I examination method on the date of certitication. Some of the experience may have been accrued simu11aneous1y with other NOE methods lat least 25% was in this methodl. 48 months of excerience VISUAL ACUITY ANO COLOR PERCEPTION The individual is capaole of reaaing Jaeger Number I letters at 12 inches in at least one eye (using corrective lenses it spec1tied belowl. and can distinguisn and differenuate contrast between colors used in this method. Cate Corr. Rea. Verified by Date Corr. Req. Verified bv 7/7/88 No Martha Pogue MOST RECENT EXAMINATION GRADES CERTIFICATION HISTORY: THIS LEVEL WEIGHT SCORES SCORES DATE Sasic 3 97.14 29.14 Initial Certification: 8/10/88 Soec1fic . 97.50 39.00 Recertification: Method .3 94.94 28.48 Recert1tication: Comoos1te Recertification:
~5 f2 2
~n Recertitication:
Resoons1b1e
*.eve1 Ill '2.-l -d"'z Receruticat1on:
REMARKS EPRI IGSCC Qualifications Manual Detection Automated Detection I Re-issued to add EPRI qualification statement. SwR1 Form QA-.. 4-3 F-49
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SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION I The Vice President, Nondestructive Evaluation Science and Technology Division, cenifies that Victor Morton is Qualified as Level Ill in Liguid Penetrant Testing in accordance with the requirements of SwRI_ Nuclear Quality Assurance. Procedure 11-1, which incorcorates the guidelines of SNT-TC*1A. 1980 Edition. Certification .Limitations: Certification valid onlv while emEloved bv SwRI- - Scecial Qualifications (if any1: None Exciration Oate: Januarv 9 1 1992 Signed:
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Vice President, Nondestructive Evaluation Science and Technology Division Date: L-7-P~ EDUCATION ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE Previous NOE Excenence lit used ~or oua1ificationl: Colston Senior Secondarv4 Grad GED COMPANY FROM ro High School None Additional: Major Field of Study Date employed by SwAI: 09/.2409 . The individual has been credited with at least 48 months of excenence in tnis examination method on the date of certification. Some of the excenence may have been accrued simuitaneous1v with otner NOE metnods lat least 25% was in :his metnodl. VISUAL ACUITY ANO COLOR PERCEPTION I The inaividual is capable of reading Jaeger Number 1 letters at 12 inches in at least one eye (using corrective lenses 1f scec1iied be!ow). and can distinguish and differentiate contrast between colors used in this metnoa. I Cate Corr. ReQ. Verified by , Cate Corr. Req. Verified by i 17 /88 No B. G. Huffman /JW MOST RECENT EXAMINATION GRAOES CERTIFICATION HISTORY: THIS LEVEL i WEIGHT SCORES SCORES DATE 3asic 3 97 .14 '29.14 Initial Certification: 1/9/89 Scec1tic .! lOQ Recertification:
"-0 00
~.1etnaa '.l 90. 77 27 .23 Recertification:
Ccmcos1te 96. 37 Recertification:
~J- /-z.-aJ.
-=esoons1ble Recertification:
~=ve1 Ill Recertification:
I REMARKS Swril Form (i,:...~.3 F-50 I
- *~>~
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I
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SOUTHWEST RESEARCH INSTITUTE NONDESTRUCTIVE *EXAMINATION STATEMENT OF CERTIFICATION, I I The Vice President. Nondestructive Evaluation Science and Technology Division. certifies that Victor HortQD is Qualified as Level Ill in Magnetic Particle Testing in accordance with the requirements of SwRI Nuclear QualitY Assurance Procedure 11*1. which incorporates the guidelines of SNT* TC* 1A, 1980 Edition. Certification Limitations: Valid onlv while em:12loyed bv SwRI Special Qualifications lif any1:
- None
~992z.
Expiration Date: Signed: 7Z/~ Vice President. Nondestructive Evaluation Science and Technology Division Date: ! -7'-P? EDUCATION ANO EXPERIENCE HISTORY I EDUCATION: NAME e.~cerience
- YEARS DEGREE Previous NOE COMPANY tit usea for oua1ificationl:
FROM .. TO High School CQl:;J:Q!l. S!iilJiQI ssis:Qo!lao 4 !.ZEAD Additional: GED None
- Major Field of Study Date emc1oyed by SwRI: 9/24/79 . The individual has been credited with at 'least 48 in this examination method on the date of certification. Some of the experience may have been a;ccrued simu1taneously with other. NOE methods lat least 25% was in this metnodl.
months of experience VISUAL ACUITY AND COLOR PERCEPTION I I The individual is cacable of reaaing Jaeger Number 1 letters at 12 inches in at least one eye !using corrective lenses if sceciiied below1. and can I distinguisn and differentiate contrast between colors used in this method. Cate Corr. Rea. Verified by Date Corr. Rec. Verified by 7 /7 /88 No B. G. Huffman /./, T<.'o/' I MOST RECENT EXAMINATION GRADES I CERTIFICATION HISTORY: THIS LEVEL I WEIGHT SCORES SCORES DATE I Basic 3 97 .14 29.14 Initial Certification: 1L9L89 Scec1iic .J 91. 43 36.57 Recertification: I Metnod 3 82.86 'J!j 96 Recertification: ! Com co site 92.67 Recertification:
~
Rescons1b1e Recertification:
~ave1 iii ;,...7-cr7 Recertification:
I
- REMARKS I I
I
- - .. I F-51
. SOUTHWEST RESEAR.CH INSTITUTE NONDESTRUCTIVE EXAMINATION STATEMENT OF CERTIFICATION The Vice President. Nondestructive Evaluation Science and Technology Oivision,.certifies that Vic.tor Morton is Qualified as Level Ill in Visual Testing IVTl.. categories _V_T_-_l_*.._V_T_-_2_,__V_T_-_3_,__V_T_-_4______,___________
- in accordance with the reQuirements of SwRI Nuclear Quality Assurance Procedure 11*2.
Certification Limitations: Certifica.tion valid onlv while employed by SwRI Expiration Cate: 08/10/91 Signed:_-"*/L~~~~~=--Z....;.....;,._.,....~-- Vi~e President. Nondestructive Evaluatio~
.jl.o".""-=-~----Date:_~_---/o_-ic_'?__
Science and Technology Division EDUCATION ANO EXPERIENCE HISTORY EDUCATION: NAME YEARS DEGREE Previous NOE Expenence tif usea for auauticat1on1: High School Colston Senior Secondary 4 Grad COMPANY FROM TO GED Additional: - - - - - - - - - - - - - - - - - - - - - - None Major Field of Study _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ Date employed by SwRI: 09/24/79 . The individual has been credited with at least 48 momns of experience in this examination method on the date of certification. Some of the experience may have been accrued simuttaneoully with other NOE methods lat least 25% was in this method). VISUAL ACUITY ANO COLOR PERCEPTION The individual is caoable of reading Jaeger Number 1 letters at 12 inches in at least one eye lusing correc?JVe lenses 1f soecnled belowi, ana can distingulSh and differentiate contrast between colors used in this metnod. Date Corr. ReQ. Verified by Cate Corr. Req. Verified by 7...1:1...l.1J.8..__;I....,o_ _ Martha Pogue -,.n.Gt,.j:) MOST RECENT EXAMINATION GRACES CERTIFICATION HISTORY: THIS LEVEL WEIGHT SCORES SCORES DATE Basic .3 97.14 29.14 Initial Certification: 08/J0/88 Specific .4 93.33 37.33 Recernfication: Method .3 86.76 26.03 Recernficatian: Composite 92.50 Recertification:
~
. Resconsible Recernfication:
Level Ill Recertification: REMARKS SwRI Form QA-43*3 F-52
- SOUI'HwEST RESF.AR.CH INSTITOTE CERTIFICATION OF PERSONNEL QUALIFICATION FOR NUCLEAR. INSPECTION AND TESTING Victor Morton i s cert i, fi e d Level III f or t h e per f ormance o £ inspection and testing in accordance with SwRI Nuclear Project Operating Pro-cedure X-FE-107 and ANSI N45.2.6 in -:.VT~-~2:.:...~VT-=--~3J.-VT;..;;.,.-~4~---------------------
Certification Limitations: Certification valid onlv while emnloved bv SwRI. Physical Requirements: verified by: .~w Date: Correction Req'd: Jaeger iFl at 12" Bonnie Caudl~ 8/13/87 No
- Jaeger #1 at 12" Betty Aldridge~ 7/7 /88 No Certified by:
Director for Levels I, II or Date Vice President for Level III Ex1:Jires:~_1_1_;2_3_/_9_o______________________~ Remarks:
- SwRI Fori:;i QA 51-1 F-53
APPENDIXG MA1ERIAL AND EQUIPMENT CERTIFICATIONS I*
- APPENDIXG MATERIAL_AND EQUIPMENT CERTIFICATIONS Table of Contents MATERIAL Date Page Pencils, Berol Prismacolor, White #938, Log #2780 22 Mar 89 G-1 Pencils, Berol Prismacolor, Black #935, Log #2594 22 Mar 89 G-2 Glycerine, Lot #TA 870731, Log #2534 05 Oct 88 G-3 Kodak, Neutral Grey-Cards, Log #1766 02 May 83 G-4 Magnaflux, Fluorescent MT, 14 AM Prepared Batch, Batch #88022,. 05 Jan 89 G-5 Log #2744 .
Magnaflux, No. 8A Red Powder, Batch #85F006, Log #2053A 03 Jul 85 G-6 Magnaflux, No. BA Red Powder, Batch #87E035, Log #2439A 15 Jun 87 G-7 Magnaflux, No. 1 Gray Powder, Batch #85K011, Log #2215A 08 Jan 86 G-8 Magnaflux, No. 1 Gray Powder, Batch #87F008, Log #2439B 08 Jun 87 G-9 Magnaflux, Spotcheck Developer, Type SKD-NF, Batch #89B06K* 27 Feb 89 G-10 M;agnaflux, Spotcheck Developer, Type SKD-NF/ZP-9B, Batch #88J047* 26 Sep 88 G-11 Magnaflux, Spotcheck Developer, Type SKD*NF/ZP-9B, Batch #88M035, 21 Dec 88 G-12 Log #2824B Magnaflux, Spotcheck Developer, Type SKD-NF/ZP-9B, Batch #88K018* 14 Oct 88 G-13 Magnaflux, Spotcheck Penetrant, Type SKL-HF/S, Batch #88G016, 11 Jul 88 G-14 Log #2591B . . Magnaflux, Spotcheck Cleaner/Remover, Type SKC-NF, Batch #89B02S, 13 Feb 88 G-15 Log #2824A Magnaflux, Spotcheck Cleaner/Remover, Type SKC-NF/ZC-7B, 26 Sep 88 G-16 Batch #88J03K* Met-L-Chek, VP-30 Penetrant, Batch #2209, Log #2845A, B, C 14 Nov 88 G-17 Met-L-Chek, E-59 Emulsifier, Batch #2193, Log #2845A, B, C 14 Nov 88 G-17 Met-L-Chek, D-70 Developer, Batch #2257, Log #2845A, B, C 14 Nov 88 G-17 EQUIPMENT Brand* Serial No. Date Page Tektronix Oscilloscope B010385 18 Apr 89 G-19 Pyrometer, Arnprobe, Fastemp 137 17 Jan 89 G-21 Pyrometer, Arnprobe, Fastemp 139 17 Jan 89 G-23 Pyrometer, Arnprobe, Fastemp 141 17 Jan 89 G-25 Pyrometer, Arnprobe, Fastemp 151 17 Jan 89 G-27 Pyrometer, Arnprobe, Fastemp 165 17 Jan 89 G-29 Pyrometer, Arnprobe, Fastemp 174 23 Mar 89 G-31 Pyrometer, Arnprobe, Fastemp 177 23 Mar 89 G-33
*Furnished by PSE&G
- G-i
APPENDIX G. _MATERIAL AND EQUIPMENT CERTIFICATIONS Table of Contents (Cont'd) EQUIPMENT (CONT'D) Brand Serial No. Date Page UVP, Black-Ray, J-221 Longwave Ultraviolet Intensity Meter 26056 20 Jan 89 G-35 UVP, Black-Ray, J-221 Longwave Ultraviolet Intensity Meter 26058 20 Jan 89 G-37 Electromagnetic Particle Yoke - Whiteline WL-1-2 01 Feb 89 G-39 Electromagnetic Particle Yoke - Whiteline WL-1-6 01 Feb 89 G-40 Parker Contour Probe '801 17 Mar 89 G-41 Sonic FTS MK I 01106E 05 Jan 89 G-43 Sonic FTS MK I OlllOE 23 Feb 89 G-45 Sonic FTS MK I 01114E 31 Mar 89 G-47 Sonic FTS MK I 01120E 15 Nov 88 G-49 Sonic FTS MK I 01122E 30 Jan 89 G-51 Sonic FTS MK I 04330E 05 Apr 89 G-53 Sonic FTS MK I Sonic FTS MK I Sonic FTS MK I Sonic FTS MK I Sonic FTS MK I Sonic FTS MK I 04332E . 04334E 06582E 760701 760712 760802 09 Feb 89
- 04 Apr 89 16 Nov 88 07 Apr 89 06 Apr 89 12 Jan 89 G-55 G-57 G-59 G-61 G-63 G-65 Sonic FTS MK I 774210 03 Feb 89 G-67 Sonic FTS MK I 774226 15 Mar 89 G-69 TRANSDUCERS Brand Serial No. Date Page Aerotech 013718 12 Apr 89 G-71 Aero tech 11278 06 Apr 89 G-73 Aero tech 11279 06 Apr 89 G-75 Aero tech A11510 30 Jan 89 G-77 Aero tech B14232 14 Oct 88 G-79 Aero tech B24653 30 Sep 88 G-81 Aero tech E09487 30 Jan 89 G-83 Aero tech E18324 30 Jan 89 G-85 Aero tech F30806 11 Jan 89 G-87 Aero tech 021651 30 Jan 89 G-89 G-ii
- APPENDIX G MATERIAL AND EQUIPMENT CERTIFICATIONS Table of Contents (Cont'd)
TRANSDUCERS (CONT'D) Brand Serial No~
- Date *Page Aero tech .H07930 02 Mar 89
- G-91 Aero tech H24817 17 Mar 89 G-93 Aero tech H24831 17 Mar 89 G-95 Aero tech H24832 17 Mar 89 G-97 Aero tech H24833 17 Mar 89 G-99 Aero tech H31806 02 Mar 89 G-101 Aero tech 116834 17 Mar 89 G-103 Aero tech M16258 02 Mar89 G-105 SwRI 515 12 Apr 89 G-107 SwRI 1125 20 Feb 89 G-109 SwRI 1264 11 Apr 89 G-111 SwRI 1720 12 Apr 89 G-113 SwRI .1774 13 Oct 88 G-115 I
SwRI 1796 15 Dec 88
- G-117 SwRI 1803 16 Feb 89 G-119.
SwRI 1807 21 Oct 88 G-121 SwRI 1845 16 Feb 89 G-123 SwRI 1848 12 Apr 89 G-125 SwRI 2547 11 Apr 89 G-127 SwRI 2676 12 Apr 89 G-129 SwRI 2757 10 Apr 89 G-131 SwRI 2924 11 Apr 89 G-133 SwRI 3223 09 Nov 88 G-135
*swru 3224 13 Jan 89 G-137
- G-iii
- SOUTHWEST RESEARCH INSTITUTE
~OST OFFICE DRAWER 28510
- U20 CULESRA ROAD
- SAN ANTONIO, TEXAS. USA 7128*
- 15121 5!1**5111
- TELEX 2**0*8 March 22, 1989 Mr. J.H. Wilson Quality Assurance Systems & Engineering Southwest Research Institute 6220 Culebra Road San Antonio, TX 78238
Dear Sir:
The analysis that you requested on two marking pencils has been completed. The results are as follows: Sulfur, 7. wt. Chlorine, i. wt. (ASTM D-129 (ASTM D-808) Berol Prismacolor Black 935 0.16 & 0.15 0.00 & 0.00
- Berol Prismacolor ~ 0.00 & o.oo If you have any questions concerning these test results, please contact me.
Sincerely, 0.00 & o.oo
#?/%~
Ralph W. Bowen, Principal Scientist Petroleum Products Research Department Automotive Products & Emissions Research
.rla Swi!I lf l(po~
P. o*._._._""':::"=.._._...., p * .a.__.o~o.s.. P..:'f..;G.;....__ LOG g7?0 SAN A N T 0 N I 0, TE X AS 0Al.l.AS / FT WORTH TEXAS
- MOUSTCN. TEXAS
- DETROIT. MICHIGAN
- WASHINGlON. CC
- G-1
SOUTHWEST RESEARCH INSTITUTE P'OST OFFICE ORAWER 28510
- e:Z20 CULESAA AOAO oa SAN ANTONIO, TEXAS. USA 782!1'
- 15121 514*5111 *TELEX 2441!48
'March 22, 1989
)
Mr. J.H. Wilson Quality Assurance Systems & Engineering Southwest Research Institute 6220 Culebra Road San Antonio, TX 78238
Dear Sir:
The analysis that you requested on two marking pencils has been comp_leted. The results are as follows: Sulfur, i.. wt. . Chlorine, i. wt. Code (ASTM D-129 (ASTM D-808) Berol Prismacolor.~k~ 0.16 & 0.15 0.00 & 0.00 Berol Prismacolor White 938 o:oo & o.oo o.oo & 0.00 If you have any questions concerning these test results, please contact me. Sincerely, 4~~- Ralph W. Bowen, Principal Scientist Petroleum Produces Research Department Automotive Produces & Emissions Research rla SwBI P.O. 7~7'{9 P. a. 0 o 3 '{ /(., LOG .J 5'1r./ SAN ANTONI~ TEXAS OALLAS I FT WORTH. TEXAS * ..iOUSTON. TEXAS
- DETl=IOIT MICHIGAN
- WASHINGTON. OC G-2
- SOUTHWEST RESEARCH INSTITUTE POST OFFICE DR~WER 28510. ez20 CULEBAA AO.AO. SAN ANTONIO, TEXAS, USA 792U. 1!12) H**51'11. TELEX 2'*8*8 October S, 1988 Mr. J.H. Wilson Quality Assurance Systems &
Engineering Southwest Research Institute 6220 Culebra Road San Antonio, TX 7823.8
Dear Sir:
The chemical analysis that you requested on one sample of Glycerine has been comp_leted. The results are as follows:. Log 2534 Loe ffe TA870731 Code Run i.il Run iF2 Sulfur, 1. wt. (ASTM D-129) 0.02. 0.02
- Total Halogens, 1. wt. (ASTM D-808)
If you have any questions concerning these test results, please contact me. 0.07 0.07 Sincerely,
~~~~~
Ralph W. Bowen, Principal Scientist Petroleum Products Research Dept. Automotive Products & Emissions Res. ygc SAN ANTONI~ TEXAS CAI.LAS / FT WORTH. TEXAS
- HOUSTON. TEXAS
- OETROIT. MICHIGAN
- WASHINGTON. CC
- G-3
SOUTHWEST RESEARCH C E RT I F I C A T E 0 F C 0 MP L I A N C E INSTITUT! SwRI Purchase Order No *. _____o_9_7o_-4_ _ __ Date ___4_-_~c_*-_u_*3_ _ _ _ _ _ _ __ Soutnwest Photo Supplies certifies the following with (Supplier's Name) respect to the above purchase order: (1) That the articles delivered under the above SwRI Purchase Order Item comply fully with the requir~mez:ts specified therein. (2) That the above supplier agrees to maintain and preserve records of
/
evidence of compliance with S~RI requirements for three (3) years from the date of final payment. These records shall include any documentation required to substantiate statements made on this form and shall be made available for review upon request of SwRI or its designated representative. Signed: lier's Representative
Title:
Date: 'c;I ~ < I * - f I
- 3~:\I SwRI Form QA-36-0 p, o. ~ 9 76 r P.R. 13/.J 't Y L:lG 17 6 fi G-4
- MAGNAFWX Date: 1/5/89 TO:
Purchase Order No.
*We hereby certify that the Magnetic Particle inspection material t y p e - - - - -
14AM Prepared Ea.th , Batch No. 881*!0:22
-----------~
meets the requirements of the following.specifications: A. ASME Boiler and Pressure Vessel Code, Section V, 1986 Edition, Nondestructive Examination, Paragraphs T-723, T-726(b) and Article 25 as applicable. B. ASTM E 709-80, Paragraphs 6.1, 6.2, 6.4, 6.4.2, 6.4.4.2 and 6.4.5.1. C. MIL-STD-1949, 1 August, 1985. Paragraphs 4.10.1, 4.10.1.2 and 4.10.2
- o. MIL-STD-271F(SH), 27 June i986, Paragraphs 4.3.2.1, 4.3.2.3 and 4.3.2.4 *.
