IR 05000254/1982019
| ML20028D079 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/23/1982 |
| From: | Danielson D, Ward K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20028D075 | List: |
| References | |
| 50-254-82-19, 50-265-82-22, IEB-81-01, IEB-81-1, IEB-82-03, IEB-82-3, NUDOCS 8301170045 | |
| Download: ML20028D079 (15) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Reports No. 50-254/82-19(DETP); 50-265/82-22(DETP)
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Docket Nos. 50-254; 50-265 Licenses No. DPR-29; DPR-30 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Quad-Cities Nuclear Power Station, Units 1 and 2 Inspection At: Quad-Cities Site, Cordova, IL Inspection Conducted: September 22, 23, October 7, 8, 19, 20, 21, 30, November 8 and December 8, 1982 479Ar JL Inspector:
. D. Ward
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Accompanied By:
D. H. Danielson (September 22 and 23, 1982)
Mbe Approved By:
H. Danielson, Chief
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Materials and Processes Section Inspection Summary Inspection on September 22, 23, October 7, 8, 19, 20, 21, 30, November 8 and December 8, 1982 (Reports No. 50-254/82-19(DETP); 50-265/82-22(DETP))
Areas Inspected: Replacement, repair, welding and nondestructive examinations (NDE) of the reactor water cleanup (RWCU) system piping; QA/QC program, imple-menting procedures, work activities, and nondestructive examinations (NDE) data
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of inservice inspection (ISI); core spray piping and torus modification; clad removal in feedwater nozzles; IE Bulletin No. 81-01 and No. 82-03 activities.
The inspection involved a total of 75 inspector-hours by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
l EKND1170045 821220 PDR ADOCK 05000254
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DETAILS Persons Contacted Commonwealth Edison Company (CECO)
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- L.
Grever, Assistant Superintendent, Admin.
- C. Smith, QC Supervisor
- D. Gibson, QA Supervisor
- J. Ford, QC Inspector N. Kalivianakis, Station Superintendent R. Bax, Assistant Superintendent of Maintenance D. Huizenga, QC Inspector H. DO, ISI Coordinator W. Witt, Level III, NDE B. Wilson, Level II, NDE T. Haaker, Level II, NDE General Electric M. McCrum, QC Supervisor United States Testing Company, Inc. (USTCo)
J. Dreibelbis, Level II, NDE J. Foster, Level III, NDE K. Shaw, Level II, NDE M. Hendryx, Level I, NDE Hartford Steam Boiler Inspection and Insurance Company F. Roose, ANII The inspector also contacted and interviewed other licensee and contractor employees.
- Denotes those present at the final exit interview.
Persons Attending Validation Meeting, Battelle Columbus Laboratories2 Columbus, Ohio, October 7, 1982 G. Dali, EPRI, Palo Alto, CA M. Behravesh, EPRI, Charlotte, NC G. Selby, Battelle, NW Labs.
K. Cook, Oak Ridge, National Labs.
J. Gieske, Sandia National Labs., Albuquerque, New Mexico J. Cook, EG&G Idaho, Inc.
W. Hazelton, U.S. NRC, Washington, DC M. Hum, U.S. NRC, Washington, DC W. Collins, U.S. NRC, Washington, DC R. McBrearty, U.S. NRC, Region I
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J. Coley, U.S. NRC, Region II W. Crowley, U.S. NRC, Region II W. Ward, U.S. NRC, Region III Persons Present for Ultrasonic Examination (UT) Demonstration October 8, 1982 l
W. Witt, Level III NDE, Commonwealth Edison Company (CECO)
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B. Wilson, Level II NDE, Commonwealth Edison Company (CECO)
Licensee Action on IE Bullet!gis 1.
NRC memorandum dated January 27, 1981, IE Bulletin No. 81-01 and Revision 1, dated April 5,1981, titled, " Surveillance of Mechanical Snubbers," Units 1 and 2.
(Closed) IE Bulletin No. 81-01 and Revision 1: The inspector reviewed the final response dated June 15, 1982, and the results of the inspec-tion performed for Unit 2.
Testing and inspection will be performed in accordance with the new technical specification on Unit 1.
The inspector has no questions at this time.
