IR 05000269/1989018
| ML15224A553 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/20/1989 |
| From: | Blake J, Chou R, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A552 | List: |
| References | |
| 50-269-89-18, 50-270-89-18, 50-287-89-18, NUDOCS 8906270178 | |
| Download: ML15224A553 (18) | |
Text
a REG UNITED STATES NUCLEAR REGULATORY COMMISSION REGION 11
< o 101 MARIETTA STREET, ATLANTA, GEORGIA 30323 O Report Nos.: 50-269/89-18, 50-270/89-18, and 50-287/89-18 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.:
50-269, 50-270, License Nos.: DPR-38, DPR-47, and and 50-287 DPR-55 Facility Name:
Oconee 1, 2, and 3 Inspection Conducted: June 5-9, 1989 Inspectors: JJA
, ?(1,,
_
R. W. Newsofe Date Signed Date igned Approved by:
C) B1ke,'Chief Date Signed Maeri s and Processes Section Engin ering Branch Division of Reactor Safety SUMMARY Scope:
This routine, announced inspection was conducted on-site in the areas of Inservice Inspection (ISI) including the eddy current examination of the Unit 2 Steam Generator (SG)
tubin The inspection included a review of the 1SI program and the Unit 2 inspection plan for this outage; reviews of nondestructive examination (NDE)
procedures; observations of in-progress NDE examinations; independent examination verifications; reviews of NDE personnel qualifications; reviews of NDE equipment calibration and material certification documentation; and, a review of completed NDE examination dat Independent inspection was conducted and NRC previously opened items were addresse Results:
In the areas inspected, violations or deviations were not identifie The licensee's ISI program appears adequate in all areas inspecte No major problems were identified in any of the ISI areas inspecte During the independent inspection conducted on pipe supports, minor discrepancies were noted for some of the pipe supports when the as-built drawings were compared with the actual support configuration in the fiel :8 890621 DR DC o)0:269 PDC:
O These pipe support deficiencies are additional examples of deficiencies identified in Violation 50-269, 270, 287/87-31-01 which is still pending resolution by the license REPORT DETAIL. Persons Contacted Licensee Employees
- E. Anderson, Site Design Engineer
- T. Curtis, Compliance Manager T. Hilderbrand, Eddy Current Examination Supervisor
- E. Legette, Compliance Engineer
- M. Tuckman, Station Manager
- J. Warren, Quality Control (QC) General Supervisor
- B. Waters, QA Manager Other licensee employees contacted during this inspection included craftsmen, engineers, security force members, technicians, and administrative personne NRC Resident Inspectors
- P. Skinner, Senior Resident Inspector
- L. Wert, Resident Inspector
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragrap. Inservice Inspection The inspectors reviewed documents and records and observed activities, as indicated below, to determine whether ISI was being conducted in accordance with applicable procedures, regulatory requirements, and licensee commitment The applicable code for ISI is the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME B&PV)
Code,Section XI, 1980 edition with addenda through Winter 198 Duke Power NDE personnel were performing the liquid penetrant (PT),
magnetic particle (MT),
radiography (RT),
visual (VT),
and the majority of the ultrasonic (UT)
examinations with Babcock and Wilcox (B&W)
personnel providing technical assistance to Duke Power personnel during the UT of components not totally familiar to the Duke Power personne B&W personnel are conducting some of the required UT examinations for Duke Power but only on a limited basis. Steam generator tubing eddy current (EC) examination data collection was being accomplished by Duke Power personnel with B&W performing the primary manual data analysis with Duke Power personnel performing a secondary automated data evaluatio II
a. ISI Program Review, Units 1, 2, and 3 (73051)
The inspectors reviewed the following documents relating to the ISI program to determine whether the plan had been approved by the.