. E. MIL-STD-2132A(SH), 15 March 1985, Paragraphs 6.2.1.3, 6.2.2.3, 6.2.2.4, 6.2.2.S, 6.2.2.6, and.6.2.2.7. .
F. The flash point of the .material is over 200°F when tested by the Pensky-Marten's Closed Cup Method (ASTM D-93). G. the vehicle meets the r.equirements o( DOD-F-87935, 12 January 1984 and Amendment 3, 27 February 1987. H. The vehicle meets the requirements *oc AMS 2641, 1 January 1988. The vehicle is classified as Type I according to Paragraph 1.3. We further certi!y. that this material does not contain mercury as a basic element and no mercury bearing equipment was used in its manufacture. Batch numbers appear on labels of bulk containers and on the bottom of aerosol cans.
-*.._._....--.. MAGNAFLUX CORPORATION' I a,.::11 Cft./ ;t-;t' '
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!*** -2744 ___..\*, C. A. Zeleznik - ~;tanager, Quality Assurance
~1. Plamoottil - Quality Control Chemist Form ~o. 1565C R-7 /88
- G-5
Date: .Jt:lv ~ .1085 Purchase Order No. - - - - - - - - - We hereby certify that the :-.iagnetic Particle Inspection Material type No. 8A Red Powde!" , Batch No. 85F006 meets the requirements of the following specifications: ~--------------- A. AS~;IE Eoile:- and P:-ess*Jre Vesi;el Code, Section V, 1980 Edition, Nondestructive Examination, with Summer 1980 through Winter 1982 Addenda, Paragraph T-753 (a) and Article 25 as applicable. *
- B. ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition,
- Nondestructive Examination, with Addenda through Winter, 1984, Paragraphs T-723, T-726(a) and Article 25.
- c. AST:VI E 709-80, Paragraphs 6.1, 6.2, and 6.3.
- o. NAVSEA 250-1500-1, Rev. 10" June 1979 and Rev. 11, May 1983, Para.,<7Taph 12.4.1.6.
E. MIL-[-6868E, 27 February 1975, Paragraphs S.l, 5.2 and 5.3. F. MIL-STD-271E(SHIPS), AC!-i-1, 24 October 1980, Paragraphs 4.2.6, 4.3.2.3, and 4.3.3.1.
- G. MIL-STD-271E(SHIPS), NTR-lE, 16 June 1978, Paragraph 4.3.2.3.
H*. :\UL-STD-2132(SH), 16 January, 1981, Paragraph 4.2.1.3 and Appendix A, Paragragh 50.4.
- We further certify that this material does not contain mercury as a basic element and no mercury bearing equipment was used in its manufacture.
Batch numbers appear on labels of bulk containers. MAGNA.FLUX CORPORATION A. S. Britton - i\Ianager, Quality Control
- w. G. Blankenship - Director of Quality Assurance Form No. l565A R-~/85 G-6
Date: ____0 _u_._*-_ _..r """'9""
-_,_~___
-;_~__
- __~
TO: Purchase Order No.------------------- We hereby certicy that the ~Iagnetic Particle Inspection :\Iaterial type No. SA Red Powder 37E035
- - - - - - - - - - - - - - - - - - - - - - - - Batch N o . - - - - - - - - - - - - - -
meets the requirements of the following specifications.: A. ASME Boilt!l" and Pressure Vessel Code, Section V, 198\i Edition, Nondestructive E...;amination, Paragraphs T-723, T-726\b) and Article 25 as applicable. B. ASTM E 709-80, Paragraphs 6.1, 6.2, and 6.3. C. NAVSEA 250*1500-1, *Rev. 10 June 1979 and Rev. 11, May 1983, Paragraph 12.4.l.6*
- D. Mll.-STD-1949, l Allg'Jst 1985 Paragraph 4.10.l.and 4.10.1.1.
E. :\UL-STD-27l.E(SHIPSJ, AC~-1, 24 October 1980, Paragraphs 4.2.6, 4.3.2.3, and 4.3.3.l. a..-:d ACN-:?, l :'.lay 1984. F. :\-Ill.-STD-271E(SHIPS), N'TR-lE, 16 June 1978, Paragraph 4.3.:?.3.
*G. l.\Ill.-STD-2132A(SH), 10 September 1984, Paragraph 6.2.1.3.
We further certify that this matedal does not contain mer-::ury as a basic element and :-:o mercury !Jearing equipme.'lt was used ln its manufacture. Batch numbers appear on labels of bulk containers. MACHA.FLUX CORPO!t.\TION A. S. Britton - .\1anager, l.(uality A:>::iurance M. Plamoottil - Quality Control Che*mist Form No. 1565A R-1/87 swaI \ P. o.* ~ 3° (4 SC f P. :e. 3 7Y.3~- II i L:~ 24 3 9 A
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- G-7
Date* .Tam1a,..v 8 , 086 TO: Purchase Order No. _ _...9-......'-'2.._~
. . . .5.......~.,* ....* ___
We hereby certify that the Magnetic Particle Inspection Material type No. 1 Gray Powder meets the requirements of the following specifications: Batch No. __ __________ 85KO11 A. ASME Boiler and Pressure Vessel Code, Section V, 1983 Edition, Nondestructive Examination, with Addenda through Winter, 1985, Paragraphs T-723, T-725(a) and Article 25. B. ASTM E 709-80, Paragraphs 6.1, 6.2, and 6.3. C. NAVSEA 250-1500-l, Rev. 10 June 1979 and Rev.11, May 1983, Paragraph 12.4.1.5. D. MI.L-STD-1949, 1 August 1985 Paragraph 4.10.1 and 4.10.1.1. I
- E. MIL-STD-271E(SHIPS), ACN-l, 24 October 1980, Paragraphs 4~2.6, 4.3.2.3, and 4.3.3.1. and ACN-2, 1 May 1984.
F. MIL-STD-271E(SHIPS), NTR-lE, 16 June 1978, Paragraph 4.3.2.3. G. MIL-STD-2132(SH), 16 January, 1981, Paragraph 4.2.1.3 and Appendix A, Paragragh 50.4. We further certify that this material does not contain mercury as a basic element and no mercury bearing equipment was used in its manufacture. Batch numbers appear on labels ot bulk containers. 57RI
?. o.9 2 2 5 4 P, R.31"rq !f ~ A. s. Britton r.::; 2 21 5 ,4 Manager, Quality Control and Quality Assurance T. E. Regan - Certification Clerk Form No. 1565A R-12/85 G-8
- bate: _ _ ____
"'"*ne z, ~JSi TO:
Purchase Order N o . - - - - - - - - - - - We hereby certify that the :\lagnetic Particle Inspection :vtaterial type No. 1 Gray Powde!' B:itch No. meets. the requirements of the following specifications:
. 87F"J08 A. AS ME Boiler and Pressure Vessel Code, Section V, 1986 Edition, Nondestr1*~tive Examination, Paragraphs T-72:?, ~-*726(b) and Article 25 as applicable.
- B. ASTM E 709-80, Paragraphs 6.1, 6.2, and 6.3.
- c. NAVSEA 250-1500-1, Rev. 10 June 1979 and Rev. ll, :\1ay 1983, Paragraph 12.4.1.6.
- D. MIL-STD-~949, 1 August 1985 Paragraph 4.10.l and 4.10.l.l.
E. ~IIL-STD-271E(SmPS), A.CN-1, 24 October 1980, Paragraphs 4.2.6, 4.3.2.3, and 4~3.3.l. and ACN-2, l :\lay 1984. F. MIL-STD-27l:C:(SHIPS), ~R-lE, 16 June 1979, P:aragraph 4.3.2.3.
. G. MIL-ST!Hl32A(SH), 10 September 1984, Paragra?h 6.2.1.3.
We further certify that this mate!."ial does not contain mercury as a basic element and no mercury bearing eqti.ipment was used in its manufacture. Batch numbers appear on labels of bulk containers.
?.1AGNAFL UX COP.PORATIO.N A. S. Britton - :.Ianager, Quality Assurance M. Plamoottil - Q;;:.r.::ty Cont:-::i~ Chemist Form No. 1565A R-1/87 .., I _.
wl'Te>
- 1. ?. ~. 2 g~ ~ c
. 2* a. 37!3Sr I L:G 24 3 98
- G-9
Purchase Order N~.
*Srotcheck Develcp,er SKD-NF' !l'JBOC:i<
~~=*--------
\\'e hereby certiCy that when tes~ed 'lt !!I~ tirtte *JC :n~rn1:*nc~~i"e, tlie 9.'.Jov~ ~:~~!":*;~: (~ l i\S~.rn lloi i~r and Prc5surc '.'c~scl C~~c. 133:> ;:~:? l~:i, S2~ticn 1.', ~1~n~estr*.:~~i*1~ E:carninotion, incluc.!(nb nil Ac.ltlend.1 ti.1i"ou;h ',\"!n:cr :J~:J ;\.dd~:i"ii..::n, : 1 ~;r::;~~~!"l -~-*~=~ nn<l ,\rticlc 2-l ns appli:nbtc. (b) AS:\tE Railer :ind ?r~ssura Vt?ssel Codo, I:J:.s :Z~l1 1.i1J~. Sec~i.:r. 1
/, ~!~nd~st:-':.!c~i\*e Exa.rnination, P 1lr11;rr.g~"'! T-Gl:i and :\rt ic!e : i ;.:.s ::~~ ~ic~:>!e.
(.:l AST:.! E-lu5-SO, Par<igrn~h 7'. :. ( d) NAVSE~ 350-tlOO-l ~ ~ev. re .J..:::~ '" !" I
. . . . .J. - * .
- 12. 5. l. 1
- 1.
Ce) ~11L-STD-2ilC,S!l), :7 Jur~~ ::3~, 1'a:-~:;:-ai'!1!; ~ *.~and :'.~.L. (C) i\t!L*s*rn-:nJ~.:\(.'5li), 15 :~i:.ir~h 1~1 .i~~. f*!:a~!'::;!h~ 7.!.~, 7.1.'.!, :1::ti -. ...',
' ~:n d
~
Appendix C, P~rugr*J;>h JO. The (ollowi~g l':!~t* results 1,*1crC obl~;acd: Su!Cur: 0.0723 rcsiUuu. Cleaner residue (sec Nu~c Jl NA
- 2. We further certify lhal this m:iteriat ~Jes r1*Jt cc11ta::1 ~c.-~'Jry ~s ~ !Jas!(: ~!ar::.~r.:, !!nd no 1nercu:-y bearing equl~r.tcnt Wo!S :J.>i!:!d ln its 1:?c.:1:..:fa.c:*.=ri:.
~: l. Our ~e.tch number lp(>cars "" th~ 1J-:!t~,::n ~r :.~! .1-:!:c.;:i~ ~J.;is .i:~(! ~~ ~:~~ : ..::.i~l or all buik c:ontnin~rs.
- 2. Most spccirications r~quir*2 lt.?3t :-~s::lts st*r:t-.J.! ir~ ~ 1.:n*~.~~1l bu: .;.:J**~~ ;*J~;::i;*~
parts ;>er million {r'pm). To con-.:c:-t "n2r~~nl" ~i;:l-~S :c **~*~':'ts ~*':!r ~:i~lic:1" m4've the decl~nal four p lac~s ~o the -: :;:it.
- 1. NAVSC:A 250-1500-l, ~iii..... ST!J-~-:"l, ~.t:L-STD-:!::~, nr:**: ."..~~.:E S*~cti~n 1....1,: r:?qui~~
that rnatet""inls ?>c s::Ojccl ~o u t>roceduie 1.0 evupoi:..:.le off vrJi.at-il~ 3-':*.-ents bl!Core 4nAlysis ror sul( Jr' :ind ha\Og"Cn. 1
,\ccC:-*!in; ~a t?i~~e Sj?~i:ic~ticn~,
only those rcsi*.!ucs hi~her t!1~;i G.~!,5 g.'~00 *r?.i. 3t1atl be ~llJ.l;.*7.ed for sulfur !l:-:*J t1~logcn. Lower csid!ics s~~ll ~~ report2~.
~. T?1e above ~':!r::r :!!lt:.;n ~i*.-~s ~=:~ r~sults ob~ ..i::!cd .lt t!~:! ~i:n:? -:f !'!".<:t::..if~t~t* .. :-~.
- \~c ::.nd l!~i.! ;::a:; ~~*.!; ~::.! .. :-i.:.:*~*::*.::3 cf *1ny ;:~*:t::*i:~l.
G-10
- MAGNAFLOX Date:
9/26/88 P~rchase Order No.
SUBJECT:
Spotcheck Developer a_ __ Batch No
- _ _8J_o_4_7_
Type: _s_K_D_-_N_F_l_Z_P_-_9a We hereby cert lfy that when tested at the time of mahufacture, the above material:
- 1. Meets the requirements of and has been tested for sulfur and halogens according.to:
(a) ASME Boiler and Pressure Vessel Code, 1983 Edition, Section V, Nondestructive Examination, including all Addenda through Winter 1983 Addendum, Paragraph T*6Z5 and Article .Z4 as applicable. (bl ASME Boiler and Pressure Vessel Code, l986 Edition, Section V, Nondestructive examination, Paragraph T-625 and Article Z4 as applicabl~. (cl ASm E-165-80, Paragraph 7.1. (d) NAVSEA 250-1500*1 (Rev. 10 June 1979 and Rev. 11 May l983) P3ragraphs 12.5.1.1 and lZ.5.l.l.l. (e) MIL*STD*Z71F(SH), Z7 June 1986, Paragraphs 5.3 and 5.3.1. (E) ~IL*STO-Zl32A(SH), 15 March 1985, Paragraphs 7.1.i, 7.1.Z, and 7.1.3 and Appendix C, Paragraph-JO . The following test results were obtained: Sulfur: 0. 0318 wt. \ of residue. Halogen: 0. 0190 wt. \ of residue Cleaner residue (see Note' 3) NA g/lOOg. NA J,/lOU ml. Z. We further certify that this material does not contain mercury as a basic element, and no mercury bearing equipment was used in its manufacture. HAGHAFLUX CORPORATION
~-~~
clteri A. *ele:n1k
- Manager,Qua*l.1 ty Assurance M. Plamoottil
- Quality Control Chemist
- -!OTES: 1. Qur batch number appears on the bottom of all aerosol cans and on the label of all bulk contalners.
Z. ~ost specifications require test results stated ln percent but some require parts per million (ppm). To convert "percent" figures to "parts pei million" move the decimal four places.to the right. *
- 3. NAVSEA Z50-1500*1, ~IL*STD*Z71, MIL*STD*Zl32, and ASME Section V ali require that.materials be subject to a procedure to evaporate off volatile solvents bef?re analysis for sulfur and halo!en. According to these specifications, only those .residues higher than 0.005 g/100 g shall be analy:ed for sulfur and halogen. Lower residues shall be reported.
- t. The ab~ve certificati~n gives the results ~btained at the .time of manufacture.
Age and ~se may alter the properties of any material. Form No. 1569 R*S/88
- G-11
December 21, 1988 Dae is: Purchase Order No.
SUBJECT:
Spot check Developer TY11e: :::10-NF/ZP-9B Batch Ho.* 8 8MO 35
*r.
We hereby certify that when tested ac the ti*e o! 2anufaccure, the above material:
- l. ~eecs the requirements of and has been tested cor sulfur and halogens according co:
(a) ASME Boiler and P?"essure Vessel Coda. 1983 Edition, Seccion: V, Nondestruccive Examination, including all Addenda through Winter 1983 Addendum, Paragraph T*6ZS and Article Z4 as applicable. (bl ASME B~iler and Pressure Vessel Code. 1986 Edition, Section V, Nondestructive Examination, Paragraph T*6ZS and Article !4 as applicable. (cl ASTM E*l65*80, Paragraph 7.1. (d) SAVSEA :SO*lSOO*l (Rev. 10 June 1979 and ReY. 11 )4ay l983) Paragnphs lZ.S.1.l and 1Z.S.l.l.l *
. (el MIL*STD*Z71F(SH), ?7 June 1986, Paragraphs S.3 and S.3.l.
(fl MlL*STD*Zl3ZA(SH), 15 March 1985, Para&raphs 7.1.l, 7.1.Z, and 7.1.3 and Appendix C, !Paragraph 30. The followin1. test results were obtaine~: Sulfur: 0 .0628 wt. \ of residue. !lalogen: 0 .0035 we. \ of residue Cleaner residue (see :.late 3) ---~-~A _____ v1ao1. NA g/100 ml. Z. We further certify that this maclllrial does- DOC' =incai.n mercury as a basic element, and
~o ~er;ury bearing equipment was used in its manufacture.
MAG.'fAELUX CORPORATION C:hen A**eleiiil * :~anager ,Qual 1 cy Assurance M. l'lamooccil *_Quality Control Chemist !Qill: l. Our batch number appears on the bottom oE all aerosol cans and on the label of all bulk cantaine~s.
- z. ~est specific:.atiollS r=quire test results stated in percent but some require parts per million (ppm). To convert "percent" figures ta "parts per million"
~eve the decimal four places to the right.
- 3. NAVSEA ZSO*lSOO*t, MIL*STD*Z71 0 MIL*STD*Zl3Z, and ASME Section Vall require that materials be subjec~ co a procedure to evaporate off volatile solvents before analysis for sulfur and halogen. According to these specifications, only those resi4ues hi&her than 0.005 i/100 ml snall be analy~ed for sulfur and halazen. Lo~er residues shall be reported.
'* The above certif-icacion gives the results obtained at the time of manufacture.
Age aad use may alter tha properties of any material.
\.
~~' fi ::~-ll p, 1
- I.CG Q
'1'31? I 28248
--~ .....,
'*~ '** lS6' l-10/BI G-12
- MAGNAFLUX.
Date: 10/14/88 Purchase Order No. Spotcheck Developer SKD-HF/ZF-98 83KO Batch No. _ _ _ _18 S U B J E C T : - - - - - - - - - - - - - Type:
~e hereby certify that when tested ~t the time of manufacture, the above ~aterial:
- l. '4eets the r_equire111ents of and has be!!n tested for sulf*Jr and halogens according to:
(al ASMS Boiler and Pressure Vessel Code, 1983 Edition, S!!ction V, ~ondestructive Examination, including all Addenda through !linter 1983 AddendWI, Paragraph T-6Z5 and Article Z4 as applicable. (bl ASM.E Boiler and Pre~sure v*essel Code, 1986 Edition, Section V, ~ondestructive Examination, Paragraph T-6ZS ind Article ?~ as applicable. (cl ASTM E-165-80, Paragraph 7.1. (dl NAVS.EA Z50-1500-l (Rev. 10 June 1979 and Rev. 11 May 1983) Paragraphs lZ.S.l.l and lZ.S.l.1.1. (e)* ~UL*STD-Z7lf(SH), Z7 June 1986, Paragraphs 's.3 .and S.3.l.
'CJ '.-1:::.-STil-ZllZA(Sll), lS March ins, Paragra;ilu 7.l.l, 7.Li, and 7.l.3 and Appendix C, Paragraph 30.
The following test resu.J.ts were obtained: Sulfur: 0 .1117 wt. \ of residue. Halogen: __o_._0_3_8_4_ wt. \ of residue r.1eaner residue (see ~ate 3) NA g/lOOg. NA 3/100 ml.
- z. We further certify that this material do~s not contain mercury as a basic element, and no ~ercury bearing equipment was used in its manufacture.
MAGNAFLUX CORPORATION Chert A. !eletn1£ - ~anager,Quality Assurance M. Planoottil - Quality Control Chemist
~OTES: 1. Our batch number appears on the bottom of all aerosol cans and on the label of all bulk containers.
Z. ~ost specifications requir~ test r!!sult* st~ted in percent but some require parts per million (ppm). To convert "percent" figures to "parts per million" rneve the decimal four pl:ices to che right. *
- 3. NAVSEA ZS0-1500*1, '41L-STD-Zil, MIL-STD*Zl3Z. *nd ASME Section Vall reo;:iuire chat rnateri3ls be subject to a procedure co ~v*porate off vol~tile solvents hef?re analysis for sulfur and halogen. According co chese speci!icaticns,
?nly those residues higher than 0.005 g/100 g shall be analyied for sulfur 3nd halogen. Lower residues shall be r"eported.
~. The above certification gives the resulcs cbtained at the time of manuf3cture.