2.
NRC memorandum dated October 14, 1982, IE Bulletin No. 82-03, titled, Stress Corrosion Cracking in Thick - Wall Large Diameter, Stainless Steel Recirculation System Piping at BWR Plants.
(0 pen) IE Bulletin No. 82-03: The inspector was involved in the following activities. This item remains open pending further review by the NRC.
a.
General (1) A meeting was held with EPRI and representatives from several NRC Regional Offices, I&E Headquarters, NRR and NRC consultants to discuss the validation of CECO's UT procedure to be performed on recirculation system pipe weld samples from Nine Mile Point (NMP) at Battelle Memorial Institute, Columbus, Ohio.
i EPRI explained that their position was not to monitor, officially witness, or report the results of the UT.
EPRI was only providing characterized pipe specimens removed from NMP and facilities to the utilities to perform the UT qualification or validation test for NRC representatives.
Quad-Cities (Commonwealth Edison) arrived at Battelle on
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l October 8, 1982.
It was agreed that Regional Offices II and l
III would witness the examinations and that Region III would present the following instructions to the ultrasonic examina-tions performed by CECO.
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Use their procedure and perform the UT as if they were
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production welds.
The lowest Level UT person performs the examinations.
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All five weld samples would be examined. They would
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remain stationary and the Ur instruments would be moved from one weld to another.
The NRC would have a copy of their procedure.
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Plot out all indications.
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Submit all new data, and Region III also requested
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that a grid form with crack (c) no crack (n) designations be completed prior to leaving Battelle. This form was used as a quick reference since a grid form was also used by Battelle in plotting out the cracks.
The NRC would give the licensee the results (acceptable /
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unacceptable) as soon as the final data was submitted.
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Five of the NMP pipe welds were decontaminated to a level under 20 mrem / hour contact. EPRI personnel characterized the ultra-sonic response amplitude of the cracks by varying the following parameters:
the model of the UT instrument, transducer type (dual and single element), transducer size, frequency and calibration reflector (notches and side-drilled holes).
Liquid penetrant examinations were performed to locate I.D. surface cracks. The baseline data was made available to the Regional representatives.
The UT was conducted in a large hot cell building with sufficient access for inspection personnel and observers.
The pipe segments were mounted on wooden fixtures with the I.D. surface masked.
CECO performed the UT using CECO procedure, " Ultrasonic Inspection of Pipe Welds," NDT-C-2, Revision 12, dated December 1980. This procedure was in accordance with ASME Section V and XI, 1974 Edition, Summer 1975 Addenda.
The five weld samples were equivalent to approximately one l
complete weld 28" diameter, 1.2" thick, made of rolled welded
stainless steel plate.
It took approximately six hours for l
CECO to calibrate and pectorm the UT on the five samples.
l Approximately three hours later, Ceco completed and submitted
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the raw data to Region III stating that it was the final results l
and asked if they (the licensee) could have the NRC final results l
(acceptable / unacceptable) of their performance.
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The NRC, their consultants, etc. compared CECO results against i
the Battelle results determining that CECO had found the l
majority of the cracks. Other indications were also called cracks. Region III informed Ceco of the results and that the CECO UT and procedure were acceptable based on the decision of the NRC, and their consultants. There were discussions between the NRC and CECO in regards to being more specific in their procedures. CECO stated that an addenda, would be attached I
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to their present procedure revising several paragraphs in the near future. There were NRC concerns, such as, if other UT personnel in their organizations would interpret the same UT presentation on their instruments to be cracks. CECO stated that their UT personnel would interpret the same presentations to be cracks.
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(2) CECO obtained a 28" pipe weld from Nine Mile Point for the purpose of training UT personnel. CECO's Level III and Level II individuals that were at Battelle and another CECO Level II individual performed UT on the weld and located several cracks.
After the UT was performed a liquid penetrant examination (PT)
was performed on the inside diameter (ID), and all cracks that were identified to be cracked by UT were confirmed to be cracks by PT.