licensee and to assure that procedures and plans had been established (written, reviewed, approved and issued) to control and accomplish the following applicable activities:
organizational structure including qualifications, training, responsibilities, and duties of personnel responsible for ISI; audits including procedures, frequency, and qualification of personnel; general Quality Assurance requirements including examination reports, deviations from previously established program, material certifications, and identification of components to be covered; work and inspection procedures; control of processes including suitably controlled work conditions, special methods, and use of qualified personnel; corrective action; document control; control of examination equipment; quality records including documentation of indications and NDE findings, review of documentation, provisions to assure legibility and retrievability, and corrective action; scope of the inspection including description of areas to be examined, examination category, method of inspection, extent of examinations, and justification for any exception; definition of inspection interval and extent of examination; qualification of NDE personnel; and, controls of generation, approval, custody, storage and maintenance of NDE record Inservice Inspection Plan Oconee Nuclear Station Unit 2, Refueling Outage #10
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QCL-5 (R9)
Control Of Preservice And Inservice Inspection Activities
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QA-16 (R6)
Procedure for Inspection of ASME Section XI Field Piping Welds
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NDE-A (R9)
Nondestructive Examination Program Procedure
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NDE-C (R3)
Calibration/Verification of NDE Equipment b. Review of NDE Procedures, Units 1, 2, and 3 (73052)
(1) The inspectors reviewed the procedures listed below to determine whether these procedures were consistent with regulatory requirements and licensee commitment The procedures were also reviewed in the areas of procedure approval, requirements for qualification of NDE personnel, and compilation of required records; and, if applicable, division of responsibility between the licensee and contractor personnel if contractor personnel are involved in the ISI effor II
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ISI-120 (R25)
Ultrasonic Examination Of Pipe and with FC-DPC-88-006 Vessel Welds Joining Similar And Dissimilar Materials ISI-130 (R24)
Ultrasonic Examination of Vessel Welds with CA-CAT-89-006 and Nozzle Inside Radius Sections NDE-44 (R8)
Ultrasonic Examination of Bolts, with TFC 89-02 Studs, Bushings and Threads in Flanges For Preservice And Inservice Inspection ISI-460 (R14)
Technical Procedure For The Evaluation Of Eddy Current Data Of Nuclear Grade Steam Generator Tubing ISI-418 (R5)
Technical Procedure for the Multi-frequency Eddy Current Examination of OTSG Tubing in 177 Steam Generators using the MIZ-18 ISI-464 (R4)
Technical Procedure for the Evaluation of Eddy Current Data of Nuclear Grade Steam Generator Tubing for Wear Fretting Eddy Current Analysis Guidelines For Oconee 1,2, & 3 Nuclear Station (Revision 1 5/19/89)
NDE-35 (RIO)
Liquid Penetrant Examination Technique (Color Contrast, Solvent Removable Method)
NDE-98 (R4)
Liquid Penetrant Examination Technique (color Contrast, Solvent Removable Method) For Preservice And Inservice Inspection NDE-25 (R12)
Magnetic Particle Examination Procedure and Techniques QCL-13 (R6)
ISI Visual Examination, VT-1 QCL-14 (R8)
ISI Visual Examination, VT-3 and VT-4 QCL-15 (R6)
ISI Visual Examination, VT-2, Pressure Test
-
NDE-12 (R7)
General Radiography Procedure For Preservice And Inservice Inspection
All procedures listed above have been reviewed during previous NRC inspection Only current revisions were reviewed during this inspectio (2) The inspectors reviewed the Ultrasonic (UT)
procedures to ascertain whether they had been reviewed and approved in accordance with the licensee's established QA procedure The procedures were also reviewed for technical adequacy and conformance with ASME,Section V, Article 5 and other licensee commitments/requirements in the following areas:
type of apparatus used; extent of coverage of weldment; calibration requirements; search units; beam angles; DAC curves; reference level for monitoring discontinuities; method for demonstrating penetration; limits for evaluating and recording indications; recording significant indications; and, acceptance limit (3) The inspectors reviewed the Eddy Current (EC)