Age and use may alter the properties of any material. For111 No. 1569 R*~/SS
- G-13
Julv 11. 1ass stra..raCT: Speeched:. Penecranc SKL-!iF/S 88G016
'?i"pe:* - - - - - - - - - Batc.!1 lfa. _ _ _ _ __
W* hereby cer-:iEy that vhen tested at the time af :ztllnuiac:ure, c~e above 3at:rial:
- l. ~eets the requir~=::.s of and has been tested f=r sulfur and halagen.s acc=rding c=:
Car ..\Silt! 3ailer and. ?::ssure Vessel Cade, 1983 E:icion, Sec:ion V, ~ondescruc::ive
.E:umiiia:ion., i.=lwiing all Ad~encia c!lraugll ;(inter t983 Addendum, Paragraph T-o;:s 111.d Ar:ic:le ?~ as applicable. .
re) ASH! 3oiler* md !'res.sure Vessel Cade, t986 Edi:ian. Sec:ian V. ~ondestruc:ive E%a.mina.tio11. l'.ragraph T-6ZS and Ar:i:.le Z4 as appli::acle. (~) A.:.~ 5-165-aa, Paragraph 7.l. (~) :4A'."3ll ZSO-U>IG-t (iteY. 10 Ju::e 1979 md R.ev. l l !lay 198:;) l'arafi:r:ipils 12 .* S.l.l and
'u.s.1.1.1.
C:l' )(!l.-m-m.::csal, z1 Jwie 1986, l':lr:ifi:raphs s.J a.--,.d s.J.1. (f) HIL-S!D-?UZ.\(SHl, lS )iar::h 1985, l'ar:r.graphs 7.1.1,*1.1.z, and 7.l * .3 and Appe:idiz C, Paragraph 30. Cil R!lT Sc.mdard F3-6T, :-lay 1974 and Oc::aber 1975 including Amend.menu l Z (2_-9*78), Ar-:icle 6, ?aragrapiJ. T-3a. (.$-~-76) and (h) General Ell!c::ric: P.S. 9000, R.ev. Z (Z*Zl*SO) Paragraphs l *.J md Z* .f". ":'lle folloving ce.sc resul.~ vere obtained: Sul.fur:" O.OZlS ' ~ t ol residu~. Halagen: O.Oo 75
~. 1 of residue Cleaner residue C.see ~a:a 3) NA g/l001. NA .*
g/100 :?LI..
~--~la.moac:il *Quality Can:rol C~e~is: .
C. A. Zeleznik-Manager of Quality Assuranc ~: of-all ~at:~ c:=ntainers.
- l. Our other IN!iriier aooear3 on che bat:om af all spray :on:ainer.s and an che label
- z. :-lase S?eca=lca:ians requira ~es: resul:3 s:o:=d in ~er::en.: buc some require par:' per :illian (P~Ml- io convert "?erc:enc" fizures ca "?ar:s per *illian"
*ave che deci:al four plac~.s co che rign:.
- l. ]~VSi>. ?SO*lSOO*l, :-!Il-STD*Z71, ~IL*STD-Zl32, R.DT F;*6T and AS1't! Sdc:ion V all require chat materials ~e subjec: co a pro~durs eo eYaparace of! Yala:il9 salvencs before analysis for sulfur and halogen.- Ac:arding co :hese s~ecifica:ians, only chose residues !liiher cha~ a.oos J/100 J shall be ~l~ed
!~r sul£ur and halogen. Lower residues* shall o* repor:=d.
~. i!le abov.- :ar:iii::acion ii"t.es Che results obui:ie.d u :he Ume of 'llanufac::ure.
~ie and use oay alc:r Che ?ropertie.s '£ any oa:erial.
~orm :fo.* tS69 !* 10/!7 G-14 *
- f\l'~~-~~--~~~~~_.::_Da::...:..::tc~:-F~eb==T=ua=Ty===l3=,==1=98=9==:_~-
Purcnase Order No.
~: _s-"i:_o_t_c:i_*_e_c_k_C_l_e_an_e_T_l_'3._e_m_OV1!2'
___ Th'*=- Batch No. S9E02S We hereby certi ry that when tested Ill tbe time at manu!ll<:tUre. the above material:
- l. ~1aet:; the rec;11ire:11cnts Q! and has t>ee~ tested Cor ~~l!ur and haloi;ens ac<:ordlng'to:
(a) ASME Soiler and Pressur* VcsseL Cada. 19'8~ Edition. Section V, ~ondestructive 5xarnination. including all Acl4'mda. tlu'aqtz Wint1tr 1983 Addendii.-n, i'aragra1?h*T-.;2s rnd Aniele 24 as applicaC.Le. (bl ASM!: Soiler and Pressure Ves~*~ C".:>dm, 1g&a Edition, Section Y, Nonaes;:~ctiv@ C:xami nation, Para~ra?h T-5ZS amt articl<r- ::.t as ae;> llcao le. (c) ASTM E*l6S-ao, i'*.uagrapll ~ -l.- (d) m!.-S';'l)-2TlF(SrJ), Z'l' June l~SS~ l!'zracrag~ S.3 and S.3.l. (el 1'U:..-sTD-2ll::A(Slil, l5 ~r:i.rt:A UU. l!'.ll'a~plls 1.1.t, 7.l.Z, and 7.1.l and Ap?endix C, Paragraph lfl. T~e Col:owing :est r*sults wer* obtained: Sul!~r: __...'R-.A-..___ .,.t. % of r .. :iidue _o_._oov __-___ ,11oa 1*. Cleaner residue (see Note 3) 0.0012 :11::0 ml.
- . We rurther c:ertl!y that t~is ma~er"ial does no~ contain ~ercury as a ~a$iC olement, and no :3rc:ury :ltlarini> *equi1>mei:i.c ~ u...t. ::a its nimautactur"e.
JMalAlLUX amPORATtO!f
. . ..ti' /}f:::;1;fii/;;, '""'""'
1, Our batc:h nuraber ~-"'" <m t:lle l:lottam ot &er"osol c:ans and on the label
~* oC all ~ulk containers.
Most spc:c:itr~*tion* r"f!<!:3ir"e tmst ~esglts stat*d in perc:ent l:IQt so,,,. require parts ?er millio~ ll'pm).* Ta c:aaTert "?troant" tiiures to "parts per million* move the dee ima I fo11r ;i taees to the* ri gn t.
- l. ~llL-ST.)-Z':' 1, lUL-S"m-?ll:., 111n<l AS?-tE Sect i 011 V a 11 require lha t :ua ter ia ls be subject to a pr~edlire t~ eYa~orate orr volatile solvents o~!ore analysis tor sulfur and ba.lo~esa- A.l:cordi~ to these spec:i!ic:ation;, only these residues higner than ll.OQS ~/iao Ill! sllall be analyzed !or sultur and halo(en. Lower
~esidues shall be repor~e~.
- 4. The above cttrU.tic:ali..,.. (hes tht results obtained at the time of manu!ac:ture.
Ace ind use ma, after t:l:la ?ropertles of any material.
!!*BI P, o. s2 2::".? 3
-- l J
f Form No. 1568
- R-1/U
~
P, B, it/JI?/ r.oa 2s24d: G-15
Date: 9/26/88 P"ichase Order No.
SUBJECT:
Spotc.:heck Cleoner/Remove1;.ype: SKC-NF/ZC-7I:I llttch Ho. _ _ _88J03K we hareby certify that when tested at the time a£ manufacture, the"abave material:
- l. Meets the requirements of 3nd ha~ been t1sted Eor sulfur and halogens according to:
(z) ASME ~oiler and Pr~ssur1 Vessel Code, 1983 Edition, Section V, Nonde~tructive ExJ111!11ation, incl11dinf all Addenda throu9h lfinter 1983 Addendum, Puagraph T*62S llnd Article Z4 as 3pp lcab\1. * (~) ASME Boller and Pr9s~ure V~ssel Code, 1986 edition, Section V, Nonde~tructiie 2*3ml~Ktlon, Paragraph T-625 &nd Article Z4 as applicable. (cl AST~ 8*165*80, Par39raph 7.1. (d) NAVSEA ZSO*lSOO*l (Rav. 10 .June 1979 and R.n. 11 "fay 1993) Par:igraphs lZ.S.l.l and IZ.S.l.1.1. (~) ~lL*SfO*Z71P(SH), 27 Juno 1986, Par~araphs 5,3 and 5.J,1. (l) ~lfL*STO-ZllZA(SH), 15 March 1915, Paraaraphs 7,1.1, 7.1..Z, ind 7.1.l and Appendls C~ Para1raph 30. The !ollowln9 test results wore obtalned: Sullur:
- NA wt, l of residue, flal,,1en: __N_A___ we. \ ol residue Cleaner re~ldue (see H.Jte 3) Q
- 0027. 1/1001. Q .0035 a/100 111.
- 2. ~. E~rther c~rtir1 th~t thls material does not contain m*rcurp as a b11slc *lem~nt, and no mercury bv~ring eq"lrme~t was used ln Its manufacture.
MAGHAPLUX CORPORATION
~ a.. ~
Cheri A. f1Ie1nlk * !4a11111er ,Q*Ja li ty Assurance
~. Plamoottll
- Quality Control Chemist *
- 'lOTl!S:
- 1. Our of all batch nu~ber appears o~ the hotto11 of all aerosol cans and on the label bulk containers.
- z. ~ost specl!lcatlons require test r1sult' ttnted ln percent but some r*quire p~rts per *illlon (pp11J, To convort "percent" tl1ur1s to "pa~ts per million" 111ove the declul four phcu to "" r\glit.
- 3, NAVSEA 250-1500-1, MIL*STD*Z71, MI.l.-STO-Zl3Z, and AS~tS Section V all require th4t msterl4ls he subject to a procedur1 to evaporate off vot*tlle solvents be!or~ 3n~lyst' !or sulfur ind h4logen, Accordlna to the~o sp4clflcatlons, only those retlduet hl1hcr than O.OUS 1/100 1 ~h4ll be analy:9d for s*1ltur and halo1un. Lawer resldu~s sh*ll be reported.
'* Tlie above certlElc~t!dn 1lvea the retults ~btalned at the tlme of 11onuC3cture.
Aae ind use may alter the properties of any aat*rla.1
- G-16
- ~ .............- . , ............... c. *** - .** 12131*... 1111 No~r 14, \'88 Stl"Olld S.1 a 600 II. Shepherd, 5u1u 115 Hc111 COft, TX 1?00 7
%9331 t: 11 l'leNO)' ;itl"t1f11d tlit Ptnltr11!1t 1:11tll'1111 f1mtilft9d On YCUP lll"lla,.i
- 1. Ki*t \lie req11i"8ll!lllU cf llIL*t*2513$0 *nd .,.. *PPr'OYtd B)' tlle u. 5 *
.&1,. rol"'l:e, 1ncllldfn; 111 to.x1c1t)I ~1111"11n111:1 fc,. ~u*l1f1i:.at1""8.
- 2.
- Men '11* ~ll11"H1111u ind M.aw ~*n uu.u f;,. 11.1lfu,. ind h1ta;an fn 1e:oi-o.11n *itll tile f11!lo1ffn; s111:'11'1.c.an11111:
- 1. XAYS£A ZSO*ISOO*l, Pll"l;raph lZ.&.l.1.l Re~. 11
- b. MIL*S~Zi![, ll'Ta*l!
- c. -ASMC &c171r- ~ P!"Hsu,.. Vuul Code, s.ac:1cn UI ll11elu,. ~ewer Plut ~~nts, Ai:i;."4tx rx, ,,,..11,..1111 rx l6JO, un t.ltl"'O~ti 1916 td1t1=n.s and 14dtll4&.
- d. ~ !oi!e:o l ,,.. .. _ Vtutl Code, Section Y, liondutrvct.1v.
ha:wirntl~ * .&r-t1cl'! ~. S1...,*l"t1clt 'T-ns. 1977 tl'l~uql! !fU 1d1t1on1 111d 1ddtnd1; ind Art1clt f, S11;11"i1c11 T*6Z5, 1'56 1dftfon
- l. J.rw '" fit lller'fllll')' cont11rbu1011, 111d 110 *l"CllPY lla11l"1Ali ilj11io.11t wn llllid fll tlle1,.. lllOl'lu!'ae~;,...
- T~* ut1r11l1 11&"9 be1n 111al)'itd f;r 1Ulf11r by A!'TM 0-129 or 1ts *liMd altll'~ie ASTH 0-1552 1r1d fCI" llllegall ~ .lS1)t !).!QI '"d AS'-t*lSS 1ppen;l1 3,
~Urhl VP-30 .l>enttr-airt t~E ~~i;;:~I' h1:Cll' I
~~~------~--------~--------------~---------~
2209 v m~/ S Su1f11r 0.01
,g:g:
s Ka1=94"
. C.01
~:g~
CERTIFICATION
\ aw31 a P. 0 9? J/'Z..____ 'I
*---'~..;::.;.,.;;;
p
- B.,~'-:.3..:i..Jt.o9"'-=0;..9;._-- l J'.OG ...2::..2..8~4.:1'.5~-!
- G-17
SOUTHWEST
*RECEIVING A.1,4 RESEARCH INSPECTION INSTITUTE REPORT L.OG NO. ~8 efs 44c R. I. :. NO. P. R. N0.~3730CJ P.O. NO. 973/~
PURCHASE PROJECT /..]*~23~*30/ END USE PROJECT - DUE CATE C:3. ,£/'4i. f.. 9 P. 0. ITEM DESCRIPTION , l.OG , ID. NO~ , SIN , ETC. CATE QUANTITY ITEM NO. fl Wa:h w~ v1 I~ c~r} //-) REC. sfo/!?9 / .Jja{J. B. l!)a:W ())~ ~ .(t.a~ ~&'C/513) s)olf'f J}ja.f. I Q. U)cdJ). U)~ iJ~ [i-.a~ ~rtts c.) S"po/~ I )Jd_ DESCRIPTION OF INSPECTION ( S ) PERFORMED 1 RESUl. TS* PASS FAil. PACKING. L.IST 0 SHIPP! NG REL.EASE 0 EXTERIOR INSPECTION DA.MAGE 0 INTERIOR INSPECTION DAMAGE 0 REMARK3 : INSPECTOR SIGNATURE: DATE I REQUIREMENT ( CHEOC SOX IF N. A.) DATE REQUIREMENT ( CHECK SOX IF N. A.) DATE MILL. TEST ( CHEMICAL. PftOPERTIES ) VENDOR INSPECTION REPORT Mll.l. TEST ( MECHANICAL.. PROPERTIES ) CERTIACATE OF CONFORMANCE CHEMICAL. ANALYSIS REPORT VQSl.S EHTltY MADE CERTIFICATE OF CALIBRATION RED TAG ISSUED HEAT TREATMENT CERTIFICATION OTHER DNR NO. ISSUED COMPLETED I CONDITIONAL. REL.EASE CATE CATE SIGNATURE SWRI FORM SS*5-5 G-18
- SOUTHWEST RESEARCH INSTITUTE
~OST OFFIC.E DRAWER 29SIO
- 8220 CULEBRA ROAD SAN ANTONIO, TEXAS 79284 15121684*5111 Calibration. Record lTBt n /( :r R aAI I ,t 0) c i I I I) s' c 0 Pe SOURCE .£) 1 '11 I '7 MODEL :2-:J] 5
- SIN --~-'-'_/_*)----.."'J.....
S-_5 _ _ _ _ _ _ _ _ SWRI NO. I 7 .2 .A L( PLUG-lNS.ETC.~A=-i,.IV=-'"------------------------------ STANDARDS Standard :--;o. ~IFGR ~odel Description SiN Cal. Due Cal. Rec. No. y,) I I
- ENVIRONME;>.'T: Temperature Locacion
. . .,_ _, ~;::"
~,2 "" * '7 / / 8L PROCEDC:RE
?'is- ~J Humidicy - - - - - - ' ' - - - " - - - - - - - -
.ti *~ ~ :;- .$"'.!~ /2 ~
~encially as outlined in MFGRS Service Manual - - - - - - - - - - - - - - - - - - -
- CO!liCLl'SION
~m wichin colerance. N.o adjuscmem was necessary.
CJ lcem ADJ/repaired co colerance - - - - - - - - - - - - - - - - - - - - - - - - - - Calibracion was in accord with requirements of MIL-STD-45662. MIL-Q-9858 and MIL-C-45208. Measurements are crace:ible co the National Institute of Scandards and Technology. Inspection and cest data are ori file and available for inspection. SIGNED tL_~ ().~ DATE 1 r=,,~e£1L I 'b"? RECORD :"!UMBER: _ _ -'/_._3_1__2______ NEXT CALIBRATION DUE: -"'"-l-"-J'_u_c_l_--=S'--'2J.-_
- G-19
SOUTHWEST RESEARCH INSTITUTE i-osT Oll'll'IC:E D .. AWE .. 28510 . 9220 CULEBftA AOA.0 SAN ANTONIO. rEXAS 711128* 1512J 151!!*-5111 Calibration Record ) SOURCE __,p~1~*y.___.l~z _ _ __ MODEL T-150 SIN 'S ilJ 5 7 I SWRI NO. ___./_$_____7____ PLUG-INS.ETC. _ ___,P~r~o~b~e'"""""#_/~3'-*-7..,.---------------------~ STANDARDS Standard No. MFGR Model Description SIN Cal. Due Cal. Rec. No. Taylor Q.S".~a9*~J Thermometer .;-1/- ;9 c .:u 9?
- ZN;/~
Taylor(Z7- l3 l) Thermometer
- ENVIRONMENT:
=
Temperature
. Rco,., )fl!
"'1i"r Location ~-flao.J n" Bl di. 68. SwRI I
PROCEDURE Humidity -~3'c....::::-;:..o..~..:../.;:;.OJ_ _ _ __ Essentially as outlined in MFG RS Ser\'ice Manual - - - - - - - - - - - - - - - - -
- JC SwRI ~uclear Projects Ope~acing Procedure XII-AG-105-2 CONCLUSION C Item within tolerance. No adjustment was necessary.
0 Item ADJ/repaired to tolerance - - - - - - - - - - - - - - - - - - - - - - -
~ Item within limits of above procedure, see* data sheet, Calibration was in accord with requirements of MIL*ST0-45662, MIL*Q-9858 and MIL-C-45208. Mea-surements are traceable to the National Bureau of Standards. Inspection and test data are ori file and available for inspection.
1 RECORONUMBER: ~~-o~o_r._1~_1J_H~~ NEXT CALIBRATION DUE: / 7 J;°l..Y S'" ')
- G-21
SOUTHWEST RESEARCH INSTITUTE SUBJECT Fastemo DATA SHEET Calibration of Amprgbe SIN Si ...; 5"1 I . SwRI 1~ I ')I T-1 SQ SHEET NO.__L_OF--L._SHEETS PROJECT DATE BY Calibration
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- SOUTHWEST RESEARCH INSTITUTE
~OST OFFICE D .. AWE" 211510
- 8220 CUl.EB .. A lllOAO SAN ANTONIO. TEXAS 711121!!1* 15121 884-!511 t Calibration Record SOURCE Piv 17 MODEL T-150 SWRINO. __ 1~]~1~~~~
PLUG-INS.ETC. _ ___,P~r~o~u~e_,_H_*~'~r~----------------------- STANDARDS Standard No. MFGR Model Description SIN Cal. Due Cal. Rec. No. Taylor o.l~89~r) Thermometer l,JFfS-lf.. ~-I/* J9 C ;u 9? auu:;.
- Taylor(ZZ-131"') Thermometer ENVIRONMENT: Temperature * '1J"'F
- Humidity ~J~;-~_.1_,,_ _ _ _ __
A'oo/'f lf It Location ~-ti.emu rr, Bldi. 68. SwRI I PROCEDURE C Essentially as outlined in MFG RS Servic~.Manual - - - - - - - - - - - - - - - - - [JC SwRI ?iuclear Projects Operating Procedure XII-AG-105-2 CONCLUSION D Item within tolerance. No adjustment was necessary. D Item ADJ/repaired to tolerance - - - - - - - - - - - - - - - - - - - - - - - Cl Item within limits of above procedure, see data sheet. Calibration was in accord with requirements of MIL*STD-45662, MIL-Q-9858 and -MIL*C-45208. Mea-surements are traceable to the National Bureau of Standards. Inspection and test data are on file and available for inspecti?n. t2_.,..,_'t::7 OJd.. RECORD NUMBER: _ _0..__0_()_1t_l_l_2_.__ SIGNED DATE "; 7J:= l" "1 NEXT CALIBRATION DUE: /7.:;;;zy ij
- G-23
. SOUTHWEST RESEARCH INSTITUTE SUBJECT Fastemn I .....1J \,i lok DATA SHEET Calibration of Amprgbe S/N 'f~U7 t'?