The same type of test was given to Level III, Level II and Level I personnel from U.S. Testing as was given to CECO in Battelle performing to a CECO UT procedure. The Level III and Level II who performed the UT at Battelle from i
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CECO supervised the UT performed by U.S. Testing. The inspector, ANII and site CECO QC inspectors observed the UT by U.S. Testing. The U.S. Testing personnel passed the test and then the U.S. Testing Level III gave the same test to several Level II U.S. Testing individuals.
U.S. Testing and CECO personnel ultrasonically examined approximately 10% of the following welds and found no unacceptable indications.
System Total Welds Total Examined 28" dia. Recir. Suction Discharge
3 22" dia. Recir. Ring Header
2 (12 cir. pipe welds and 8 saddle to pipe welds)
12" dia. Recir. Riser
4 16" dia. RHR
6 20" dia. RHR
3 b.
Review of Personnel Material and Equipment Certifications, Data Reports and Audits The inspector reviewed documents relative to the following items:
Ultrasonic instruments, calibration blocks, transducers and UT
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couplant certifications.
Several NDE personnel certifications in accordance with
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SNT-TC-1A, 1975 Edition.
Data reports and determined that they demonstrated that the QA/QC
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requirements were met.
CECO QA Audit Reports of ISI/ Recirculation System Piping
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activities, Nos. QAM 4-82-52, QAM 4-82-54, QAM 4-82-67.
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Functional or Program Areas Inspected 1.
Torus Modification a
a.
General References:
Region III Report Nos. 50-254/79-19; 50-265/79-16 (Torus
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Modification)
Region III Report No. 50-254/79-29; 50-265/79-26 (Torus
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Modification)
Region III Report Nos. 50-254/80-03; 50-265/80-05 (Torus
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Modification)
Region III Report No. 50-254/80-15; 50-265/80-18 (Torus
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Modification)
Region III Report No. 50-254/80-23; 50-265/80-25 (Torus
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Modification)
b.
Procedure Review
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The inspector reviewed the following procedures:
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USTCo, NDE Personnel Certifications, UST-TC-1A, Revision 6
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(SNT-TC-1A 1975/1980 Edition)
CECO, Ultrasonic Inspection of Pipe Welds, NDT-C-2, Revision 12.
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CECO, Ultrasonic Inspection of External Support Attachment Weld
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Areas of Piping, NDT-C-4, Revision 9.
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CECO, Ultrasonic Inspection of the Inner Radius of the Nozzle
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to Vessel Junction, NDT-C-10 Revision 6.
CECO, Ultrasonic Inspection of Ferritic Safe-End to Nozzle
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Welds, NDT-C-15, Revision 3.
CECO, Ultrasonic Inspection of Dissimilar Metal Welds, NDT-C-16,
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Revision 4.
CECO, Non Aqueous Red Dye Liquid Penetrate Examinations, NDT-D-2,
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Revision 3.
CECO, Visual Examination of Nuclear Reactor Coolant System
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Components, NDT-V-1, Revision 4.
M, Procedure Specification for Shielded Metal Arc Welding of
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Carbon Steel Materials According to ASME Section IX, CS-1, Revision 10.
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M, Procedure Specification for Shield Arc Welding (SMAW) of
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Carbon Steel (ASME P-1) Material According to ASME Section IX,.
CS-11, Revision 6.
M, Procedure Specification for Shield Arc Welding (SMAW) of l
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j Carbon Steel (ASME P-1, Group 2) Material According to ASME
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Section IX, CS-16, Revision 5.
M, Procedure Specification for Shield Arc Welding (SMAW) of
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Carbon Steel (ASME P-1) Materials According to ASME Section IX, CS-17, Revision 3.
M, Procedure Specification for Shield Metal Arc Welding (SMAW)
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of Carbon Steel (ASME P-1, Group 2) Materials According to ASME Section IX, CS-18, Revision 2.
M, Procedure Specification for Gas Tungsten Arc Welding (GTAW)
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Shield Metal Arc Welding (SMAW) of Carbon Steel (ASME Gr. P-1)
Materials According to ASME Section IX, CS-20, Revision 4.
M, Procedure Specification for Shield Metal Arc Welding (SMAW)
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of Carbon Steel (ASME Gr P-1) to Stainless Steel (ASME Gr. P-8)
Materials According to ASME Section IX, DM-7, Revision 2.