procedures for technical content relative to:
multichannel examination unit, multichannel examination indication equipment is specified, examination sensitivity, material permeability, method of examination, method of calibration and calibration sequence, and acceptance criteri (4) The inspectors reviewed the liquid penetrant (PT)
procedures to ascertain whether they had been reviewed and approved in accordance with the Ticensee's established QA procedure The procedure was also reviewed for technical adequacy and conformance with ASME,Section V, Article 6, and other licensee requirements in the following areas:
specified method; penetrant material identification; penetrant materials analyzed for sulfur; penetrant materials analyzed for total halogens; surface temperature; acceptable pre-examination surface conditioning; method used for pre-examination surface cleaning; surface drying time prior to penetrant application; method of penetrant application; penetrant dwell time; method used for excess penetrant removal; surface drying prior to developer application, if applicable; type of developer; examination technique; evaluation techniques; and, procedure requalificatio (5) The inspectors reviewed the Magnetic Particle (MT) procedure to ascertain whether it had been reviewed and approved in accordance with the licensee's established QA procedures. The procedure was reviewed for technical adequacy and for conformance with the ASME Code Section V, Article 7, and other licensee commitments/require ments in the following areas:
examination methods; contrast of dry powder particle color with background; surface temperature; suspension medium and surface temperature requirement for wet particles; viewing conditions; examination overlap and directions; pole or prod spacing; current or lifting power (yoke); and, acceptance criteri (6) The inspectors reviewed the Visual (VT) examination procedures to determine whether they contained sufficient instructions to assure that the following parameters were specified and controlled within the limits permitted by the applicable code, standard, or any other specification requirement:
method direct visual, remote visual or translucent visual; application hydrostatic testing, fabrication procedure, visual examination of welds, leak testing, etc.; how visual examination is to be performed; type of surface condition available; method or implement used for surface preparation, if any; whether direct or remote viewing is used; sequence of performing examination, when applicable; data to be tabulated, if any; acceptance criteria is specified and consistent with the applicable code section or controlling specification; and, report form completio (7) The inspectors reviewed the Radiographic (RT) procedure to determine whether it contained sufficient information to assure that the following parameters were specified and controlled within the limits permitted by the applicable code, or any other specification requirement:
type of material to be radiographed; material and weld surface condition requirements; type of radiation source, effective focal spot or effective source size; film brand or type; number of films in cassette; minimum source to film distance; type and thickness of intensifying screens and filters; quality of radiographs; film density and contrast for single and composite viewing; use of densitometers for assuring compliance with film density requirements; system of radiograph identification; use of location markers; methods of reducing and testing for back-scatter; selection of penetrameters including penetrameter placement; number of penetrameters; shims under penetrameters; radiographic technique for double wall viewing; and, evaluation and disposition of radiograph C. Observation of Work and Work Activities, Unit 2 (73753)
The inspectors observed work activities, reviewed certification records of NDE equipment and materials, and reviewed NDE personnel qualifications for personnel that had been utilized during the required ISI examinations during this outag The observations and reviews conducted by the inspectors are documented belo (1) The inspectors observed calibration activities and portions of the in-process ultrasonic examinations being conducted on the welds indicated below. The observations were compared with the applicable procedures and the ASME B&PV Code in the following areas:
availability of and compliance with approved NDE procedures; use of knowledgeable NDE personnel; use of NDE personnel qualified to the proper level; type of apparatus used; calibration requirements; search units; beam angles; DAC curves; reference level for monitoring discontinuities; method of demonstrating penetration; extent of weld/component examination
coverage; limits of evaluating and recording indications; recording significant indications; and, acceptance limit Item N Weld ID Description B02.040.002 2-SGA-WG58-2 SG-A, Lower head to Tube Sheet C01.020.005 2-CFTB-LH-SHL Core Flood Tank Head to Shell The inspectors conducted an independent ultrasonic verification examination, using Duke Power equipment, on portions of welds listed abov These examinations were performed in order to evaluate the technical adequacy of the ultrasonic examination procedure being used by the licensee and to assess the validity of the information being reported by the ultrasonic examiner The verification ultrasonic examinations conducted by the inspectors indicated that the procedure being used to conduct the examinations is adequate and the verification examination results compared favorably with the information being reported by the ultrasonic examiner The following listed ultrasonic equipment and materials certification records were reviewed:
Ultrasonic Instruments Manufacturer/Model Serial N KB/USD-10 31501-537 KB/USK-6 27593-4182 The inspectors reviewed spectrum analysis data for the ultrasonic transducers listed below:
Serial N Size Frequency F21817
.25" 5.00 MH (megahertz)
M18425 1.0" 2.25 MHZ z Ultrasonic Couplant Batch Numbers 8661 & 8764 Ultrasonic Calibration Blocks 40350 & 40397 (2) Steam Generator Tubing Eddy Current Examination The inspectors observed the EC activities indicated belo The observations were compared with the applicable procedures and the Code in the following areas:
method for maximum sensitive is applied; method of examination has been recorded; examination equipment has been calibrated in accordance with the applicable performance reference; amplitude and phase angle have been
calibrated with the proper calibration reference and is recalibrated at predetermined frequency; required coverage of steam generator tubes occurs during the examination; acceptance criteria is specified or referenced and is consistent with the procedure or the ASME Code; and, results are consistent with the acceptance criteri (a) Steam generator tube eddy current data collection is being accomplished by Duke Power personne In-process tube data acquisition, including calibration confirmation and tube location verifications, was observed for the steam generator tubes listed below:
SG-B Row Co Row Co SG-A Row Co (b) In-process Eddy Current data evaluation, including calibration confirmation, was observed for the tubes listed below. Primary manual data analysis was being accomplished by B&W and secondary automated data analysis was accomplished by Zetec and Duke Powe If differences are noted between the two evaluations they are resolved by a designated lead analyst The below listed tubes were jointly evaluated by the NRC inspector during the data evaluation observations conducted by the inspector. The NRC inspector's evaluation indicated that the tubes appeared to be correctly evaluated by the analysts and that any noted indications were being reported as require Primary Analysis Steam Generator A Row Column Row Column 104 119 100 118 109 116 110 115 113 113 113 114 114 111 149
96 127
68 135
135
135
135
135
135
135
135
Secondary Analysis Steam Generator A Row Column Row Column 103
103
104
103
103
103
103
103
103
103
103
77
77
77
77
77
27
27
27
27
28
28
(c) Certification records of EC calibration standards 49154 and 49155 were reviewed for material type, correct fabrication, and artificial flaw location/siz (3) The inspectors observed the in-process PT examinations indicated belo The observations were compared with the applicable procedure and the ASME B&PV Code in the following areas:
specified method, penetrant materials identified; penetrant materials analyzed for halogens and sulfur; acceptable pre-examination surface; surface temperature; surface drying time prior to penetrant application; method of penetrant application; penetrant dwell time; method used for excess penetrant removal; surface drying prior to developing, if applicable; type of developer; examination technique; evaluation technique; and, reporting of examination result Item N Weld N B10.010.001 2-53A-H8B C05.021.003A 2-53A-9-17 The inspectors reviewed the below listed liquid penetrant materials. certification records to ascertain if the sulfur and halogen content of the material was within acceptable content limit Materials Batch N Liquid Penetrant 87KO43 Cleaner/Remover 89C011 Developer 89805K (4) The inspectors reviewed documentation indicating that a 10 pound lift test had been performed on magnetic particle alternating current (AC) yoke OC-QA-182. The certification record for lift test plate SYCNT-11016 was reviewed to confirm the weight of the test plat A review of the magnetic particle material certification record for batch number 88G001 indicated the sulfur and halogen content of the material was within acceptable content limit (5) Verification Of Visual Examinations The NRC inspectors conducted an independent visual examination of the pipe supports tabulated belo This examination was conducted in order to evaluate the adequacy of the examination procedure being used by the licensee and to assess the validity of the information being reported by the visual examiners. These re-examinations generally agreed with the findings of the visual examiner Item N Component ID F1.03.265 2-03A-1-0-1400A-H32/R3 F1.03.305 2-03A-1-0-1400A-H33/R2 F1.03.264 2-03A-1-0-1400A-SR103/RO F1.03.178 2-03A-1401A-GC-0905/R1 F1.03.135 2-03A-1-0-1401A-SR28/R1 F1.03.179 2-03A-1-0-1401A-SR31/R7 F1.03.177 2-03A-1-0-1401A-SR33/R3 F1.03.142 2-03A-1401B-DE007/RO F1.03.143 2-03A-1-0-1401B-SR16/R2 F1.03.141 2-03A-1-0-1401B-SR17/R5 F1.03.436 2-07A-0-1400A-H1O/RO
F1.03.392 2-07A-0-1400A-H16/R4 F1.03.433 2-07A-0-1402A-H40/RO F1.03.391 2-07A-6-0-1400A-H60/R3 F1.03.390 2-07A-6-0-1400A-H65/R4 F1.03.393 2-07A-6-0-1400A-H68/R1 F1.03.394 2-07A-6-0-1400A-H69/R2 F1.03.431 2-07A-0-1402A-R13/R2 F1.03.374 2-07A-0-1400A-SR25/RO F1.02.072 2-01A-0-1481A-H3A/RO F1.01.133 53A-0-1478A-H3A/RD2 (6) The inspectors evaluated the below listed radiographic films for these Main Steam pipe welds which were radiographed under the licensee's ISI program. These films were evaluated in order to determine if the radiographic quality was in accordance with the applicable procedure and ASME Code requirements and to specifically verify the following: penetrameter type, size, and placement; penetrameter sensitivity; film density and density variation; film identification; film quality; weld coverage; and, disposition of the welds radiographe Item N Weld N Film Reviewed C05.021.101 2-O1A-MS1A-B 0-1, 1-2, 2-3, 3-4, 4-5, 5-6, 6-7, 7-8, 8-0 C05.021.122 2-O1A-MS5B-A 0-1, 1-2, 2-3, 3-4, 4-5, 5-6, 6-7, 7-0 C05.021.122L 2-O1A-MS5B-AL 0-1 C05.021.101L 2-01A-MS1A-BL 0-1 The inspector confirmed the calibration status for Densitometer OCQA19 (7) The inspectors reviewed the qualification documentation for the below listed examiners in the following areas:
employer's name; person certified; activity qualified to perform; effective period of certification; signature of employer's designated representative; basis used for certification; and, annual visual acuity, color vision examination, and periodic recertificatio Company Examiner Method-Level DPC MWB EC IIA DPC WKD EC IIA B&W JMB EC III B&W CRH EC IIA B&W DEH EC IIA B&W RLN EC IIA DPC TMB EC IIA DPC MBT EC IIA ZETEC CRB EC IIA ZETEC MJK EC IIA ZETEC KJN EC IIIA DPC TBA EC II DPC TLT EC II DPC DLP EC II DPC RR VT-1 II DPC DLO VT-3/4 II DPC WCL VT-3/4 II DPC AEB VT-3/4 II DPC TRB VT-3/4 II DPC ADG MT II/PT II DPC CHM MT II/PT II DPC GJM PT II DPC DLR PT II DPC JWS PT II/UT II DPC JWR PT II DPC RPB PT II/MT II DPC GGB PT II/UT II DPC HAD RT II DPC WGR RT II DPC DWB UT II DPC MTW UT I DPC DLR UT II d. Data Review and Evaluation, Unit 2 (73755)
(1) Records of completed nondestructive examinations were selected and reviewed to ascertain whether:
the methods(s), technique, and extent of the examination complied with the ISI plan and applicable NDE procedures; findings were properly recorded and evaluated by qualified personnel; programmatic deviations were recorded as required; personnel, instruments, calibration blocks, and NDE materials (penetrants, couplants)