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J.':,]_J IV/// ~OST 5J SOUTHWEST RESEARCH INSTITUTE O"fllCa O .. Awe:,. 2aa10 8220 C1Jt..Ell"A lllOAO SAN ANTONIO. Tl!XAS 71!129* J5121 984S*'!.111 Calibration Record ITEM AmErobe 1 FastemE SOURCE I!b: lZ MODEL T-150 SIN *.5 JO &o 5 SWRINO. L'L. L PLUG-INS, ETC. Probe # t_ ~ t. UFG!iS TOLERANCE 1c.J1mw J*r ol' Sr.~ IN~1e;171,IJ STANDARDS Standard No. MFGR Model Descri21ion SIN Cal. Due
- Cal. Rec. No.
Ta!lor (!~~~9-FJ Thermometer f..J.,# ~-s-1r.. ..2 Jf._ 0 .:v 'lf'
.11.l".I~
Ta!lor(77-l l.,.2Thermometer W.f p,) l.:1.t. 1..-3-lf.. 0::1..2.'f..Z ENVIRONMENT: ex Temperature
- A'o-A//
-7 :!"r Location fr"'~=- ~ lHs1i, 68. SwRI SwRI Nu;lui:: li::gJr:s:u
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PROCEDURE 0 Essentially as outlined in MFG RS Service Manual Qg1~ating*!~ccedJJ~e Humidity XII-AG-lCS-2 5 i " l... CONCLUSION 0 Item within tolerance. No adjustment was necessary. 0 llem ADJ/repaired to tolerance Cl Item within limits of above 2rocedure, see data sheet. Calibration was in accord with requirements of MIL*STD-4S662, MIL-Q-98S8 and MIL*C-4S208. Mea-surements are traceable to the National Bureau of Standards. Inspection anci test data are on file and available for inspection. SIGNED o_~o~ 000& 1. 0(. DATE /ZJ2.11 a::z RECORD NUMBER: NEXT CALIBRATION DUE: J 7 .;IJL'I r~
- G-25
SOUTHWEST RESEARCH INSTITUTE SHEET*NO. SUBJECT Fastem'O DATA SHEET Calibncion of AmRr;bg r-1 ~o S!N"5IO~"J'.5 . SwRT ,f IE// PROJECT DATE BY t;z;&..v ol GJ)~ - 1 OF--l__SHEETS Calibration
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SOUTHWEST RESEARCH INSTITUTE
~qST 011 .. 1ca OflllAWI! .. 28510 SAN ANTONIO, TEXAS 79.:ZSA Calibration. Record SOURCE Piv 17 MODEL T-150 SWRINO. ~/"-"S~I.___ __
PLUG-INS, ETC. _-_._ _._P~ro~b~e:.......:.~-~/~5:;....o;/_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~ STANDARDS Standard No. MFGR Model Description SIN Cal. Due Cal. Re-:::No. Taylor Q.8~8§'*') Thermometer ..: J'f c .:u 9?---
- ..10.1~
Tavlor(77-13l"'")Thermometer .tj-3-l'f o::.:z.';'7--
- ENVIRONMENT: Temperature 7£ "/ al~.../or A'oo,., It Humidity - - - - - - - - -
Location ~..,.ftuozq :"l":
- Bldg. 68 SwRI I !
PROCEDURE -I C Essentially as outlined in MFG RS Service Manual - - - - - - - - - - - - - - - - - .0:1 Gt SwRI N'uc:lear p .. ojec:s Operat'no t>-gc<>dnra CONCLUSION 0 Item within tolerance:. No adjustment was necessary. 0 Item ADJ/repaired to tolerance - - - - - - - - - - - - - - - - - - - - - - - (:% Item within limits of above procedure, see data sheet. Calibration was in accord with requirements of MIL-STD-4S662, MIL-Q-98S8 and MIL-C-4S208. Mea-surements are traceable to the National Bureau of Standards. Inspection and test data are on file and available for inspection. SIGNED ~ rY~ DATE /7 ,,,'TM f? RECORDNUMBER: ~~~o_n_r._._J_,_o_~_,~- NEXT CALlBRA TION DUE: / / .:J.::4,* 0- (
- G-27
11
..SOUTHWEST RESEARCH INSTITUTE SUBJECT Fascemn DATA SHEET Cal_ibracion of Amnobe. T-1 50 SIN :;j",;~?6
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Chec]<ed h;Jgh t"ange -ac *foUowing pciincs: J SHEET NO. PROJECT DATE BY (S)td.-.._ 1 OF--1.._SHEETS Calibration
/7..");.JV 51 -
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- SOUTHWEST RESEARCH INSTITUTE 8220 CUI.EBA.A llllOAO SAN ANTONIO, TEXAS 71!1294 1s121 ee4.5111
**calibration Record ITEM AM f'~ o,g c 0k' '.:TC: 111 f? SOURCE ~~-)_Jl_/_7_____
MODEL 77,-c; SIN S 30 :1.. ou SWRI NO. _/..__6.-'S.._______ 1 PLUG-INS. ETC. C',.e1J,6'e;'-;11" 1 6 STANDARDS Standard No. MFGR ~ode! Description SIN Cal. Due CJ!. Rec. '.'lo.
- ENVIRONMENT: Temperature----------,..
-5 .5 ~veT Location 7 J"r A/tJCl C"t<J e. .r'.-z aJffc'1'.r PROCEDURE O Essentially as outlined in MFGRS Service-Manual - - - - - - - - - - - - - - - - - -
-r2 "'{.
Humidity--""'/-'"---------
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CONCLUSION 0 Item within tolerance. No adjustment was necessary. 0 Item ADJ/repaired to t o l e r a n c e - - - - - - - - - - - - - - - - - - - - - - - - -
.g flA-i ~,H:;,,_ j,",.,.;tr '2.' ..9,bov£, p.e.."e:."-M, sp-e- µ/£ :-kC.,"'"7' Calibration was in accord with requirements ofMIL-STD-45662. MIL-Q-9858 and MIL-C-45208. Measurements are traceable to the National Institute of Standards and Technology. Inspection and test data are on file and available for inspection.
SIGNED ~ @.d., te
.DATE /? 1@.t f7 RECORD NUMBER: _ ..... o. . o. . . .o. .4. ._?....,6.....0....__ _ _ NEXT CALIBRATION DUE: c 7 S",!"Pr ~ 2
- G-29
.jQUTHWEST RESEARCH INSTITUTE
. DATA SHEET SUBJECT C-9Li13R.~/ltJN oF .t<J"1?f2o8~ -"7.-J~()
SHEET NO, i OF...L_SHEET PROJECT C.<JL/!J'R;Q/loJ DATE I 7 /l/,Q R.. 5 i F/1-:f~M id
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G-30
- SOUTHWEST RESEARCH INSTITUTE 190ST 0-~ICa OlllAWl!lll 281510
- 8220 CUl.EB"A lllOAO SAN ANTONIO. T'EX.AS 71!1294 Calibration Record )
ITEM /.) IY1 p 12. 0 tJ C & 27i&n fJ SOURCE _ _,.,./):....:'..:.i/.......:..../...:.7_ _ __ MODEL
-,--_ISO S I N .. -- .3 -
,J-S"rJ
' -"'- - - - - - - - - - - SWRI NO. _ _ /1 ~ _ _ _ __
PLt.:G*INS. ETC. ., **d""7" *:ti &. rJ/3c It" I 74 SfANDA RDS S1andard :-fo. ~tFGR Model Descrioiian SIN Cal. Due CJ.I. Rec. '.'io. ke-ssLEK.. .1.s-d91g ~er1J\0}11<&iev- S'7 J-7-~I ivr46' 1 l.. cJ I./;_ 1 L 7 ..,-, ~ ~ , ,_A ENVIRONMENT: Temper:uun: Humidicy -"' -4 ** S?t Location . eooti;\. AJI; /lt../)G- 6~; f4.l,Z.T PROCEDL'RE
=::; Essentially as outlined in MFGRS Service ~tanual - - - - - - - - - - - - - - - - - - -
23] ">'NR7 A./ucle:a.¥-8-aj=-c~ g,qera.71ii9 f'~c<:':'d~i Y"-a J<Ti--"'G
-iaS-"'l-CONCLUSION 0 Item within 1olerance. No adjustment was necessary.
0 Item ADJ/n:pain:d 10 1olerance -----=--------------------
~ :Ikm w;lh 1~ l1m~7i af a..bo v<? aroc~eft..1Y-e (""..,,.,. cl1..b. slr*u~T 1 >
Calibration was in accord with requin:ments of MIL-STD-45662. MIL-Q-9858 and MIL-C-45208. Measurements an: m1ce:ib!e 10 the National Institute of Standards and Technology. Inspection and 1es1 data an: on file and available for inspecdon. SIGNED a ..zz::.~.* 1-i?A I DATE 2.. Y /1-f,t? !'<!. 'ii" ~ RECORD NUMBER: _ _ _0_0_0_A.._,: '_-..... ~~!)'---- NEXT CALIBRATION DUE: .;;... '3 .rc:-,.::o;- g '3' I i G-31
SOUTHWEST RESEARCH INSTITUTE DATA SHEET SUBJECT C.AuAtU-rio.:i o c Ai-1 P(l..4)i>C::, r- is-a
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- SOUTHWEST RESEARCH °INSTITUTE
~OST Oll'll'tCI OlltAWI,. 291510 9220 CUL.!:ll"A ROAO SAN ANTONIO. T'!>CAS 119284 Calibration Record ITEM -..:A~M..:....:...f:J-'tZ.....;;;.v_,.tl...::E.__-..,r;;;E'-'&""'°.._ft,......_-:.;;..M._.f)'----------- SOURCE _ 1_v'_l_7.._""'----
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PLUG-INS. ETC:. r'*e*J*.f e:* .,,.,,,. ' .., ~ STANDARDS Standard No. MFGR ~iodel Descriocion S/N Cal. Due C.il. Rec. '.'io. kessLsit.. /.S-a91g 1Ae,-mowi .. i1"' S'-jJ-~"':J.61 lvr.re 9'l.. o (/1.1 '2-
- ENVIRONMENT: Temperarure _ _ _ _ _7 Location 200"".
_......__.-? .:-r- ____ Humidity -----*_.a.._ A ii,..; lit../),:;;. PROCEDURE O Essencially as oudined in MFGRS Service Manual - - - - - - - - - - - - - - - - - - -
~ S/rt RI tUru./ea-tc frajc<:ft g.oer=a..71~t9 f',e.,c<":'do Y"e J<ZT- AG 6~.:;: fa.N?
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- CONCLUSION 0 Icem within colerance. No adjusunent was necessary.
0 Icem ADJ/repaired 10 colerance - - - - - - - - - - - - - - - - - - - - - - - - - i;::: COi Ilem w;JA,.d.. /,;,,.,~"?; of a..bo v@ tarocedf"V"e ) <'"c.G d.*1.h s)'!.6'f . Calibration was in accord with requirements ofMIL-~5662. MIL-Q-9858 and MIL-C-45208. Measurements are crace:ible 10 !he National Ins1iru1e of Standards and Technology. Inspection and cest dai:a are on file and available for* inspection. SIGNED . CLJ;t:;:...,_, tP /.. . . - DATE 1 3 /1-f.o e..l 'i' ' RECORD NUMBER: _ _ _ _ _ _ () __Q_l)._,~1....
?.~7_7....__ NEXT CALIBRATION DUE: _1__.3...._~_t:-_'?.-.1_~_1_ _
- G-33
SOUTHWEST RESEARCH INSTITUTE
.Q.S'"T"'e-M \'
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- SOUTH\VEST RESEARCH INSTITUTE
~220 CULEBfllA AO.AC SAN ANTONIO, TEXAS 7928* *512l 984-5111 Calibration Record ITEM U~, /31At.t~//,4f' ,/~NJW,J#'!' t,J V /Uff-,vs ;717 -#ri<~Z.. SOURCE _ _.;;;;~;;..._;_v_/__;7 __
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/ SIN ---=-~)~~::.....;;0;......:5_-~~;___ _ _ _ __ SWRINO.
PLUG-INS, ETC.
~FGRS TOLERANCE STANDARDS Standard No. '.\1FGR '.\lode: Descriouon SiN C.il. Due C:ii. R~c ..~o.
IJ/,.0 /NI'.: ?P<-1 n..., iY ~ 5{"'7U(j(.
~
r ENVIRONMENT: Temperature - - - - - - - - - - Humidity Loc:mon
.- Es.sentiaUy as outlined in MFG RS Se!"'-'tc: :\1anu:iJ PROCEDURE CONCLL'SiON ~
JI Item within loierance. No adjustment was necessary.
- Item ADJ/repaired lo toleranc: - - - - - - - - - - - - - - - - - - - - - - - -
c1Hhr1':a 1u ***erti 'ti: . l!~ai: 22::2.:e_ _: ? flt.:. 3 5562. ! Ill Q :s.:: 1 1
'!!. ,,... .s:ce. \.1e:i-suremems are traceable to the National Bureau of Slandards. Inspection and lelit data are on file and availabie for inspection.
SIGNED~~ DATE ------~=-"'.:.'_JL~~..:./~f~ RECORD NUMBER: _ _ _n ___11_n_. .:1_*-*40~;;...J')""""-- NEXTCALJBRATION DUE: /,? vv'l. Z,9
- G-35
~e =ep:ify thac :he i~scrumenc describec has had l : 3 oerformance eva:~a=*~
iC *cing,:~ ~he ~rocecures set fore~ by the manufac:urer or procedures ~uc~ec __ Ce a sui:ac~e subscicuce. Where cossible. daca ~as obcainea relating :o =~e
'as fciund" ccncition of the inscrumenc. ~~alibracec" readin~s ~ere ob:ainec
!fcer a ~ecommencec alignmenc procedure was cerformed. The ecuipment used i~
- ,is :ercification have been calibraced with crace~bility to NES.
-~ese services ~ave been pr6vided with reference to PO* 81053 in accordance ~ith cur cuality ~r ::g':"' 3m .
SePtemt:er
- anuar~ :7, 1989 Ovv : ::JC t:oc 52C~
560 :ccc .. ,....C:.""'
-*~-'-' s::~
-74;1~ -0% -5',; -:o; 6\:-:: - -'o1'4
-:co 6CC - :cc : _:c
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v--:: cemceracure a~c ~~mijicv / .;:. = !'7;5;., NBS traceable certificac!:rs are maintained in our fi~es. Calibrated equipment used:
- ..iscomer number: Pl3 CAOOl I Scuchwesc Research Institute Jim Pa!:.:..erson I
P. O. Drawer 28510 6220 C:..1lebra Rd. San Anconi-0 TX 78284 i G-36
- SOUTHWEST RESEARCH INSTITUTE 5220 C:UL.EBlllA AOAO SAN ANTONIO. TeXAS 79%!14 .5121 ee*-s111 Calibration Record SOURCE _ _:Z)::_;_v_/--7°'-'--
MODEL _ _.-.._i.;.*....z...=....1_ _ SIN _ _ _2_c:_c__;;s-;...,;::8:::.,_______ SW R l NO. PLUG-INS.ETC. _ _ _...;..A/;..d_:.¥1....;;,.~_ _ _ _, . . - - - - - - - - - - - - - - - - - - - - - - STANDARDS Standard No. ~FGR :Yfodel Desc:riction S/N C.;J. Due C::i. ~e~. 'Jo.
,A/,,0 hVC. ,~<;(n.._, /Y
- ENVIRONMENT: Temperature - - - - - - - - - - Humidity ---~------
Loc::11ion - - - - - - - - - - - - - - - - - - - - - - - - - PROCEDURE
,... Essentially as outlined in .'.IFGRS Service :'v!anuai - - - - - - - - - - - - - - - - - -
CONCLUSION
~.1. '-' Item within toler:mc:e. No adjustment was necessary.
C Item ADJ/repaired to tolerance - - - - - - - - - - - - - - - - - - - - - - - - 0 --------------------------- c,'ib:C?'ia 18 n ilJJ! j 'ti . !~ * :::c.:zs .. i ? Ill .:TB 1566:2. ? tll 1 ?@50 t '!!' C ::2~ . .\1e:J.* suremenu are traceable to the National Bure:iu of Standards. Inspection and test d:1ta are on ii!e and available. for inspection. SIGNED fl- #.ttZZ:Z.,. ./ DATE ;(Ill ;;:r,_ l"j' RECORDNUMBER: _ _ _ _n_n_o_._J_~.~-'-~-- 1 NEXTCAL[BRATION DUE: /f7f7 /f I G-37
ULTRAVIOLET RADIOMETER we cer~!fy t~at the inscrument described has nad its cerfor~a~~e e*1a~~~=~c .:::.. _.,..::.:_::-; :.= ~~e ~:o:)c~du;"3s set. f<Jr-:..:-i by ':he 'T!ar.uf~cf_:..!r~r- -:;':"" ~r-:c~"J'--Q-s .. --*~- .. __ oe *~ sui:aole subst!t~te. ~here possible, aaca was 0c:a!nec re~dt!~~ =~ =~~
'?s ~ound" condition of the instrument. "Calibratac" reac!ngs ~ere ~~t3i~e~
after a recommended alignment oroceaure was oerformed . . T~e ec~icmen~ ~sec in =~~s cer:ificaticn have been calibrated with traceabili~y :o NES.
-hese services have been =rcviced ~itM refere~ce :o =s= 91053 i~C ~ave oeen crcvidec in accorcance ~i:h our cual!cy cr:gram.
C~RRENT VERs:aN: :.o APCROVE~: Eec:e~cer
- / ' :.-: .
- -s-:-*~ment.: ~VP :-::: radiometer
~~!'":...=_'Jo.: :~osa ~eCC'"": °'40.: 89A67S Car~:f:c~~:on 60C l:.Co ::cc s::0~ 5'?0 :cec C.l80 ~:::o
~enc deviac!on from scancarc: -:~o- - :~.; ~"*
.... a.
.,,,, -~
~.JC
-:oc -_._..,..,...
..._ 3::;:
'5 9*~ --:.oQ .! ---
*. ~" s:.-:.*:
-2*; *J'2; *:~;
=
~ : p 1146 Sheffield Slvd., ~F NBS traceaole ~er~if:ca~:Jr.s Houston, TX 77015 are mai~tained in our fi:es.
Calibrated equipmen~ ~sed: d
'I Customer number: P13 QACCl Southwest Research Institute Jim Patterson P. O. Drawer 28510 6220 Culebra Rd.
San Antonio. TX 78284 G-38
- SOUTHWEST RESEARCH INSTITUTE CERTIFICATION OF CALIBRATION OF ELECTROMAGNETIC PARTICLE PROBES THIS IS TO VERIFY THAT THE EL.ECTROMAGNETIC PARTICL.E PROBES L.ISTEO BEL.OW HAVE BEEN CAL.IBRATEO IN ACCORDANCE WITH SOUTHWEST RESEARCH INSTITUTE NUCl.E.:AR PROJECTS OPERATING PROCE:OURE ./!1-~e-//'f-,c)
- MODEL ANO SERIAL NUMBER DATE CALIBRATED BY
- t---------------------+------1------ ---------l
- G-39
~
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- ~
r: ; /. SOUTHWEST CERTIFICATION RESEARCH INSTITUTE ELECTROMAGNETIC PARTICLE OF CALIBRATION .OF' PROBES THIS IS TO VERIFY THAT THE E!.ECTROMAGNETIC PARTlC!.E PROSES l.ISTED SEt.OW HAVE SEEN CALIBRATED IN ACCORDANCE WITH SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS Of'ERATING PROCEDURE u1-c..~-//~-C) . MODEL AND SERIAL NUMBER DATE CALIBRATED BY
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l i '~- . .,,,...-;;;:- SOUTHWEST RESEARCH INSTITUTE CERTIFICATION OF C.lL!BRATlON OF ELECTROMAGNETIC PARTICLE PROBES THIS 15 TO VERIFY THAT THE E!..EC;"ROMAGNETIC PARTIC:..S: PROBES LISTED BELOW HAVE 8E!::N C.l.LJSRATEO IN AC::ROANCE WITH SOUTHWEST RESEARCH INSTITUTE NUCLEAR PROJECTS OPE.RATING PROCEDURE ;tL/- e- u . . 4. o . MODEL AtlD SERIAL NUMBER I DATE I CALiBRATE:J BY
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No. _ _().-........1..... REFERENCE. PRocEol.fiE Xlr-FE- lrJl1 -(}- ei..,t, ALIGNMENT oF *soN1c FTs MARK .I FLAW DETECTOR I. CURRENT ORAi~ Ji 3 (.. MA.
- 2. AMPLITUDE LINEARITY I% FSH
- 3. CALIBRATION OF GA!N ( COARSE ) ot
. 4. CALIBRATION OF GAIN DB ( FINE ) ot
!5. HORIZONTAL LINEARITY I% FSW 6.