M, Procedure Specification for Gas Tungsten Arc Welding (GTAW)
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Shield Metal Arc Welding (SMAW) of Carbon Steel (ASME Gr. P-1)
to Stainless Steel (ASME Gr P-8) Materials According to ASME Section IX, DM-22, Revision 1.
M, Visual Inspection of Welds to AW3 D1.1 Structural Welding
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Code, NDE-VE-3, Revision 8.
M, General Procedure for Welding of Carbon Steel Piping,
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Pressure Vessels and Structural Materials, PC-901, Revision 2.
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M, Material Control - Receiving of Materials, QSMC-1, Revision 3.
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M, Storage of Materials and Items, QSMC-5, Revision 2.
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M, Welding Material Control, QSPC-2, Revision 4.
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M, Erection of Supports - Restraints and Final Installation
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l Verification, QSPC-16, Revision 2.
M, Use of Weld Data Report for Piping Subassemblies for Sizes
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2-l" 0.D. and Larger, QSPC-17, Revision 1.
M, Utilization of Mechanical Revision Directive, OSPC-23,
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Revision 3.
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M, General Repair Procedure, QSPC-30A, Revision 1.
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M, Calibration Check of Torque Wrenches, QSPC-31C, Revision 1.
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M, Bolt-up Procedure, QSPC-33, Revision 4.
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M. Process Control; Groove Fillet or Socket Welds, QSPC-37,
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Revision 6.
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M Torus Coating, QSPC-38, Revision 6.
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M, Process Control, Installation and Welding Sequence for Torus
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Modification, QSPC-44, Revision 3.
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Persennel Certifications, Material and Equipment Certifications The inspector reviewed NDE personnel certifications in accordance
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with SNT-TC-1A, 1975 Edition and welder certifications in accord-j I
ance with ASME Section IX, 1980 Edition, Winter 1981 Addenda.
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The inspector reviewed the certification documents relative to
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the following items:
Liquid penetrant, magnaflux materials, penetrant, cleaner
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and developer.
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Magnetic particle, Magnaflux materials and equipment.
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d.
Observation of Work
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The inspector observed several welders welding and visually examined i
the welds of the following:
Torus spray header saddles
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Downcommer longitudinal bracing
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Catwalk overhead support plate
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Lower catwalk support beam
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Ring guide weld reinforcement
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Ring guide stiffener plate
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i Downcommer crotch plates
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RCIC drain pot vent line stiffener
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HPCI drainline vacuum breakers
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Mid span strut
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e.
Review of NCRs, Surveillance and Data Reports A review of data reports for the torus activity demonstrated that the QA/QC commitments had been complied with.
The inspector also reviewed Receiving Reports, QC Receipt Inspection Reports, Chemical Analysis Certifications, PO's, NCR's and CECO " Survey Status Inspection" of Morrison, No. QC 82-21, dated September 15, 1982.
No items of noncompliance or deviations were identified.
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2.
Inservice Inspection a.
General Ceco contracted U.S. Testing Company to perform the ISI in accordance i
l with ASME Section XI, 1974 Edition, Summer 1975 Addenda, a
b.
Program and Procedures The inspector reviewed the following procedures.
USTCo, NDE Personnel Certifications, UST-TC-1A, Revision 7.
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l (SNT-TC-1A 1975/1980 Edition)
CECO, Ultrasonic Inspection of Pipe Welds, NDT-C-2, Revision 12.
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CECO, Ultrasonic Inspection of External Support Attachment
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Weld Areas of Piping.
NDT-C-4, Revision 9.
CECO, Ultrasonic Inspection of the Inner Radius of the Nozzle
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to Vessel Junction, NDT-C-10, Revision 6.
CECO, Ultrasonic Inspection of Reactor Vessel Head Welds,
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NDT-C-12, Revision 6.
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CECO, Ultrasonic Inspection of Pressure Retaining Bolting TWo
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j Inches or Greater in Diameter, NDT-C-14, Revision 6.
CECO, Ultrasonic Inspection of Ferritic Safe-End to Nozzle
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Welds, NDT-C-15, Revision 3.