CHECKS OF POTS A~D SWITCHES: FREQUENCY MHZ Ot REJECT ot.. RANGE al~ DELAY POT. <Pt FILTER d21~ MATL. CAL. <DIS REP. RATE Q{( DELAY SW. Q/( VIDEO SW. "2~ THRU TRANS - NORM . or DAMPING 12~ DEC. }J f 8 6 DB SWITCH Q~ 14 DB SWITC~ fj2f(
.7. LOW BATTERY LIGHT ADJUSTMENT :
( JUST ON AT 10 :75 VOLTS) _ _.Q._J(~--------------- Ir CERTIFICATION : ALIGNMENT PERFORMED ( DA.TE )
- G-43
INSTRUMENT VERIFICATION RECORD INSTRUMENT SERIAL NO. or I 0'1 E AMPLITUDE LINEARITY CONTROL LINEARITY LARGER ECHO SMALLER ECHO ACTUAL 80 O/o -6 DB JtiJ % NOMINAL O/o 1-1 O/o
~'° 80 -12 DB 100 % 50 O/o Ofq FSH 90 % 45 % H-r 40 O/o + 6 DB Y1- O/o 80 °/o 40 °/o ffrD
- 20 % + 12 DB 1j O/o 70 o/o . 35 O/o '.)~
60 % 30 °/o '.}IO CJ 50 % 25 °/o 1;- I +:- +:- 40 % 20 °/o '1.-0 DISTANCE LINEARITY 30 °/o 15 % 1-l ACTUAL THICKNESS ULTRASONIC MEASURED 20 % 10 °/o 111 10 11 10 6D8 8 14 DB SWITCH LINEARITY 9" q 100% - 6D8 J.f (.., O/o e" ~ IJ O/o 7 100 % - I 4DB 7" 40% + 6D8 b:t'
..... O/o 6" tz....
10% t 14DB ~_j O/o 5"
~
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~------------
- ~ I SONIC FTS -MARK I FLAW DETECTOR CALI BRAT ION I OPERATIONAL CHECKLIST FOR SONIC FT S MK I No. CJ///0£ REFERENCE - PROCED~E ')(j/-FE._-j()t_,-Q C#/,, ALIGNMENT OF SONIC F_TS MARK :I FLAW DETECTOR I. CURRENT DRAIN Volz MA.
- 2. AMPLITUDE LINEARITY !% FSH
- 3. CALIBRATION OF GAIN ( COARSE ) v. c 4, CALIBRATION OF GAIN DB ( FINE ) 0. ,J::
- 5. HORIZONTAL LINEARITY / % FSW
- 6. CHECKS OF POTS AND SWITCHES:
FREQUENCY MHZ 0, ,<, REJECT /'). < RANGE /'J. K, DELAY POT. /J_,r, FILTER CJ. K. MATL. CAL. f3.,,r-REP. RATE a.;::, DELAY SW. /"J. -~ VIDEO SW. 0 /<', THRU TRANS - NORM . 0? .. c. DAMPING 6 DB SWITCH.
//.~
c:J' /(-_ DEC. 14 DB SWITCH
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- 7. LOW BATTERY LIGHT ADJUSTMENT :
( JUST ON AT 10: 75 VOLTS) o/v: rr CERTIFICATION : AtlGNMENT PERFORMED BY :
~
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( DATE )
- S'Of ~I ~ 0~11 P'll - -
II 2 G-45
INSTRUMENT VERIFICATION RECORD SERIAL NO. DATE r0///0c AMPLITUDE LINEARITY CONTROL LINEARITY I lj-{) O/o LARGER ECHO SMALLER ECHO ACTUAL 80 °/o -6 DB NOMINAL
.;l D . O/o S-0 % FSH 80 °/o -12 DB 100 % 50 %
90 °/o 45 O/o <<s-% 40 °/o + 6 DB
<;{) O/o 80 °/o 40 °/o 20 O/o + 12 DB
.?a %
70 % 35 O/o 60 % 30 % 50 % 25 % 40 % 20 O/o DISTANCE LINEARITY 30 % 15 °/o ACTUAL THICKNESS ULTRASONIC MEASURED 20 % 10 °/o 10 11 JO 6D8 8 14D8 SWITCH LINEARITY .g" 100 % - 6D8 O/o 8" 100 % - 14D8 O/o 7" 40% 10%
+
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- SONIC FTS MARK I FLAW DETECTOR CALIBRATION I OPERATIONAL CHECKLIST FOR SONIC FT S MK I No.
REFERENCE PROCED~E ,ef£=--;E-,j'J/'Lf1~L I GNMENT OF SONIC FTS MARK :C FLAW DETECTOR I. CURRENT DRAIN -fJJ.. MA.
- 2. AMPLITUDE LI NE AR ITY I % FSH
- 3. CALIBRATION OF GAIN ( COARSE )
- 4. CALIBRATION OF GAIN DB ( FINE )
- 5. HORIZONTAL LINEARITY I % FSW
- 6. CHECKS FREQUENCY RANGE FILTER OF POTS MHZ ANO SWITCHES:
;1'3,/-
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- 7. LOW BATTERY LIGHT ADJUSTMENT :
( JUST ON AT 10; 75 VOLTS) CERTIFICATION : ALIGNMENT PERFORMED BY
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- s**111 ~01111 1'11-11-2 G-47
INSTRUMENT VERIFICATION RECORD
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_3 cl.A// L:.__ /l!k.z-SERIAL NO. CJ/1/-1'6 DATE JI//1/1/~# J t AMPLITUDE L INEARIT Y CONTROL LINEARITY LARGER ECHO SMALLER ECHO ACTUAL 80 O/o -6 DB 3? %* NOMINAL
/7 100 %
90 % 50 % 45 °/o
.,5
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-12
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DB 6 DB fJL O/o O/o 80 % 40 °/o -to 20 O/o + 12 DB (?*7
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60 O/o 30 % J]{)
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4" -1._ 3" .3 2" 2 1" I
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I TEST BY:
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(SrGNATURE)
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- 8D SONIC FTS MARK :r FLAW DETECTOR CALI BRAT ION I OPERATIONAL CHECKLIST FOR SONIC FT S MK I No. ¢ l/cl.D G REFERENCE* PRocEDl.flE X.P-;::tf-{P~-o c4* 1, ALIGNMENT OF SONIC . FTS MARK I:
FLAW DETECTOR I. CURRENT DRAIN ¥6{) MA.
- 2. AMPLITUDE LINEARITY I % FSH GAIN ( COARSE )
e;I<'
- 3. CALIBRATION OF CJf(
- 4. C-ALI B,RATION OF GAIN OB ( FINE )
- 5. HORIZONTAL LINEARITY /3 FSW
- 6. CHECKS OF POTS ANO SWITCHES.:
o/(* e;)( FREQUENCY MHZ REJECT RANGE t)/f DELAY POT. ok O'C FILTER MATL. CAL. oK REP. RATE t)k DELAY SW. o.r VIDEO- SW. t;K THRU TRANS - NORM . ok' DAMPING {)K' ' DEC. ~A 6 08 SWITCH DK 14 OB SWITCH t?lf
- 7. LOW BATTERY LIGHT ADJUSTMENT :
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- 3. CALIBRATION OF GAIN COARSE )
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- 5. HORIZONTAL LINEARITY )' % FSW
- 6. CHECKS OF POTS AND SWITCHES:
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- 7. LOW BATTERY LIGHT ADJUSTMENT :
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- G-51
INSTRUMENT VERIFICATION RECORD
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- z. AMPLITUDE LINEARITY I O/o FSH
- 3. CALIBRATION OF GAIN ( COARSE ) w
- 4. CALIBRATION OF GAIN DB ( FINE l tJL
,I O/o HORIZONTAL LINEARITY FSW 5.
( 6. CHECKS OF POTS AND SWITCHES: FREQUENCY MHZ tJt' REJECT tl/ RANGE &C DELAY POT. t2C FILTER (),f' MATL. CAL. tU* REP. RATE 4( DELAY SW. ~-I-VIDEO SW. *ot THRU TRANS - NORM . -CJ"+t:.----- DAMPING Of- DEC. Al/4 6 DB SWITCH or 14 D 8 SWITCH _ ____...a~~'--------
- 7. LOW BATTERY LIGHT ADJUSTMENT :
( JUST ON AT 10 ;75 VOLTS)
.Ir CERTIFICATION :
ALIGNMENT PERFORMED BY ( DATE ) G-53
INSTRUMENT VERI FICA TIO N RECORD
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S~RIAL NO. t.9.:?.33 oe DATE S/I~/{' 87 AMPLITUDE LINEARITY CONTROL LINEARITY LARGER ECHO SMALLER ECHO ACTUAL 80 O/o -6 DB 3B O/o NOMINAL 100 % 50 O/o so 0
/Q FSH 80 O/o -12 DB 19 O/o 90 % 45 °/o #S 40 % + 6 DB g3 O/o 80 °/o 40 °/o -fo 20 O/o + 12 DB 8J O/o 70 % 35 O/o J~
60 % 30 % . lo 50 % 25 °/o .25 40 % 20 % 20
- DISTANCE LINEARITY 30 % 15 % /:.£ ACTUAL THICKNESS ULTRASONIC MEASURED 20 % 10 °/o /ll
*10 11 L<l.
6DB a 14 DB SWITCH LINEARITY 9" 9' 100% - 6DB ?C/ O/o a" 9 100 % - I 4DB // O/o 7" 7 40% + 6DB 91 O/o s" t 10% + 14DB s.=;:. O/o . 5" > 4" "'/ 3" ~ 2" 2 1" I TEST BY : ~&M~
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REFERENCE. PROCED~E Y//-rF-/('£*-Dul{ ALIGNMENT OF SONIC FTS MARK I: FLAW OETECTO~ CURRENT DRAIN 9'so MA. AMPLITUDE LINEARITY / 0 i0 FSH CALIBRATION OF GAIN ( COARSE ) -~./C. CALIBRATION OF GAIN DB ( FINE ) .CY..<- HORIZONTAL LINEARITY I O/o FSW CHECKS OF POTS AND . SWITCHES: FREQUENCY MHZ REJECT c::J.c. RANGE DELAY POT. . '?.r-FILTER 0 . ..C. MATL. CAL. ~./C. REP. RATE Q /- DELAY SW. . /} ./(.. VIDEO SW. C2 .,k
- THRU TRANS - NORM . ?**C DAMPING G) ~L * /Zh/;
6 DB SWITCH _ _ _ _ _ _..;:.;v_-:J_.*c;....._:;....*- - ~!co.a SWITCH >?. ,~r.
- 7. LOW BATTERY LIGHT ADJUSTMENT :
( JUST ON AT 10. 75 VOLTS)
.I! CERTIFICATION :
ALIGNMENT PERFORMED BY : J ( DATE )
- G-55
INSTRUMENT VERI FICA Tl 0 N RECORD if~*_;/;;~) INSTRUMENT SERIAL NO. ' DATE S l')/l) IC_ ...C: T'5 //'/L £ ~ c/. ~---?.-2 £ 9/"~~xP? AMPLITUDE LINEARITY CONTROL LINEARITY LARGER ECHO SMALLER ECHO ACTUAL 80 O/o -6 DB Ljo O/o NOMINAL 110 O/o -12 DB :;20 O/o 100 % 50 °/o 5*--0 °/Q F SH 7"'°'5--- 4;_ O/o + 81 O/o 90 % . 45 % 40 6 DB 80 % 40 °/o 5/o ~ ( 20 O/o +
!2 DB /lo O/o 70 % 35 O/o ~r- ~
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60 % 30 O/o 3n ::t 50 % 25 O/o <?2-S- J6 40 % 20 O/o =2..o ;.?, DISTANCE LINEARITY 30 % 15 °/o /S-ri? ACTUAL THICKNESS ULTRASONIC MEASURED 20 °/o 10 O/o /U~ 11 L/J /( 6DB a 1408 SWITCH LINEARITY 10 9" l c-, '( 100 % - 608 cj_9 O/o *a" f 'r 100 % - 1408 /~ O/o 7" 71r 40% .. 608 79 O/o 6 lb ,, II 10% + 14DB *s-1 O/o 5" [!. /ll. 5
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INSTRUMENT VERIFICATION RECORD SERIAL NO. DATE D&' 01-- 11.Jl.,4 &' AMPLITUDE LINEARITY CONTROL LINEARITY LARGER ECHO SMALLER ECHO ACTUAL 80 O/o - 6 DB H (:, % NOMINAL
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REFERENCE* PRO~EDURE X1I-:FE-/t}"6 ' 6 CA I
- ALIGNMENT OF SONfC FTS MARK :I FLAW DETECTOR I. cuRi:iENT DRAIN 7130 MA.
- 2. AMPLITUDE LINEARITY I O/o FSH OJ(
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S.W.R.I. CERT DATE: APR 12, 1989 NAME OF OPERATOR : B.HUFFMAN ULTRASONIC TRANSDUCER ANALYSIS REPORT TRANSDUCER* INFORMATION _Page I of 2 MANUFACTURE: AEROTECH SERIAL NO: 013718
. CASE STYLE: RECT. TEST ANGLE = 0 .
CRYSTAL SIZE: .50 X 1.0 FREQUENCY = : 2.25
--------------~--------------------------------~---------?---------------------
WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION :18 MODE =:NORM REP. RATE = :015 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : = Switch to INT TRIGGER *
- TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK s.* 0. H.
-----------------------------------------------------------------------~-------
FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM : 1 .8 Mhz FREQUENCY-= : 2.11 Mhz MAXIMUM= : 2.7 Mhz ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL :MARK I SERIAL No. :01109E
~OT. APPLICABLE £?/
Ob 'SETTING : DATE
ili O/A PLOT REQUIRED ON TRANSDUCERS rD BE MOUNTED ON *A WEDGE AND/OR USED CERTIFICATION PERFORMED IN ACCOR~L~rSM~~II-FE-126 .
G-71
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: 013718 PAGE 2 of 2 CERTIFICATION DATE: APR* 12, 1989 ANALOG '3CRN
.10~~~~~~~~~~~~~~~~~~---.
ATTEN 14. 4 dB \I 0 t 1ia. iaia a g e
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- S. W.R. I.
CE;RT DATE: APR 5 , 1989 . NAME OF OPERATOR : 8.HUFFMAN ULTRASONIC TRANSDUCER ANALYSIS REPORT TRANSDUCER INFORMATION Page 1 of 2 MANUFACTURE:. AERO TECH SERIAL NO: 11278 CASE STYLE: RECT TEST ANGLE = .. 0 eRYSTAL SIZE: . 50 x 1.0 FR~QUENCY = : 2.25 WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #: 1Z14 TYPE: HP WAVEFORM RECORDER MODEL: Sl80A SERIAL #:2318A00667 UTA SETTING ATTENUATION :13 MODE =.:NORM REP. RATE = :015 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : =Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION PLASTIC SALL BLOCK S. 0. H.
FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM : 1.8 Mhz FREQUENCY= : 2.27 Mhz MAXIMUM = : 2.7 Mhz ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL :MARK I SERIAL No. :01109E Ob SETTING : NOT APPLICABLE /!# *.:
------------------------------------------------------------------------------~
1 DATE NO O/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A WEDGE AHO/OR USED CERTIFICATION PERFORMED IN ACCORO~~~G~~~~1I-FE-i26
-------------------------------~--------------------------~--------------------
G-73
---------------~---,----------------
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: 11278 PAGE : of 2 CERTIFICATION DATE: APR 6, 1989 ANALOG scm,1
. RTTEN l 4 . 2 d8
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- S. W.R. I .*
CERT DATE: APR 6, 1989 NAME OF OPERATOR : 8.HUFFMAN UL TR ASON IC TRANSDUCER ANALYSIS REPORT TRANSDUCER INFORMATION Page 1 of 2 MANUFACTURE: AERO TECH SERif!L NO: 11 279 CASE STYLE: RECT TEST ANGLE = 0 CRYSTAL SIZE: . 50 x 1 .(} FREQUENCY = : 2.25 WAVEFORM AND POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #: 1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION :13 MOOE = :NORM REP. RATE = :015 EXT. & INT. PULSER = S~itch to INT PULSER EXT. & INT. PULSER : = S~itch to INT TRIGGER TARGET REFLECTOR INFORMATION
----------------~--------------------------------------------------------------
PLASTIC BALL BLOCK S. D. H. FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM = : 1 .8 Mhz FREQUENCY= : 2.19 Mhz MAXIMUM = 2.7 Mhz ULTRASONIC INST. -- DAC CURVE TYPE : SON IC MODEL : MARK I SERIAL No. : 01109E _____________________________ ::_::::~::_~----------~-QI_~~f-~1~-~~~~--~---- SGNATURE D_ATE NOD/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED OH A WEDGE AHO/OR USED CERTIFICATION PERFORMED IN ACCOROANCJ\S Nf~ ~E-126 G-75
S.W.R.I.* ULTRASONIC TRANSDUCER ANALYSIS 'REPORT MANUFACTURE: AEROTECH SERIAL No: 11279 PAGE 2 of 2 CERTIFICATION DATE: APR 6, 1989 ANALOG SCAN
- ATTEN
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- 5.W.R.I.
CERT DATE: JAN 3J, I 989 NAME OF OPERATOR : 8.HUFFMAN ULTRASONIC TRANSDUCER ANALYSIS REPORT
-----------------------------------------~-------------------------------------
TRANSDUCER INFORMATION Page I cf 2 MANUFACTURE: AERO TECH SERIAL NO: Al 1510 CASE STYLE: RO DUAL TEST ANGLE = 0 CRYSTAL SIZE: *. :s0 FREQUENCY = . "'" .... -'c: I ., .., WAVEFORM ANO POWER SPECTRUM INST.' JYPE:-AEROTECH MODEL: UTA-2 SERIAL ;;: I: 14 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION = :0 MODE = :THRU REF. RATE* = :015 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : = Switch tc INT TRIGGER
- TARGET REFLECTOR INFORMATION OTHER= :1 INCH SECTION ON'PT 300 BLOCK FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM = : l .9 Mhz FREQUENCY = : 2.A: Mh: MAXIMUM= : 2.7 Mh:::
ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL : MARK I SERIAL No. :0110'3E SETTING : NOT APPUCABLE ~~~W~*- - Db
- ~CATE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED .ON A WEDGE AND/OR USED CERTIFIC11TION PERFO~MED IN AC~~S~E*1~H )(II-FE-1.::6 G-77
S. W.R. I. . IJL TRASON IC TRANSDUCER._.ANALYS IS REPORT MANUFACTURE: AEROTECH SERIAL No: Al 1510 FAGE :: .;:f :: CERTIFICATION DATE: JAN 30, 1989 RNRL*)G :=.cRr*.j RTTEN 3. 3 dB
.10.--~----------'---~----'-~ -. 11!1'---_.__ __.._ _....__ __.__ _..___ _,__ _:....__....J t:J 2 4 10 lE Ttrne lusec1 I
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2 3 5 Megahert= G-78
- S.W.R.I.
CERT DATE: OCT 14, 1988 NAME OF OPERATOR : 8.HuFFMAN uLTRASONIC TRANSDUCER ANALYSIS REPORT
------------------------------------J------------------------------------------
TRANSDUCER INFORMATION Page 1 of 2 MANUFACTURE: AEROTECi1. SERIAL NO: 8j4232 CASE ST"'t"LE: DIAMOND TEST ANGLE = 0 CR.rSTAL SIZE: . 25 FREQUENCY = : 2.25 WAVEFORM ANO POWER SPECTRUM INST.
-----------------------------------------------------------------~------------
TYPE: AEROTECi1 .r100EL: UTA-2 SERIAL ;;::12i4 TYPE: ~p wAVEFORM RECORDER MODEL: 5i80A SERIAL ;;:~2318A00667 IJTA SETTING ATTE~iUATION * : 12 MOOE = :NORM REP. RATE = : 01 s E:'T & INT PULSER = Sw1tcn to INT PULSER E:~T & INT PULSER : = Si.lit en to H1T TRIGGER
-----------------~-------------------------------------------------------------
TARGET REFLECTOR INFORMATION PLASTIC BALL. 8LOCk S. D. ~. FREQUENCY ANO SPECTRUii*ANAi..YSIS ACCEPTABLE MEASURED ACCEPTABLE i .8 Mn: FREQUENCY : , 2. i j Miiz iiAxIMUM = 2.7 Mn: ULTRASONIC INST. -- OAC CuRVE TYPE :SONIC MODEL :iiARk I SERIAL. No. :0i i09E Db SETTING : NOT APPLICABLE_fJ ......ft DATE NO DIA PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A W~DGE AND/OR USED
--------*---** ~~MrUMM~U
________ -*lN *--~S~G~E.BEMt*. _____ _
~~Kl1r1~M\1UN M~~UMUMN~~ W!IH x11-r~-j~b G-79
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*_=.:-:.i JATE: ig88 Fage
- ~* *----.....
~., 1Ui:-!"lt"!I'~
TRANSDUCER :NFQRHriTICN "1EROTECH :ER~riL Nu: DIAMOND TEST riNGi....E
*_;-.~':ii1!.... :.:.::...:.:
. --*~
;:RE~UENCY _.:s
------------------------------------------------------------------------~------
..' .--- .. i100E:...: CJTA-: . . .:.
- 1CuE:...: =:3v.Jri -- ... -*
_._j ..... ._
----------------~--------------------------------------------------------------
0 i*lODE ; f'lUF'M -'-- - - : ..' - E:*~ T & INT :-"\.Jl...:~:-.
-* 11 ---
- w~ ~'.
., 0 : :ff ..:~*=::.-
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- TARGET REFL£CTGR !NFORMATIDN H.
~*- _::,:-. -~~=-
-------* ,,,..c.:..:.* ;a:=r.
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. ---- - --=. - '-=
- * - *... .::.:""" r
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!.JL TRASGN IC i1GOE:... : MAF~: SERIAL r~o. ::31 ~0~E Db SET!ING NOT APPLICABLE ~iii SIGNATURE DATE
- CERTIFICATibN PERFORMED IN ACCORDANCE WITH XII-FE-1:6 G-81 NO DIA PLOT REQUIRED ON TRAHSDUCERS TO BE MOUNTED ON A WEDGE AHDJOR USED AS ANGLE BEAM.
*I *11 1l1 I~~ I~ I I t:
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- =.!.J.R.I.
- ERT iJ,"lTE: j,<;N 3Q, : ggg 1
NAME OF OPERATOR : 8.HUFFMAN
~LTRASONIC TRANSDUCER TRANSDUCER INFORMATION
~NALiS!S REPORT
.~:ge ; ::r :
r*1ANUFACTURE: ~ERO TECH SERIAL NO: E09487 CASE STYLE: RO DUAL TEST ANGLE = !J CRYSTAL : IZE: .:50 FREQUENCY = : 5.0 WAVEFORM ANO POWER SPECTRUM INST. TYPE:*-AEROTECH MODEL: 0TA-: :E~ IAL ::: : 1: 1 4 TYPE: HP WAVEFORM RECORDER MODEL: Sl80A :ERIAL ;:23l2A00657 UTA *:ET"'.": ~JG ATTENUATION = : '3 MOOE = : THRU REP. RATE = * *~ I C:
*VI-EXT. 0
<.X INT. PULSER Switcn ~ *~ INT ?UL SER EXT. u< INT. PULSER : = Switcn t .J INT TFIGGEP
- OTHER = ~
TARGET REFLECTOR INFORMATION I INCH SECTION ON PT 300 BLOCK FREQUENCY ANO SPECTRUM ANALYSIS ACCE?TA6LE ~EA SURED ~CCEPTASLE MINIMUM : .; ,. ,~.~ h: ~REQUENCY =: ~.s: Mhz f"1AX iMUM = ULTRASONIC r~ST. -- OAt CURVE 7YPE :SONIC MODEL : :1ARI< i :ER!AL f'ia. :JI !liJ'3E Ob SETTING :
.-~OT APPLICABLE W_.__
.;.:.:..di......
7 C1ATE NO DIA PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A WEDGE AND/OR USED
~ERTIFISAT!CN PERFORMED :N . - l"'"'Rr1 f\L.._u .1..lr.!*1 AS AliGl.f. BEAM._~ -=-.;* _::
'* ' 1 C.E,-,.,, .i.: ;-, '.i. ... - -
G-83
- ,N*"*** LTRASONIC T?ANSOUCER ~NALY~:~
~ANUFACT~RE: ~E~OTE H ~ERIAL No: EJS487 -:if -
- ERT:F!CATION CATE: AN 30, 1ggg rir*.JAL,y:; ::,,:fii . J
- !!Er*l 3. 3 dB
. ~J . - - - - - - - - . . . . : . - - - - - - - - - - - - - - - - . . ,
I I l i I I i
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G-84
- S.W.R.I.
CERT DATE: JAN 30, 1989 NAME OF OPERATOR : B.HUFFMAN ULTRASONIC TRANSDUCER ANALYSIS REPORT Page 1 of 2 TRANSDUCER INFORMATION MANUFACTURE: AERO TECH SERIAL NO: E18324 CASE STYLE: RO .DUAL TEST ANGLE = 0 CRYSTAL SIZE: .250 FREQUENCY = : :.25
---------------------------------------------------~---------------------------
WAVEFORM ANO POWER SPECTRUM INST. TYPE~-AEROTECH MODEL: UTA-2 SERIAl #:1214 TYPE: HP WAVEFORM RECORDER ~ODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION = ~0 MOOE = :THRU REP. RATE = :015 EXT. & INT. PULSER = Switch to INT PULSER EXT. & INT. PULSER : = Switch ta INT TRIGGER
- OTHER= ~1 TARGET REFLECTOR INFORMATION INCH SECTION ON PT 300 BLOCK FREQUENCY AND SPECTRUM ANALYSIS
----~---------------------------------------------------------.-----------------
ACCEPTABLE MEASURED ACCEPTABLE MINIMUM = FREQUENCY ., .,.., MAXIMUM =
- 1. 8 Mh: ~ ..... ' : 2.7 Mh:::
ULTRASONIC INST. -- DAC CURVE Pr'PE :SONIC MODEL :MARK I SERIAL No. :01 l09E Ob SETTING : NOT APPLICABLE ff# j/ DATE NO DIA PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON AWEDGE ANO/OR USED CERiIFICATION PERFORMED HJ ACCOROA~~~B~... i=E-l :s G-85
s:w.R.I. ULtRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: E18324 FA6E : .::, f : CERTIFICATION DATE: JAN 30, 1989 RNRL1)13 ~::;cRr*~ RTTE!*l 3. 3 dB
-. HJ
~ ~ 8 a 114 i.: l-+ lf; Time I IJSE'C')
POHE? ~PE1:T?UM tia1~ ( I "
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G-86
-------------~-----------------------------------------------------------------
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT CERT DATE: JAN I 1 , 1 989 Page 1 of 2 NAME OF OPERATOR : G.CAYWOOD TRANSDUCER INFORMATION MANUFACTURE: AEROTECH SERIAL NO~ F30806 CASE STYLE: RO TEST ANGLE ~ 0 CRYSTAL SIZE: .25 FREQUENCY * . : 2.25 WAVEFORM AND POWER SPECTRUM' INST.
-----------------------------------------------------------------~-------------
TYP:: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667
------------------------------------------------~------------------------------
UTA SETTING ATTENUATION :20 MODE = :NORMAL REP. RATE = :015 EXT. & INT. PULSER = Switch to INT PULSER EXT. & INT. PULSER : =Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION 3/32 IN. 113 T HOLE IN PT 300 SLOCK FREQUENCY AND SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM = : 1 .8 Mhz FREQUENCY = : 2.27 Mhz MAXIMUM a : 2.7 Mh:
ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL : MARI\_ I SERIAL No. :01109E Ob SETTING : 34
- CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-126 DATE G-87
S.W.R.I. ULTRASONIC TRAN-SOUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: F30806 PAGE Z of 2 CERTIFICATION DATE: JAN 11 , 1989 RNRLOG SCAN RTTEN 23. 3 dE
.11-1.------------------~
0 1~.lil~ ~1\tvv\[\JVVIJV\f' t a g e
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- .. ',i.F..I.
--------~----------------------------------------------------------------------
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=. r-11...:Fri"'P:~~
T~ANSOUCER INFORMATION
;;)
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"ANuF:":CTURE: ~E?iJTE*:H :ERIAL NO: G216Si POUrlO DUAL TE:i ANGLE = *zi
.2S;) ;;:;E*:uE~JC'! =
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- S ~GCE = :~HRU RE?. ~ATE ** t'.\'
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- AL ~le. :0110'.:E NOT APPLICABLE~~~/?'""---~* - -
- CERTIFICATION PERFORME~
/ DATE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A WEDGE AND/OR USED IN ACc~A~~~§~ :<II-FE-1:6 G-89 I
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- ~: - 391:':!
.: .=. r:. =*
-------------------------------------~--------------------~-----------~--------.
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT CERT DATE: MAR ;:; , 1.989 Page i *=* f ;:; NAME OF OPERATOR : R.SCHAEFER TRANSDUCER INFORMATION
--------------------------~----------------------------------------------------
MANUFACTURE: ,C\EROTECH SERIAL NO: H07930 C,°\SE STYLE: or TEST ANGLE = 0 CRYSTAL SIZE: 0.25 FREQUENCY = : 5.0 WAVEFORM ANO POWER SPECJRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 urn SETTING
.:; TTENU,'1 TI ON : 1 I MOOE = :~WRM REP. RATE = :015 EXT.
EXT. 0
<:I 0
<:I INT. PULSER ~*Wl tch INT. PULSER : = ~.w1t~:h .+.... ..._.-
cu INT PULSER
- INT TRIGGER
- TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. 0. H.
------------------------------------------------------------------~------------
FREQUENCY ANO SPECTRUM ANALYSIS
,C\CCEPT ,11BLE MEASURED P1CCEPT.'18LE MINIMUM = : 4 Mhz FREQUENCY = : 4.51 Mhz MAXIMUM = ~ Mhz ULTRASONIC INST. -- OAC CURVE TYPE : SONIC MODEL : MARI< I SERIAL ~fo. :01109E Db SETTING :
NOT APPLICABLE
----------------------------------------------------------------------------~~-
-r> '
0,11 TE
- NO DIA PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED. ON A WEDGE AND/OR USED AS ANGLE BEAM.
CERTIFlCATION PERFORMED IN ACCORDANCE WITH XII-FE-126 G-91
S:W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: H07930 CERTIFICATION.DATE: MAR 2, 1989 Ri'IRLOG SCRt'1
- ATTEt*.J 7. 2 dB
.l0~------------------.
'v'
- l
('1 . a I,'\ L} ,..r .....--------.-*-- I
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G-92
- . S.W.R.I. ULTRASONIC TRANSDUCER ANAL?SIS REPORT CERT DATE: MAR 17, 1989 NAME OF OPERATOR : R.SCHAEFER TRANSDUCER INFORMATION Page 1 of 2
. MANUFACTURE: ,~ERO TECH SERIAL NO: H24817 CASE STYLE: DIAMOND TEST ANGLE = 0 CRYSTAL SIZE: 1/4 FREQUENCY = : 2.25 WAVEFORM AND POWER SPECTRUM INST.
TYPE: AEROTECH MODEL: UTA-2 SERIAL#:t214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION :20 MODE = :NORM REP. RATE = :015 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : = Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. 0. H.
FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED PiCCEPTABLE MINIMUM = : I. 8 ~lhz FREQUENCY = : 2.34 Mhz MAXIMUM = .
'-*I *'1hz ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL : MA Rf< I SER I AL No. : 0 t I 09E Ob SETTING : NOT APPLICABLE I ( )
DATE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE ~.WUNTED ON A WEDGE AND/OR USED
.~~ ,'-'.i'iLiLt 8cf.h.
CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-1:5 G-93
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: H24817 PAGE ~ of 2 CERTIFICATION DATE: MAR 17, 1989 ANALOG :3CRN RTTEN 6. 6 dB
.Hl.------'--__;:;;;-----'---------
~
v ~ I**"""__. . . . . . ,.,. . . .------1 '~,,~-~-'-"'-"'"'-*--I g I. I I I
-. J EJl-_ _..___.....__ __..__
I __.._ _ ...___.....__~---' I Gl l~]i;J ----i----------------~ I/ ' ! ! i
/I \ I p
e !I \ I I ., I 1' \, I r~0~---+-'-'*----'---+----'+-----~--~ c / I \ I I e n I \ l i
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.___.;.........____-'-__ i __.I___ -===-=---==-I
---------1
- i .2 ~ 4 :
r1egai*1er-c:;: G-94
- S.W.R.I.
CERT DATE: MAR 17, 1989 ULTRASONIC TRANSDUCER ANALYSIS REPORT NAME OF OPERATOR : R.SCHAEFER TRANSDUCER INFORMATION Page 1 of 2 MANUFACTURE: AEROTECH SERIAL NO: H24831 CASE STYLE: DIAMOND TEST ANGLE = 0 CRYSTAL SIZE:* 1/4 FREQUENCY = : 2.25 WAVEFORM AND POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SER I AL :ii: : 12 14 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL :ii::2318A00667
-----------------------------------------------------------------------~-------
UTA SETTHIG ATTENUATTON :20 MOOE = :NORM REP. RATE = :015 EXT. ~ INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : = Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. 0. H.
FREQUENCY AND SPECTRUM ANALYSIS
- 1CCEPTABLE MEASURED ACCEPTABLE MINIMUM : I. 8 Mhz !="REQUENCY : 2.34 Mhz MAXIMUM = . .,
- i.....
( Mh: ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL : MARK I . SERIAL No. : 01109E Ob SETTING : NOT !~PFL'.CABLE___._R. .5_-__ . _
~~ I '7 l't 4C \ '1.S-'"( ~sI<=ATURE DATE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A WEDGE AND/OR USED AS ANGLE BEAM.
- ERTI~ICATION PEFFORMEO IN ACCORDANCE WITH ~II-FE-!ZS G-95
S.W.R.I. ULTRASONIC T~ANSOUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: *H24831 PAGE . . of 2 CERTIFiCATION DATE: MAR 17, 1989 m.JALOG' :~CRt-1 RTTEN :3. 6 dB
-. HJ'----'----"-----'-------------~
"1 12 l4 JE; Ti me ;, 1.i.;;e:i:)
I / \. f ' I \ I I i i \ I p I \
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/ I \
n I / I \ I t \ I a [,.----.. . ____ I
.;J* .
\
*-*-. _***-L__ ].
a t1egaheri:= G-96
-------~-----------------------------------------------------------------------
S.W.R.I. ULTRASONIC TRANSDUCER ~NALYSIS REPORT CERT DATE: MAR 17, 1989 Page 1 of 2 NAME OF. OPERATOR*: R.SCHAEFER TRANSDUCER INFORMATION
------~------------------------------------------------------------------------
MANUFACTURE: AEROTECH SERIAL NO: H24832 CASE STYLE: DIAMOND TEST ANGLE =. : 0
*CRYSTAL SIZE: 1/4 FREQUENCY= : 2.25 WAVEFORM AND POWER SPECTRUM INST.
TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A0086~ UTA SETTING ATTENUATION :20 MOOE = :NORM REP. RATE = :015 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : =Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. D. H.
FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM = : 1 .8 Mhz ~REQUENCY = : ~.27 Mhz MAXIMUM = : 2.7 Mhz ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL : MARK I SER I AL No. : 01 109E Db SETTING : NOT APPLICABLE -!()" DATE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED. ON A WEDGE AND/OR USED AS ANGLE BEAM. CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE~1:6 G-97
5.W.R.I. ULTRASONI~_TRANSOUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: H24832 PAGE : cf : CERTIFICATION DATE: MAR 17, 1989 ANALOG '.3CAN RTTEt-.J
,]0,...---------------------, :3. 4 dB
,r ~./ t 1 a .
<1.lillil --~--- -A I ~~t~
- ~ I)
~J I I I I "1 2 b a u:1 12 l-+ !g Tim.:: L u:~ec J I I/ .. I !
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~1e*::i ar, er "t =
G-98
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT CERT DATE: MAR 17, 1989 Page 1 of 2 NAME OF OPERATOR : R.SCHAEFEF TRANSDUCER INFORMATION MANUFACTURE: AERO TECH SERIAL NO: H24.833 C.lliSE STYLE: DIAMOND TEST ANGLE = 0 CR.YSTAL SIZE: ! I 4. FREQUENCY = : 2.25
-~-----------~-------------------------------------~---------------------------
WAVEFORM ANO POWER SPECTRUM INST.
-------------------------------------------------------------------------~----- .
TYPE: AEROTECH MODEL: UTA-: SERIAL :1::1:14 TYPE: HP WAVEFORM RECOFOER ~OOEL: Si80A SE~IAL :i:::~18A00667
----------------------------------------------------------------~--------------
rHTENUAT ION MOOE -= : ~WRM REP. R~TE = :015 EXT. & INT. PULSER Sw1tcn tc INT PULSER E~T. & INT. PULSER : = Switch to INT TRIGGER
- PLASTIC TARGET REFLECTOR INFORMATION BA~L BLOCK S. D. H.
FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED nCCE?inBLE
- '1INIMUM = 1*8 i1h: ~REOUENCY = : :.19 Mh= <1AX IMUM =
ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL :MARI< I SERIAL Ne. :01109E Ob SETTING : *,:..., r NOT ,.~iPPLICABLE___.__J~-L--.
--------------------------------------------*----------------------------------- I DATE
- NO 0/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A WEDGE AND/OR USED AS ANGLE BEAM.
CERTIFICATiON PERFORMED IN ACCORDANCE WITH XII-FE-1Z6 G-99
S.W.R.I.
- ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: HZ4833 PAGE 2 of :
CERTIFICATION DATE: MAR 17, 19~9 RNF.L 1Jt:; SCRtJ ATTC::1-I. :3. 6 dB
.10.--------------------.
\I o ~G. ~~r(t___.. .,.:. ......~_......__.._....,...__,I 1 tt,----.., .__.._-___. r '3 . ~ I
-. Hl"-----------------------'
(J l-1 :E lG0 . - - - - - - - - - - - - - - - - - - -
! V' I
. A I
----------/~1:---,-\-1----------------
~~I~----~1----/-.~:----\~.\~t,. _--""-~--~ t I 1~~~,~,~~l~---i~\~~i~---; I / I
/ I \
I I I
- J....
- I **-,*--i a"'----"=-'--*-------'----___;;~==-~
2 .;, Me13 ::ine r-r. = G-100
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT
-------------~-------------~--------------------~------------------------------
CERT DATE: MAR 2, 1989 Page 1 *=*f 2 NAME OF OPERATbR : R.SCHAEFER TRANSDUCER INFORMATION MANUFACTURE: AERO TECH SERIAL NO: H31806 C,'1SE STYLE: DI TEST ,'1NGLE = 0 CRYSTAL SIZE: FREQUENCY = : 5.0 WAVEFORM ANO POWE~ SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #::1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL ::2318A00667 UTA SETTING P1TTENUATION . ., '
'~I MOOE = :NORM REP. RATE = :015 EXT. ~ INT. PULSER = Switch to INT PULSER EXT. & INT. PULSER : ~*switch t .::; INT TR I GGER TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. 0. H.
FREQUENCY AN~ SPECTRUM ANALYSIS ACCEPTABLE MEASURED r'1CCEPTP1BLE MINIMUM : ! ~hz FREQUENCY = : !.84 Mhz MAXIMUM = S Mhz ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL :MARK I SERIAL No. :01109E Ob SETTrnG :
**- --~
NOT APPLICABLE-""""'RJ......
------------------------------------------------------------------------------- .:t I ~Z~- SIGNATUR OP1TE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A WEDGE AND/OR USED AS ANGLE BEAM.
CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-12S G-101
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: H31806 PAGE "' of 2 CERTIFICATION DATE: MAR 2, 1989
.t0...------------------....
ANALOG SCAN ATTEH 15. 2 dB 11 y I
/1 i1 1
- J
!-lillil r-,---:-----~~-----*'
\I \i \;\-------------*
1 / 1 ~ I* I~
-. L0 ' - - - - - - - - - . - - - - - ' - - - - - - - - - _ . . .
~ i fime l.usec)
POHEF :3PE*:TPUM
., I I I ! I/ " *'! i! I I I
,..! \
\ i I I I p I i I I /I ... I i i i I
I I I I II I \. I I I I I e I i/ i \ ! I I I I I I n i / I/ I *.*. I I I
!Ir--.,_ I / I l '*\ I
.. i .,_
*. I ./ ! I I ! *. I I' \ ..,
I *-* *+--' I I I i i ' --*
**, l.-.---*:I lt:l G-102
. I
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT CERT DATE: MAR 17, 1989 Page *1 of 2 NAME OF OPERATOR : R.SCHAEFER
-----------~-------------------------------------------------------------------
TRANSDUCER INFORMATION MANUFACTURE: AEROTECH SERIAL NO: J16834 C.C\SE STYLE: DIAMOND TEST ANGLE = 0 CRYSTAL SIZE: 1 / .:1. FREQUENCY = : 2.25 WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SER I AL #:: l 2 ! 4 TYPE: HP WAVEFORM RECORDER MODEL: S180A SERIAL #::2318A00667 UTA SETiLNG ATTENUATION = :20 MOOE = :NORM REP. RATE = :015 EXT. ~ INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : = Switch to INT TRIGGER TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. 0. H. FREQUENCY AND SPECTRUM ANALYS1S ACCEPTABLE ~.EASUREO ACCEPTABLE MINIMUM = : J. 8 Mh:: FREQUENCY = : 2.34 Mhz MAXIMUM = .