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CECO, Ultrasonic Inspection of Dissimilar Metal Welds,
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NDT-C-16, Revision 4.
CECO, Ultrasonic Inspection of Control Rod Drive Return,
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Line Nozzle, NDT-C-26, Revision 0.
CECO, Ultrasonic Examinstion of Reactor Vessel Welds to NRC
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Regulatory Guide 1.150 for Boiling Water Reactors, NDT-C-30, Revision 0.
CECO, Beam Spread and Refracted Angle Determination of NRC
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Regulatory Guide 1.150 for BWRs, NDE-C-31, Revision 0.
CECO, Nonaqueous Red Dye Liquid Penetrate Examinations,
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NDT-D-2, Revision 3.
CECO, Visual Examination of Nuclear Reactor Coolant System
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Components, NDT-V-1, Revision 4.
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Personnel, Material and Equipment Certifications, Data Reports
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and Audit J
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The inspector reviewed NDE personnel certifications in accordance
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with SNT-TC-1A, 1975 Edition and certification documents relative to the following items:
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Liquid penetrant, magnaflux materials, penetrant, cleaner and
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i developer.
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l Ultrasonic instruments, calibration blocks, transducers and
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couplant.
The inspector also reviewed data reports and determined that they demonstrated that the QA/QC requirements were met.
An audit was reviewed of the ISI activities by CECO QA, No. QAM 4-82-52.
No items of noncompliance or deviations were identified.
3.
Reinspection of Unit I Core Spray Welds r
a.
As required by LER 80-25/0IT-0 a re-examination of the following Core Spray Welds was performed for Unit I and was found to be acceptable.
(Ref. NRC Reports No. 254/80-23; 265/80-25 Repair of Core Spray Welds).
A-Loop B-Loop 14A-F2 UT 14B-F2 UT 14A-F3R UT 14B-FAR UT 14A-F4ER UT 14B-F6AR PT 14A-F6 UT 14B-F7 UT I
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USTCo performed the NDE in accordance with ASME Section XI, 1974 Edition, Summer 1975 Addenda.
c.
The procedures reviewed in Paragraph 2.b were also used on the Core Spray System piping.
d.
The inspector reviewed NDE personnel certifications in accordance with SNT-TC-1A, 1975 Edition and certification documents relative to the following items:
Liquid penetrant, magnaflux materials, penetrant, cleaner
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and developer.
Ultrasonic instruments, calibration blocks, transducers and
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, couplant, A review of data reports demonstrated that the QA/QC commitments had e.
been complied with.
No items of noncompliance or deviations were identified.
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4.
Feedwater Sparger Replacement, Clad Removal and Control Rod Drive Return Line Thermal Sleeve Removal and Inspection a.
General The old feedwater spargers were replaced and the feedwater nozzle cladding was removed. The activities involved were as follows:
The old feedwater spargers were removed.
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The nozzle bore and radius stainless steel cladding on all four
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feedwater nozzles was machined out.
i The nozzle bore, radius, and machined areas were PT'd.
No
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relevent indications were present in three nozzles.
In the PT of the 60* nozzle face and bore, GE identified a crack approxi-mately 33" long in the cladding at the 12 o' clock position and identified four small rounded indications, in a row, in the cladding at the 6 o' clock position with a crack like indication between the second and third round indications.
In all, the four indications were approximately 23" long. GE used their Procedure QCCR 1015, Revision 0, to go 1/8" deep in the 33" long crack and 1/16" to 3/32" deep in the four rounded
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indications. At this point the inspector observed the areas that were ground out.
After the grinding there was still a crack in the 33" long area. CECO then used their approved procedure, " Grinding of Reactor Pressure Vessel Clad, Revision 2" to go 3" deep. After grinding 1" deep there was still a crack approximately li" long.
In accordance to CECO procedure, to go deeper than
}", approval from GE, San Jose Design Engineering must be received. GE approval was received. The 12 o' clock position was ground down i", 7" long and 4" wide before the crack was removed. The 6 o' clock position was ground down 5/16", 6" long and 3" wide before the crack was removed. Final PT was performed on both areas to verify that the cracks were removed.
New triple sleeve-double piston ring spargers were installed.