.;_*I Mh:
ULTRASONIC INST. -- DAC CURVE 1 YPE :SONIC MODEL :MAR~: I SERIAL ~.Jc.. :01109E Db SETTING : NOT APPLICABLE_R_)_.- -
-----------------------------------------------~-------------------------------
I SIGNA~ DATE NO IJ/f, PLOT REQUl:1ED ON TRANSDlJCERS
- -0 BE i:iiOUNTED GN A WEDGE .-~;*WiOR USEC:
*\S P.NGLE SEAM.
CERTIFiCATION PERFORMED IN ACCORDANCE WITH XII-FE-J25 G-103
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: J15834 PAGE 2 of 2 CERTIFTC,'1TICN DATE: MAR 17,
- 1989 ANALOG SCAN
.]0.------...;._-;;._ATTEN _ _ ll.?
__ dB POHEP. *~PECTPUM l~::l0 .-------,..----......-------,....---.......,
/
/
ll r \ p
/ \
\
/
1-----.. . e " r,
- Sill I ./ _ _ _\\_
,f__,.... I _ ___,..._ __
~
. I '\.
n ~I---------'-'-+-----+f....____,___ -i 1: / \.
\
I *' I !.,;"' ***.......
~
0 2 3 r*1e~iahert= G-104
-----~----------------------------------~--------------------------------------
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT CERT DATE: MAR :, 1989. Page I .::,f 2 NAME OF OPERATOR : R.SCHAEFER TRANSDUCER INFORMATION MANUFACTURE: AEROTECH SERIAL NO: M16258 CASE STYLE: DI TEST ,'1NGLE = 0 CRYSTAL. SIZE: 0.25 FREQUENCY = : 5.0
---------------~---------------------------------------------------------------
WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL ~: 1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL ~:2318A00667 urn SETTING Pi TTENUAT I ON . ,_..,
* '"Ir.\
MOOE =. : ~JORM REP. RATE = :015 EXT. & INT. PULSER Switch t.::, INT PULSER EXT. & INT. PULSER : =Switch to INT TRIGGER TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK 5. 0. H. FREQUENCY AND SPECTRUM ANALYSIS
,t~CCEPTABLE MEASURED P1CCEPTi'1BLE MINIMUM = : 4 Mhz FREQUENCY = : 4.45 Mhz MAXIMUM = 5 Mhz ULTRASONIC INST. -- bAC CURVE TYPE :SONIC MODEL : MARI< I SERIAL No. :01109E NOT APPLICABLE f: T Ob SETTING : ---~----------------------------------------------------------L __ : _________ ~--- .
OIHE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON AWEDGE AND/OR usm AS ANGLE BEAM. CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-12S G-105
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: AEROTECH SERIAL No: M16258 PAGE 2 of 2 CERTIFIC.01TION DATE: MAR 2, I 989 ANALOG SCRN RTTEN i 7 . 5 dB
. l0 ,...----------------~
-. LI!!"---------------------' Lil f ime POHE~ 3PECTFIJM I ,...
/r .. 1 I I I I I I I I ,. I I \
! I I
p
,* I I \ I I I
I I I
\
e I ! I l I /I ! I I,\ I I e n / I I I \
\
\
I t / i I I
\
I
~. .-f I l i '*
'* I i
-~.
-/. I' I ........... _ _ _
i 1 3 ~ j B 9 I la 1*1eg ane rt:= G-106
- S. W.R. I.
CERT DATE: APR 12, 1989 NAME OF OPERATOR : B.HUFFMAN ULTRASONIC.TRANSDUCER ANALYSIS REPORT TRANSDUCER INFORMATION Page 1 of 2 MANUFACTURE: SWRI SERIAL NO: 515* CASE STYLE: RECT TEST ANGLE = 0 CRYSTAL SIZE: .375 FREQUENCY = : 1 .5 WAVEFORM AND POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION = :0. MODE = :NORM REP. RATE = :015 EXT. & INT. PULSER = Switch to INT PULSER EXT. & INT. PULSER : =Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION
------------------------------------------~------------------------------------
PLASTIC BALL BLOCK S. 0. H.
---------------------------------------------------------------------------~---
FREQUENCY AND SPECTRUM ANALYSIS
---------------------------------------------------------------------------~---
ACCEPTABLE MEASURED ACCEPTABLE MINIMUM = : I .2 Mhz FREQUENCY = : I . 48 Mhz MAXIMUM = : 1.8 Mhz ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL :MARK I SERIAL No. :01109E Ob SETTING : NOT APPLICABLE *- rf?I
---------------------------------------------------------------------------~d-
;£*(~$~//_
4L '~ #~hr ___.,.....;;...D~A-T_E_ _ _ _ _ __ _.L..J,._ IW D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON AWEDGE AND/OR USED f\S ANGLE BEAM. CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-126 G-107
S.W.R.I. ULTR~SONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: SWRI SERIAL No: 515 PAGE 2 of 2 CERTIFICATION DATE: APR 12, 1989 RNRLOG SCAN ATTEH 3. 3* dB
.10.-----....;..;.'--~--;;....;..;;....;..~----------.
I/ ' Q I \ 1tuua~ I t1
-. J l ! J L - - - - ' - - - - - ' - - - - ' - - - - ' - - - - - ' ' - - - - ' - - - - - ' - - - - - '
ia 4 s a ua 12 16 T i me ( u ::> e c ) POWER SPECTRUM l00
/ \
r \
/ I 1,
I \ p e I \ r ~GI [\ I \ c e
\ I \
n \ t \I ,.. ) I' '*\,
/ \
\ \
\._,,,-.
\/ I *-~
.2 :3 Megahertz G-108
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT
-------------------------------~-----------------------------------------------
CERT DATE: FEB 20, 1989 Page I of 2 NAME OF'OPERATOR : R.SCHAEFER TRANSDUCER INFORMATION MANUFACTURE: . SWR I SERIAL NO: 1125 CASE STYLE: RO TEST ANGLE = 0 ; CRYSTAL SIZE: 0.375 FREQUENCY = : 2.25 WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-Z SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL ~:2318A00667 UTA SETTING ATTENUATION :20 MOOE = :NORMAL REP. RATE : \) 15 EXT: & INT. FULSER Switch to INT PULSER EXT. & INT. PULSER : = Switch to INT TRIGGER TARGET REFLECTOR INFORMATION 3/32 IN. 1/3 T HOLE IN PT 300 BLOCK
------------------------------------------------------------------------------~
FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTn8LE MINIMUM : I .8 Mh:: rnEOUENCY = : 2. 27 Mh:: :'1AX IMUM = ,.,,...,_ 1 ** *.:.. ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL : MARf< I SERIAL No. : 0 I I 09E Db SETTING :40
----------------------------------------~--------------------------------------
DATE
- CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-F~-i:6 G-109
S.W.R.I. ULTR8SONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: SWRI SERIAL No: 1125 PAGE .:. of 2 CERTIFICATION DATE: F~B 20, 1989 ANALOG ~3CAN
.HJ.------,,....----------------, RTTEN 23. 3 dB v
0 1 II,~,, I '..)\r, (\ "I' '\ I r . ,, 'v i1 _,,, V'J~
. j1I \
I~ J Vi 1\;1 ,. ill\ t, ~ \ v'"'\JI i1-v V"tl\fJ
'iiUlB t
a 13 e I
-.*1a.__ _ _ _ ___._ _ _ _ _ _ _ _ _ _ _ __
t:l 8 a 1ia 12 l4 lti Time ( 1.Jsec) POv*JER SPECTRUM i..:Jli! . - - - - - - - - - . - ,1---\------..---------.
/ \ .
'i I
p i '*
\ II I
e I \ rs~ i-----+--__,.../_...___\_.-----t------+ c ' t1 ,* t / \ i \
~
Q I
.......____ :.V_____ .I ___ ___
2 3
. \
~1e!3 ahe rt::
DAC CURVE 10, I I i I I i
...... I I
_'.:-~
~-
I ***r**. I *~ '* 0 .::-i A *1 *~*-.. I l c
- l. . ~k I I i ***""!:..._
! I I
CI. 5 l. Q l. 5 2.1.il HOLE DEPTH G-110
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT CERT DATE: APR 11 , I 989 Page I of 2 NAME OF OPERATOR : 3.HUFFMAN TRANSDUCER INFORMATION MANUFACTURE: SWRI SERIAL NO: 1264 CASE STYLE: RECT. TEST ANGLE = 0 CRYSTAL SIZE: i .0 FREQUENCY = .. .,.:.. . .., t:
~-
WAVEFORM ANO~POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL : : I : 1 4. TYPE: HP WAVEFORM RECORDER MODEL: 5i80A SERIAL ::Z318A00657 UTA SETTING ATTENUATION = :9 MOOE = :NORM REP. RATE : ~I 5,,_, EXT. EXT. INT. P'JLSE~ Switch to INT PIJLSE::l INT. PULSER : = Switc:i " INT TRIGGER~
- TARGET REFLEC70R INFORMATiDN PLASTIC BALL BLOCK S. D. H.
----------------------------~--------------------------------------------------
FREQUENCY ANO SPECTRUM ANALYSIS
;-;ccE=TABLE MEASURED ACCE:::TAELE ~~IN I M!J:-1 : I. 3 :"!h: i='RE(JUENCY -- .........
- ,'1AX IMUM = .. ~
{ Mh;: ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL :MARK I SERIAL No. :01109E Ob SETTING : 1~/
-------------------------------------------------~.Q.T~ePJ.J9.A.~~~--~-=~.:~
DATE NO O/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED OH A WEDGE AHO/OR USED CERTIFICATION PERFORMED IN ACCORcA~~GIJt~~:I-FE-126 G-111
0 S. W.R. I . UL TR AS ON IC TR ANSOUCER ANALYSIS RE?'JRT MANUFACTURE: SWR I SERIAL No: 1::64 PAGE : of 2 CERTIFICATION OATE: APR 11, 1989 ANALOG SCRr'>l . Fl TTEH l 2 . 3 dB
. Ji:)*.-------'----"'---'---------.
6 3 l4 lEi Time 1 usec .1 t00 ~----------------- I I 1,I "' I I I I ll I Ii \ p ~ I !I
~11~\~---~~------......;......,.~~"-------...;
I I II 'l c ~~~.---------------,....---...,......--~ I !
;v .- *l
- r. I /
i:. , / ... i\/ \ l. I.--- . ___ J' i i I .'- a*'------------------------=-
~ - 3
- - * .. A*
~1eganer"t=
G-112
- S.W.R.I.
CERT DATE: APR 1:, 1989 NAME OF OPERATOR : B.HUFFMAN ULTRASONIC TRANSDUCER ANALYSIS REPORT . TRANSDUCER INFORMATION Page . 1 of 2 MANUFACTURE: SWRI SERIAL NO: 1720 CASE STYLE: ROUND TEST ANGLE = Q) CRYSTAL SIZE: I *0 FREQUENCY = .,
. .,'-. ?S
~
WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL J:2318A00667 UTA SETTING ATTENUATION :30 MOOE = :NORM REP. RATE = :Ql15 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : =Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION 3/16 IN. 3/4 ~HOLE IN E.E.I. BLOCK
---------------------------------------------------------------------------~---
FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM 1 .8 Mhz FREQUENCY =: 2.42 Mhz MAXIMUM= : 2.7 Mhz ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL :MARK I SERIAL No. :Ql1109E Ob SETTING :51
- CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-126 DATE
------------~------------------------------------------------------------------
G-113
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: . SWRI SERIAL No: 1720 PAGE 2 of 2 CERTIFICATION DATE: APR 12, 1989 ANALOG ~3CAN ATTEN
. Hl..----....;..;..___;;~--___..;.---------., 33. 3 dB v
0 ~lil. li.llil /vv\J\J\fVV'l\f\,(IJ\f1/\) a g e
-. l l!I'---.......__ _.__ __._ _......__ _.__ __._ _.......__ __.
Iii 4. 6 a llil l2 l4 l6 Time (1.Jsec :i PO~~ER SPECTRUM l00
/\
I \I, I \ p e I \ r 513 \ c / \ e n l \ t I',
\
/
\\ /-."\_/ ,...--..._
\.,/ I v ' ..,
*- ---**~--*-
2 :3 Heg ahert z DAC CURVE
~
.J r **--~.
l .. k>~* I ~---*** '* D <: ~
~*.i.t_
~/ I Fi -
c I I i 0.0
- l. iil HOLE DEPTH i
- 2. ia 3.Wl G-114
-~----------------------------------~------------------------------------------
- * ..i.J. r, . .:. .
---------------------------------------------------------~---------------------
'~SS *..;. l.
- 5. :1UF;::;*1A~l 1*1Ai'luFAC:uRE: *::WF: I SER I AL 1'lU :
*:.~SE :;i"tLE: RE*:T TEST A1'1Gi..E I.~ : . ~'::. "':""ti=E: .i;~ROTE-:h ;100E:...: .j IM-.:. :=::=::ALJ:"l I ..
r*!PE: HP wAvE~0FM ~ECCFDE~ :c:.~1~L ~:~_:::A00~57
- liE:*iuA TIOi*J E:<:T u Ii*J i
.*10DE Fi.JL=E~
- :\lo;;:*i .::Er ::,A : c:.
Swltcn ~o I :*J T F*_ L.:E:= 1
- 0 I ~-
E:, T .:, ~ i~ T :=iJLS::::; Swl tc~ to I(**~ T ; I"' i 1.: '.:J C::.:-1 H.
=~c~ .~un ~N~L!~l:
!iE;;SuREiJ
.'
- w- *=;.~*:UE:'JC *~
uLTRASO~IC INST. -- OAC C~R0E
;*tOOE:... : :'1AR~~
NOT AF PLl CAD LE _;..;;/.J""" //~-- 1 iJb SC::T7Ii'IG iJATE
- CERTIFiCATION PERFORMED IN ACCORDANCE G-115 NO O/A PLOT REOUIREC 011 TRMISDUCERS TO BE MOUNTED .ON A WEDGE AND/OR USED AS ANGLE BEAM.
WIT~ XII-Ft:-1:5
911-~
,..... J-:' --
'-4';. ~*'=';.;
t.
--.--:**- .... _ ... --.. I
~
\ ...
' ..1; c.
I I I ___,,________ _r-..__
.'i I 111 t'I I \,I I
*-l
,'y----------..,.... ___,. ;.
f :._,..., I .,.,._.*...." :' 1. J 11 I C* I *i .,.. 111!
.I *11 \f I 1.11.i I IJ ~
I , I I
'-----------------------------------------------~~~*
d J.' :.. . u ' 11..:i~..l.-= l*.j:J :.*~. ::11::l!:ll'Jo:'
"'~..:. , : *~.r-.: ~~I::::::
l~G~3~ S!S~,~N~ ~~~n~SN~~l J!NQS~~!,0 . I . ~. "*. :.
UL TRASmJ IC TRANSDUCER P1NAL YS IS REPO*RT S.W.R.I. CERT DATE: DEC 15, 1988 P.3ge I cf 2 NAME OF OPERATOR : B.HUFFMAN
-----------------------------~-------------------------------------------------
TRANSDUCER INFORMATION MANUFACTURE: 'SWR I SERIAL NO: 1796 CASE STYLE: RECT TEST ANGLE = 0 CRYSTAL SIZE: *, 375 FREQUENCY = : 2.25 WAVEFORM AND POWER SPECTRUM INST.
-------------------------------~-----------------------------------------------
TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2Ji8A80667 UTA SETTING
~TTENUATION = :4 MOOE = :NORM REP. RATE EXT. & INT. PULSER Switch to !NT PULSER -!
EXT. & INT. PULSER : = Switch ta INT TR!GGEF
*TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. D. H.
FREQUENCY AND SPECTRUM ANALYSIS
- ~CCEPTABLE MEP1SUREO Mrf'.1:MuM . .
- t I~
\,,., Mh: FREQUENCY = : :.34 Mh=
ULTRASONIC INST. -- JAC CUPVE f"!1JDEL.. : MAR~: I Gb ~ETTirJ1: : _______ ~- ____ *_ ---------~------ _______________ __ N_QIJ\PPliCPiliLE ,6J'd___ *- --., =-. --- -
-, ***TC U*r11 i._
NO D/A PLOT REQUIRED Oi*I TR.~Nrnuc:Rs TO BE MOU!HEO ON A \'iEDGE MW/Of1 USED
- E:::;=I=-I*:,.q:ror*-i ~-ERF::~FMED I1'\J r*~,:ciJF:D~~.i~ ~~GlJ S.Efif~L'~E- i .:s G-117
s.w.~.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: s:..;R I -*SERIAL No: 1796 PAGE 2-.cf 2 CERTIFICATION DATE: DEC 15, 1988 Ar*JF\LiX:i ~3CAN ATTEN 7. 3 dB
.10.....---------------------, -.HJ'----'-----"----'----'---'-----'-----1.----'
0 12 l4 lF.; Time (1.Jsec) F'OHEF: *::;PECTRIJM j I I I I ./ \ I i 1I i i I Ii I I I I I p I I l I i I I I
~I----4--~-H/1/I i
II i
*- l I I
_,1 I I 7"5G ' _ _+11-+----...__ _
- i. I I
~ ~11;*~~:---..,---~,-.--__,\,--+------------il
' ~ I I I n ~I_.,*----;----,-/--+_ ____.,.\- ' - - - - - ' - - - - - 1 1
~- II p ..
\
\
I
. \I G-118
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT CERT DATE: FEB 16, 1989 . Page I of 2 NAME OF OPERATOR : R.SCHAEFER TRANSDUCER INFORMATION MANUFACTURE: SWRI SERIAL NO: !803 CASE STYLE: RECT TEST ANGLE i= 0 CRYSTAL SIZE: .5 FREQUENCY = : 2.25 WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE:.HP WAVEFORM RECORDER MODEL: 5180A . SERIAL #:2318A00667 UTA SETTING ATT_ENUATION :J2 MOOE = :NORMAL REP. RATE EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : = Switch to INT TRIGGER TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. 0. H. FREQUENCY ANO SPECTRUM ANALYSIS
-----------------------------------------------------------------------~-------
ACCEPTABLE MEASURED ACCEPTABLE
~INIMUM = : 1 .8 Mhz FREQUENCY = : 2.50 Mhz MAXIMUM= : 2.7 Mhz ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL :MARK I SERIAL No. :01109E Ob SETTING :
NOT APPLICABLE ---el/ DATE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A WEDGE AND/OR USED AS ANGLE BEAM. CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-126 G-119
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: SWRI SERIAL No: 1803 PAGE'2 of 2 CERTIFICATION DATE: FEB 18, 1989 ANALOG SCAN RTTEN 12. 2 dB
.101.-----------'-""""'-_..;.;.;;~-------.
v 0 ~!il.lillil-.............__...._.....__~} a g e
-. JEI'--.....__.......__ __.._ _......__.....__ _.__ __.._ ___.
Iii 4 s B 11il 12 l4 l5 Time Cusec) POWER SPECTRUM l00
\ / \
I
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p
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121 v '-./
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Iii 2 3 4 s Megahertz G-120
- S.W.R.I.
CERT DATE: OCT 21 , I 988 NAME OF OPERATOR : 8.HUFFMAN ULTRASONIC TRANSDUCER 6NALYSIS REPORT TRANSDUCER INFORMATION Page I of 2 1
~ANUFACTURE: SWRI SERIAL NO: 1807 CASE STYLE: RECT TEST ANGLE = 0 CRYSTAL SIZE: .50 FREQUENCY = : 2.25 --------------------------~---------------------------------------------------- ------- WAVEFORM AND POWER SPECTRUM INST. -------
TYPE: AEROTECH MODEL: UTA-2 SERIAL ; : I 2 I 4 . TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION = :9 MODE = :NORM REP. RATE = :015 EXT. & INi. PULSER Switch to INT PULSER EXT. & INT. PULSER : = Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. D. H.