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A baseline UT was performed on all four nozzle bore and
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radius areas. The safe-end-to-nozzle welds in the drywell were also UT'd.
Thermocouples were installed on the outside surface of the
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feedwater nozzles.
The CRD Return Line nozzle thermal sleeve was removed and the nozzle PT'd.
The nozzle radius, bore, and face were cleaned and flapper-wheel ground prior to a PT.
Several circumferential and axial indications on the welded ring were present, as were some axial indications on the radius.
Following grinding operations a second PT was performed.
Small axial indications on the radius and several small indications on the bottom section of the ring remained.
Following further grinding, the nozzle was FT'd by the Commonwealth
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Edison Company Level III, and evaluated. The remaining relevant indications were a small nozzle radius indication which was removed by grinding, and an axial indication on the ring. The axial indica-tion on the ring has been analyzed and evaluated by the Station Nuclear Engineering Department to allow it to remain in place. A final PT was performed to verify removal of the nozzle radius indication.
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A UT of the CRD Return Line nozzle inner radius and adjacent vessel plate was performed, and no crack indications were detected.
An augumented ISI of the high-stress weld joints on the CRD Return Line in the drywell was performed by UT.
No crack indications were detected.
Prior to unit start-up, both of the CRD Return Line manual valves located outside the drywell will be shut and locked. This is the present arrangement for Unit 2.
b.
Procedure Review The inspector reviewed the following procedures:
GE, Tool and Equipment Control, QCCR1-1001, Revision 0
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GE, Materials and Processes, QCCR1-1002, Revision 0
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GE, Cleaning and Cleanliness Instructions, QCCR1-1003, Revision 0
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GE, Pre-operational Test of the Cladding Removal Machine,
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QCCR1-1004, Revision 0 GE, Installation and Alignment of the Clad Removal Machine,
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QCCR1-1007, Revision 0 GE, Feedwater Nozzle Dimension Measurements, QCCR1-1008,
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Revision 0 GE, Machining Procedure for Feedwater Nozzles, QCCR1-1009,
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Revision 0 GE, Feedwater Sparger Fit-up and Installation, QCCR1-1010,
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j Revision 0 GE, Ultrasonic Thickness Measurements of Feedwater Nozzles and
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Safe-Ends, QCCR1-1011, Revision 0 GE, Liquid Penetrant Examination of Nuclear Power Plant
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Components, QCCR1-1012, Revision 0 GE, Load Movement and Control, QCCR1-1013, Revision 0 l
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GE, CRM Hydraulic Fluid Inventory Control, QCCR1-1014, Revision 1
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GE, NDT Personnel Training Qualification and Certification
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Procedure No. ASBD-NDT-1101.
GE, General Welding Procedure, GWP 1000, Revision 14
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GE, General Weld Repair Procedure, GWP 1001, Revision 8
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GE, Welding Performance Qualification, P28A-AE-2012, Revision 1
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GE, Welding Performance Qualification Sup., P28A-AE-2012S1,
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Revision 0 GE, Detailed Welding Procedure Specification, WPS 8.2.3.1,
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Revision 6 GE, Detailed Welding Procedure Specification, WPS 8.2.4.8.R,
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Revision 4 GE, Procedure Qualification Record, PQR 3.8.9.5.2, Revision 0
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GE, Procedure Qualification Record, PQR 306, Revision 0
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GE, Welder Qualification, WQ 8.2.3.1, Revision 6
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GE, Welder Qualification WQ 1025, Revision 0
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GE, Product Specification, PS 5000, Revision 12
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GE, Product Specification, PS 5006, Revision 12
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GE, Product Specification, PS 5051, Revision 1
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GE Product Specification, PS 5217, Revision 0
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GE, Ferrite Measuring, PP-FM-4001, Revision 2
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GE, Weld Material Control and Issue, GWP 1010A, Revision C
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GE, Radiographic Examination for the Qualification of Welders,
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NDE-RT-3006, Revision 1 c.
Observation The inspector observed / examined the following:
Face cutting of a nozzle
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Welds and pipes of the new sparger
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Unacceptable areas ground out in the 60* nozzle
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d.
Travelers, Personnel Certifications, Data and Audit The inspector reviewed the following:
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Travelers.
NDE personnel certifications in accordance with SNT-TC-1A,
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1975 Edition.
Welds personnel certifications in accordance with ASME Section IX
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1977, Winter 1979 Addenda.
,
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Data Reports.
.
CECO QC " Survey / Status" Report No. 82-22 on GE clad removal
.
activities.
CECO QA Audit Report No. QAM 4-82-68 of clad removal activities.
.
t No items of noncompliance or deviations were identified.
5.
Reactor Water Cleanup System Piping (RWCU)
l a.
General The RWCU Line was replaced in the same basic configuration as the
!
original routing. The exceptions to this were that large radius l
pipe bends (5D radius) were replaced with standard elbow fittings (1.5D radius) and a 6" maintenance valve was added close to the 20" RHR Header.
Weld end details for pipe to pipe and pipe to fitting joints were j
in accordance with NUTECH Drawing M-1640.
NDE of these weldments were in accordance with Repair Programs COM-49-0201 and COM-49-0202.
'
Integrally attached pipe support lugs were replaced on the new piping in the identical locations as the originals.
Lug geometry, thickness, and attaching weld size matched those of the original.
Lug material was in accordance with NUTECH Drawing M-1700 and examination of welds was in accordance with the repair programs.
.
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Program and Procedures Review The inspector reviewed the following program and procedures:
NUTECH, Repair Programs COM-49-0201 and COM-49-0202.
.
Mechanical Inco:porated (MI), Weld Repair Procedure,, WPS-903,
.
Revision 1.
MI, P-8 to P-8 GTAW with Consumable Inset, WPS-909, Revision 0.
.
CECO, Radiographic Examination, NDT-A, Revision 8.
.
GE, Welding Procedure (Automatic Welding Machine) 8247,
.
Revision 0.
c.
Material and Equipment Certifications and Purchase Orders (PO)
The inspector reviewed the certification documents relative to the following items:
Ultrasonic instruments, calibration blocks, transducers and
.
couplant.
Liquid penetrant materials.
.
Stainless steel (S/S) A 312 type 304L, Sch. 80, 6" pipe.
.
S/S Type 304L, Sch. 80, 90* elbows, 6" diameter.
.
S/S Type 308L S/S, 6", Consumable Inserts.
.
The inspector also reviewed P0's on 6" pipe and elbows.
d.
Personnel Certifications, Observation, Data Reports, Drawings and Audit The inspector reviewed the following:
.
NDE personnel certifications in accordance with SNT-TC-1A, 1975 Edition.
Welder certifications in accordance with ASME Section IX,
.
1977 Edition, Summer 1977 Addenda, GE and MI.
,
It was determined that applicable welding and NDE procedures
.
and materials were used and the appearance of the weld surfaces were acceptable.
Travelers, welding, receiving inspection and NDE reports.
.
NUTECH Drawing No. M-1700, " Lugs."
.
NUTECH Drawing No. M-1640, M-1701 and MI Drawing No. 1-1202-6"-W2
.
of Reactor Water Cleanup System and Weld End Details.
S&L Drawing, 151-109 Revision A, Inservice Inspection Class I
.
Reactor Water Cleanup Piping.
CECO Surveillance Report No. QAM 4-82-119 of Mechanical Inc.
.
activities also Reports No. 4-82-118 BS and No. 4-82-112.
Radiographs and reports of the following welds, which were
.
replaced and found to be acceptable in accordance with CECO, Radiographic Examination Procedure NDT-A1, Revision 8.
Weld No.
Weld No.
Weld No.
SW-1 SW-10 FW-5 SW-2 SW-11 FW-6 SW-3 SW-12 FW-7
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Weld No.
Weld No.
Weld No.
SW-4 SW-13 FW-8 SW-5 SW-14 FW-9 SW-6 FW-1 GE-FW-1 SW-7 FW-2 GE-FW-2 SW-8 FW-3 GE-FW-3 SW-9 FW-4 GE-FW-4 f
No items of noncompliance or deviations were identified.
Exit Interview The inspector met with site representatives (denoted in Persons Contacted
!
Paragraph) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection noted in this report.
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