FREQUENCY AND SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM : l .a Mhz FREQUENCY = : :.:7 Mhz MAXIMUM = .:. * ' f1 h:: ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL : MARr: I SERIAL r*Jo. :01109E Ob SETTING : NOT f\PPL!CJ\GLE /# DATE NO DIA PLOT REQUIRED C*N TRMISDUCERS TO BE f*.'10UIJTED Oi~ ;:, *.*:EDGE i~ND/OR USED r~s Af~GLE BEAM. CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-126 G-121
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT f4ANUFACTURE: :wR I 3EP IAL No: '\ 307 PAGE .., of ;:: CERTIFICATim~ DATE: OCT 21 *. 1988
- A~,IALr)(; ::;CAN
-. ]El'-----------......__ _ _ _.___ _ _ _ ____
Gl a. !6 Time t *.1.:;er: ,.1 POHEP '3PE*:TPUM l00 . - - - - - - - - - - - - - - - - - - - - - - - . I / \ p .
./
e ...
/ II cr ::~ r------.r---.----;.----'r----i------;-------i e
/
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~
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'----------'-----'------'===:==i - .3 . ... 5 1'1e *~ah er'!'.-=
G-122
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS RE?ORT
- CERT DATE: FEB 16, 1989 NAME OF OPERATOR : 6.CAYWOOO MANUFACTURE: SWRI TRANSDUCER INFORMATION SERIAL NO: 1845 Page ! of Z CASE STYLE: RO TEST ANGLE = 0 CRYSTAL SIZE: 1 .0 FRE*JUENCY =
WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-: :: : 1:' J. TYPE: HP WAVEFORM RECORDER MODEL: Si 8*'lA c-:
... c: .. r~.Al*- ::t:Z3iSA00667 UTA :ETTHJG AiTENUA i I (J~~ : :S MCO~ = : t~GRM ~E? . .~.~7C:
EXT. & WI. PULSE:: Sw1 :c:i tc ::JT P 1JL3:::.= EXT. ~ I~T. PULSER : = Sw1:c~ ~c ~NT T;IGGER TARGET RE::L:::CTGF. !NFGRMATIGN
- 3/16 IN. 3/4 THOLE IN E.E.I. 2LCCK FREQUENCY ANO SPECTRUM ;NAL~srs
~1=CE::iA5LE MEASURED
- 1
- 3 Mhz ~=E:UENCY = : :.52 ~h:
ULTRASONIC :NST. -- OAC :uRVE
"!fC::'. :SONIC MODEL :MAR!< I SERIAL No. :;]11vSE Ob SET7ING :53 SIGNATURE DATE
- CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-126 G-123
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: SWRI SERIAL No: 1845 PAGE Z of 2 CERTIFICATION DATE: FEB 16, 1989 v
.10.-------------------,
ANALOG SCAN ATTEN 22. 2- dE !*-* ~VV"~ g e
-. Ii,."--""'"--------------------""
la 2 4 6 8 Lia l2 L4 lS' Time (1Jsec J POY.iE? S?~CTF.!JM l011! . - I I / \ I I I I I I **, I I I p I II \I 11 \I e I I/ *~ c r Sl3 I - A ~ e n I/ VI I\ t
- I .I I\
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- 2 '.3 s Megahert.:::
DAC CURVE
~
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-- l.la 2.0 3.ia 4. la HOLE DEPTH G-124
- S.W.R.I.
CERT DATE: APR 12, 1989 NAME OF OPERATOR : 8.HUFFMAN ULTRASONIC TRANSDUCER ANALYSIS REPORT TRANSDUCER INFORMATION Page 1 of 2 MANUFACTURE: SWRI SERIAL NO: 1848 CASE STYLE: ROUND TEST ANGLE = 0 CRYSTAL SIZE: 1 .0 FREQUENCY = : 2.25 WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MOGEL: UTA-2 SER I AL #: I::: 14 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION :28 MOOE = :NORM REP. RATE : el 15 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : =Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION 3/16 IN. 3/4 THOLE IN E.E.I. BLOCK FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM 1. 8 Mhz FREQUENCY 2.50 Mhz MAXIMUM = : :.7 Mhz ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL :MARK I SERIAL No. :01109E Ob SETTING :52
- CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-125 G-125
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT' MANUFACTURE: SWR'I SERIAL No: 1848. PAGE 2 of 2 CERrIFICATION DATE: APR 12, 1989 RNALi)G ~:;CR1'l
.10.--~-~-~~~----~------,
ATTEN 3 1 . 3 cl B I./ 1 !ra. a lillil ':\/\/vW'A.) g
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c ! I I i
-J 0.lil l.lil 2.lil 4. Iii HOLE DEPTH G-126
- S.W.R.I.
NAME OF OPERATOR : 8.HUFFMAN ULTRASONIC TRANSDUCER ANALYSIS REPORT
----------------------------------------------------------------------T--------
CERT DATE: APR 11 , 1989 TRANSDUCER INFORMATION Page i of 2 MANUFACTURE: SWRI SERIAL NO: . 2547 CASE STYLE: RECT. TEST ANGLE = 0 CRYSTAL SIZE: .375 FREQUENCY = : 1 .5 WAVEFORM ANO POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION = :0 MODE = :NORM REP. RATE = :015 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : ~Switch to INT TRIGGER TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. ~. H. FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM : 1. 2 Mh: FREQUENCY = : 1. 56 Mhz MAXIMUM = : 1 .8 Mhz ULTRASONIC INST. -- DAC CURVE
-~----------------------------------------------------------------------------~
TYPE :SONIC MODEL :MARK I SERIAL No. :01109E
. ::_::::~::_~ _______ .N_QI_8f.f.~L~~~~--~-~~~-="-
sIGNAURE DATE
*~o DiA r-1..Li1 Kt.\JuiKtL,. .11* ; *..-11~::,*n;:..;.;.~:~
TO BE MOUNTED OH AWEDGE. AND/OR USED AS AMGl.E BEAM. CERTIFICATION PERFORMED IN ACCORDA~~~-WITH XII-FE-126 G-127
S. W. ~~ I
- ULTRASONIC TRANSDUCER ANAL.YS IS REPORT MANUFACTURE: SWRI SERIAL No: 2547 PAGE 2 of 2 CERTIFICATION DATE: APR 11 , 1 989 Al'lRLOG S~RN
. RTTEN 3.3 dB .J0.-------~-~--~--~---~
I . i**"r-----------~* rj'v~ 1 ~ 111 I
-. JP.l'--...__ _ _ _..___...__ __.__ __...___ _.___ _..
i;i 2 6 Ila 12 l4 15 Time (usec) Pm~EP SPECTRUM l00
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2
~
5 Hegahert::: G-128
-----------------~-------------------------------------------------------------
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT
--------------------------------------~----------------------------------------
CERT DATE:.APR 12, 1989 Page l of 2 NAME OF OPERATOR : 8.HUFFMAN TRANSDUCER INFORMATION I MANUFACTURE: SWRI SERIA!l. NO: 2676 CASE STYLE: RECT. TEST ANGLE = e CRYSTAL SIZE: .375 FREQUENCY = : 1 .5 WAVEFORM AND POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #:1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION* = :3 MODE =:NORM REP. RATE = :*015 EXT. & INT. PULSER Switch to INT PULSER EXT*. & INT. PULSER : = Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION
*PLASTIC BALL BLOCK S. D. H. ------=-- FREQUENCY ANO SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM = : I. 2 Mhz FREQUENCY = : I. 48 Mhz MAXIMUM = : I .8 Mhz ----------------------------------------------------------------------~--------
ULTRASONIC INST. -- DAC CURVE TYPE :SONIC MODEL :MARK I Ob SETTING :
-~-----------------------------------------------------------------------------
DATE NO D/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED OH AMDGE AND/OR USED AS ANGLE BEAM. CERTIFICATION PERFORMED IN ACCORDANCE WITH XII-FE-126 G-129
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: SWRI SERIAL No: 2676 PAGE 2 of 2 CERTJFICATION DATE: APR 12, 1989 ANALOG :3CAN RTTEN 6. 3 dB
.10...-----""--.;._----..;;.:_--------.
v 0 10.00 t' ' ' t .a
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FREQUENCY SPECTRUM AND R.F. WAVEFORM ANALYSIS
- MANUFACTURER CASE S'TYLE
~UJ /(_I g(JtLnc/
SEARCH UNIT SERIAL N0._."'"'";)..""'-'?'-"5";..._;.7 TEST ANGLE---=-_d_ _ _ _ _ _ _ __ CRYSTAL SIZE * :J..:i-d" FREQUENCY 7,5 JY1 Hz. ULTRASONIC TRANSDUCER ANALYZER SETIJNGS ATTENUATION i.,7 GATE WIDTH l/.3' GAIN TRIM _ _-"0=26~--- DAMPING '555 MODE t/a~m EXT. PULSER DOWN GATE DELAY &97 REP. RATE 115 EXT. TRIGGER DOWN SPECTRUM ANALYZER
- RoF. SECTION INPUT ATTENUATION 10 SCAN WIDTH _ _ _ _ 1 _MH_z_ _ _ _ _ __
CENTER FREQUENCY 5. 0 TUNING STABILIZER_ _O.._F_F_*- - - - - - - BAND WIDTH 30 KHz RANGE 0-11 SPECTRUM ANALYZER* l.F. SECTION LOG REF. LEVEL _ _._...;;...,=~"------MV/DV DISPLAY ADJUST____o________ VIDEO FILTER . OFF TRIGGER _ _ _ _ _A_U_T_O_M_AT_l_C_ _ _ __ SCAN TIME/DIV. 2 MILLI SEC. TARGET REFLECTOR SwRI SPEC PHOTOGRAPH DATA
- 0 3/32 INCH, 1/3 THOLE IN PT 300 BLOCK Dr 3/16 INCH, 3/4 THOLE IN E.E.I.
BLOCK MINIMUM MAXIMUM 6
- t2 (Y)tl;;
9, cl Pl fl c MEASURED FREQUENCY 7. 4 CERTIFICATION BY MHz/DIV _ _/ _ _ _ _ __ USEC/CM _ _ VOLTS/CM _ _
, 1_A1_S_ _ __
so_M_V 0 PLASTIC BALL BLOCK S.D.H.
~~ ~ /9.?~
0 OTHER _ _ _ _ _ __ SIGNATURE DATE / c.yJ?
- SwRI FORM FE-67-0 G-131
SEARCH UNIT BEAM PROFILE IDISTANCE VS AMPLITUDE - RANGE Bl
~*
SEARCH UNIT TEST EQUIPMENT TEST BLOCK BRANO 8.(1/. B_I SERIAL NO.
;). 757 CARBON STEEL WITH
()" Son{.c CASE STYLE R"ll"d ANGLE TYPE l/B INCH DIAMETER CRYSTAL SIZE * ~S<!l y FREQ. 7-5~Hl MODEL IYJ}( I SIDE DRILLED HOLE GAIN SI dB TEStEO BY: DATE SERIAL NO. 0 I J tJf..E 100
- 8. II!/r ;:-M "11'/ lcJ .4PI< Jr; 9)
90 ,_._ ..._ 80 '\ s "\ I
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G 70 N A L 60 '
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\
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L \ I ' T u 40 ~ D E .... 30 ' 20 - - 10 0 1/4 1/2 3/4 1 1-1/4 1-1/2 1-3/4 2 HOLE DEPTH IN STEEL SwAI Form FE-68-0
---------------------------------------------~--------------------------~------
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT CERT DATE: APR 1 1 , 1989 Page 1 of 2 NAME OF OPERATOR : 8.HUFFMAN . . TRANSDUCER INFORMATION MANUFACTURE: SWRI SERIAL NO: 2924 CASE STYLE: RECT. TEST ANGLE = 0 CRYSTAL SIZE: .375 FREQUENCY = : 1 .5 WAVEFORM AND POWER SPECTRUK INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #: 12 14 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00667 UTA SETTING ATTENUATION :14 MOOE = :NORM REP. RATE = :015 EXT. & INT. PULSER Switch to INT PULSER EXT. & INT. PULSER : =Switch to INT TRIGGER TARGET REFLECTOR INF*ORMATION PLASTIC BALL BLOCK S. D. H.
-----------~-------------------------------------------------------------------
FREQUENCY AND SPECTRUM ANALYSIS ACCEPTABLE MEASURED ACCEPTABLE MINIMUM : 1 .2 Mh:: FREQUENCY = : 1 .64 Mh:: MAXIMUM = : 1.3 :'!~:: ULTRASONIC INST. -- OAC CURVE TYPE :SONIC MODEL : MAR~: I SERIAL No. :01109E Db SETTING :
*i' *~'~*v !" *Atil ~: ___ tJ7/f' * -------------------------------------------------=--~:,.: __ ::....:...~ ___'-:_*::_ ___________ *..:..-=~-
1/ 48/fi'f DATE
,, ...... -~.. ..;: .. **""'~!.. .JI' . ;\~f1...:ui.JL;i::.K~
10 BE MOUNTl:.D ON AWEDGE AND/OR USED CERTIFICATION PERFORMED IN ACCORiMrfdlG~~l.II~FE-!25 G-133
S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: SWRI SERIAL No: 2924 PAGE 2 of 2 CERTif;ICATION OAT~: APR 11 , 1989 R~*lRLOG .SCRf'.l
.10.------ RTTEN
------_ 17. __ 3 :dB
~
\/
0 I\ t 1ta.lillil 1:---~--~-}'1 '\/\,r----------- a 1, g I e I Iii 2 4 6 8 10 12 l4 16 Time (1_isec) PO~~ER ~3PECTRUM l 00 .------.---,,,...---,-------,.-----,-------,
/ \
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lil 2 3 5 Hes_1ahertz G-134
S.W.R.I. CERT DATE: NOV 9, .1988 NAME OF OPERATOR : 8.HUFFMAN ULTRASONIC TRANSDUCER ANALYSIS REPORT TRANSDUCER INFORMATION Page i of 2 MANUFACTURE: SWRI SERIAL NO: 3223 CASE STYLE: ROUND TEST ANGLE = Ql CRYSTAL SIZE: .250 FREQUENCY = : 2.25 WAVEFORM AND POWER SPECTRUM INST. TYPE: AEROTECH MODEL: UTA-2 SERIAL #: 12 14 TYPE: HP ~AVEFORM RECORDER MOD5L: 5180A SERIAL #:2318A00667 UTA SETTHIG ATTEi*ll_!AT Im~ . 7
* ..J MODE = :NORM REP. RATE : '.) 1 t; E:<T. & HJT. PULSER St.1 t tch to INT PUL::ER EXT. E, INT. PULSER : = S1.1.1i tch to INT TRIGGER
- TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. D. H.
FREQUENCY ANO SPECTRUM ANALYSIS MEASURED
- l. 2 FREQUENCY= : 2.27 Mh:
ULTRASONIC INST. -- DAG CURVE MODEL : MAR~: I SERIAL tfo. :01 iOSE Ob SETTHIG : NOT APPLICABLE >f// DATE NOD/A PLOT REQUIRED ON TRANSDUCERS TO BE MOUNTED ON A WEDGE AND/OR USED r-i1 *.*
~~s. A@LE SEAM.
t . t_!, 1...1ri1~t_,t_: ~Ji. 1 H '\ T i L -!- t: - 1 _ :"'") G-135
S.W.R.I. ULTRASONIG TRANSDUCER ANALYSIS REPORT MANUFACTURE: SWRI SERIAL No: 3223 CERTIFICATION DATE: NOV 9, 1988 R~*JALOG RTTEl*I
.10.--~~~~~~~~~~~~~~~~~----,
~3CRr"I
- 6. 3 dB PAGE 2 of 2
*POHEF' '3PECTPUM
/
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't
....___,......__--+\.--'!'---------,
~:~~----I~-/-----~---\~\~-. ~---!-.~~
----ii i i / I . I I 1.--
r1e~~;aher-t= G-136
- S.W.F:.I.
CERT DATE: JAN !3, 1989 NAME OF OPERATOR : 8.HUFFMAN ULTRASONIC TRANSDUCER ANAL Y.S IS REPORT TRANSDUCER INFORMATION Page 1 s*f 2 MANUFACTURE: SI.JR( SERIAL NO: 3224
- CASE STYLE: ROUND TEST ANGLE = 0 CRYSTAL SIZE: .25 FREQUENCY= : 2.25
' WAVEFORM AND POWER SPECTRUM INST.
TYPE: AERO TECH MODEL: UTA-2 SERIAL #: 1214 TYPE: HP WAVEFORM RECORDER MODEL: 5180A SERIAL #:2318A00657 UTA SETTH113 A'T9.JUAT I ON = :0 r*lOOE = : NORM REP. RATE = :J1E EXT. & INT. PULSER Switch to INT p1r1 ~;::-;; EXT. & INT. PULSER : = Switch to INT TRIGGER
- TARGET REFLECTOR INFORMATION PLASTIC BALL BLOCK S. D. H.
FREQUENCY ANO SPECTRUM ANALYSIS
~::* 1 :EPTA8LE MEr%1JREO ACCEf= Tr,5*L~
- 1 I r.,j I Mur1 : 1. S Mhz FREQUENCY= : 2.!9 Mh: Mrl.i I f*1ur--~ -= .! ~- -*
ULTRASONIC IN~T. -- OAC CURVE M()OEL : MAR~: I Ob SETTiNG : 7 , '
. 1*-~0T PiPPL!Cl~DLE. /3 Z7
- G-137*
_.S.W.R.I. ULTRASONIC TRANSDUCER ANALYSIS REPORT MANUFACTURE: Sl.JRI SERIAL No: 3224 PAGE 2 or 2 CERTIFICATION DATE: JAN 13, 1989 RrlRLOG SCRr*.j RTTEN 3. 3 dB
.10.----'-------------------,
-. l ~,____ .........._ __.__ __.___ __.__ ___,_ __,__ __.._ ___,
~ 12 l4 Time (u:secl l/ \
~ ' I I
/ I
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ii ' I -.. ._ I ...__*--t----- 8 ~----'------------------'--------' :;.
*:* s Me*~ at-i er t =
G-138
- 1 APPENDIXH CUSTOMER NOTIFICATION FORMS
- APPENDIXH CUSTOMER NOTIFICATION FORMS Table of Contents CNF No. Area Indication(s) Disposition SAMl-1 4-SJ-2120-33 9/16" linear extending Accepted. Reexamination after into base metal surface preparation revealed no recordable indications.
SAMl-2 1-RPV-6046-A 3 Code-allowable Accepted "as is" in accor-Head-to-Flange dance with IWB-3510 of 83/S83 Section XI ASME B&PV
- H-i
Southwest Research Institute
- CUSTOMER NOTIFICATION Part I- SwRI Type of FORM Findings Examination fr;(.
I SwR! NOT Method 0 UT J"'\PT Procedure/Rev. Examination 0 PSI *JlQ ISI: OMT .ORT 0ET 0VT Za::>-1/;
,,£,. . U Comments 4-SJ- Z/20 - 3o Examination Reference :
Signature at SwRI Representative Date
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Signature of Customer Representative Date Comments Reexamination Signature CNF Closed Date SwRI FORM NOTR-CNF-1,R .. -I
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Southwest *Research Institute CUSTOMER NOTIFICATION FORM Part I - Sw RI Findings Project N!2. : / T1pe of Examlna!lon NOT Method f,i{UT OPT ~~~~ure/Rev. 0 PSI iJ IS:t OMT .ORT 0ET OVT ~-~ Comments /-~Pv-C.o4C. -/-?* /Tf.{:'/.10 ~ ,C~,,4,,(.4_ I) I
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Sw. R. I. EXAMINATION
SUMMARY
RECORD PROJECT No.: SITE: SHEET No.: 17-2735 Salem Generating Station, Unit 1 ~OC) EXAMINATION AREA I SYSTEM /COMPONENT) (LINE/ SUBASSEMBLY) I IDENTIFICATION) l
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FORM NO. SWJll 17-30 (REV 1(}'9-791
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i __ )* Sw. R. I MAGNETIC PARTICLE EXAMINATION RECORD r I I PROJECT No.: SITE: _Salem Generating DATE: (DAY- MO -YR) TIME: (24 HR. CLOCK) SHEET No.: 17-2735 Station, Unit 1 /~ *-'tAA..'/ -ffi. ~~:~ i~A~ETDE:D:~g~ *:i.~~GQi9 EXAMINATION AREA: LINE/ SUBASSEMBLY: IDENTIFICATION: Lo LOCATION: W~ LOCATION: (SYSTE~P/JONENT > c_~u/21!' l-l1:?f b l-i!PJ/ ~ o ~ r;. A L/c-.i:Sc..-c 0 t. '<Jett* (r. EX~INER~ ,/I SNT LEVEL PROCEDURE SURFACE FINISH: WELD TYPE (-FLOW-+-) MAGNETIZATION /{2_. ~ i l *~. '1JV~ \LI r.f? ~.,. b(U)0~~ fl~!/-/) - fl,<f*V6r:.:- SPACING:._<SY'~ 11
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