were designate Records selected for this review are listed belo Item N Weld/Component ID NDE Method 805.021.001 2PZR-WP91-1 PT B05.021.002 2PZR-WP91-2 PT B05.021.003 2PZR-WP91-3 PT B05.050.008B 2PDB2-2 PT B07.020.004 2PZR-RELIEF-A VT-1 16 NUTS & 8 STUDS 807.020.005 2PZR-RELIEF-B VT-1 16 NUTS & 8 STUDS B07.020.006 2PZR-RELIEF-C VT-1 16 NUTS & 8 STUDS B08.020.004 2PZR-WP82-YZ MT 808.020.008 2PZR-WP82-WX MT B09.021.004 2PSP-12 PT 809.021.006 2PSP-21 PT 809.021.007 2PSP-22 PT 809.021.031 2-50-7.1-30 PT B09.021.032 2-50-7.1-34 PT B09.021.038 2-51A-35.1-101 PT B09.032.007 2PDB1-10 MT B09.032.008 2PDB2-10 MT C02.010.003 2LPCB-INLET PT C03.040.054 2-53B-R11 PT C05.011.008 2-53B-17.2-25 PT C05.011.010 2-53B-17.2-79A PT C05.011.021 2-53B-17.4-101 PT C05.011.024 2-53B-18.1-40 PT C05.021.101A 2-O1A-MS1A-B MT C05.021.122A 2-01A-MS5B-A MT C05.021.101 2-O1A-MS1A-B RT C05.021.122 2-O1A-MS5B-A RT C05.021.122L 2-O1A-MS5B-AL RT C05.021.101L 2-01A-MS1A-BL RT 805.050.008 2PDB2-2 UT B05.050.008A 2PDB2-2 UT C01.030.005 2LPCB-SH-TUBE UT C05.021.003 2-53A-9-17 UT F1.03.265 2-03A-1-0-1400A-H32/R3 VT-3/4 F1.03.305 2-03A-1-0-1400A-H33/R2 VT-3/4 F1.03.264 2-03A-1-0-1400A-SR103/RO VT-3/4 F1.03.178 2-03A-1401A-GC-0905/R1 VT-3 F1.03.135 2-03A-1-0-1401A-SR28/R1 VT-3 F1.03.179 2-03A-1-0-1401A-SR31/R7 VT-3 F1.03.177 2-03A-1-0-1401A-SR33/R3 VT-3 F1.03.142 2-03A-1401B-DE007/RO VT-3 F1.03.143 2-03A-1-0-1401B-SR16/R2 VT-3 F1.03.141 2-03A-1-0-1401B-SR17/R5 VT-3 F1.03.436 2-07A-0-1400A-H1O/RO VT-3/4 F1.03.392 2-07A-0-1400A-H16/R4 VT-3/4
F1.03.433 2-07A-0-1402A-H40/RO VT-3/4 F1.03.391 2-07A-6-0-140A-H6 VT-3/4 F1.03.390 2-07A-6-0-1400A-H65/R4 VT-3/4 F1.03.393 2-07A-6-0-1400A-H68/R1 VT-3/4 F1.03.394 2-07A-6-0-1400A-H69/R2 VT-3/4 F1.03.431 2-07A-0-140A-R13/R2 VT-3 F1.03.374 2-07A-0-1400A-SR25/RO VT-3 F1.02.072 2-O1A-0-1481A-H3A/RO VT-3/4 F1.01.133 53A-0-1478A-H3A/RD2 VT-3/4 (2) The inspectors reviewed the eddy current data analysis results and a sample of associated completed records for approximately 50 SG A and B tubes. The reviews were compared with the applicable procedures and the ASME B&PV Code in the following areas:
the multichannel eddy current examination equipment has been identified; material permeability has been recorded; method of examination has been recorded; and, results are consistent with acceptance criteri The inspectors compared randomly selected current examination results with historical examination result No significant discrepancies were note By the conclusion of the NRC inspection all EC examinations had not been complete The final examination results will be reported to the NRC in accordance with TECH SPEC requirement Preliminary results of the EC examinations of SG's A and B indicate that 3 tubes in each of the 2 steam generators will require plugging in accordance with the applicable acceptance criteri In the areas inspected, violations or deviations were not identifie.
Independent Inspection While the inspectors conducted the visual examination verification on the pipe supports identified in paragraph 2.c.(5) above, it was noted that five supports had discrepancies when compared to the as-built drawing Four supports appeared to have original construction deficiencies and one support had a bent member which could be either an original construction deficiency or a service induced deficiency. The five supports with their associated discrepancies are listed belo These discrepancies are additional examples of the discrepancies identified in Violation 50-269, 270, 287/87-31-01, As-Built Drawing Discrepancies Compared With As-Built Conditions, which is still pending licensee resolutio II
Item N Support N Discrepancy (1) F1.03.265 2-03A-1-0-1400A-H32/R3 Support 2-03A-1-0-1400A-H33 is attached to the same common channel This common attachment is not shown on the drawin (2) F1.03.135 2-03A-1-0-1401A-SR28/R1 Four welds at two horizontal members connected to a column and both ends of an inner vertical member are welded on two sides onl The drawing indicates these members should be welded all aroun (3) F1.03.391 2-07A-6-0-1400A-H60/R3 Snubber is not perpendicular to the pipe. The drawing does not show the snubber in an offset positio (4) F1.03.374 2-07A-0-1400A-SR25/RO The outer vertical member is ben (5) F1.01.133 53A-0-1478A-H3A/RD2 Support 53A-0-1478A-GPD-0101 is on the same line and 11" west of 53A-0-1478A-H3 Support 53A-0-1478A-GPD-0101 has been omitted from the isometric drawin Within this area of inspection, no violations or deviations were identifie. Action on Previous Inspection Findings (92701) (Closed) UNR 50-269/88-23-04, Pipe Support Discrepancies Between the As-Built Drawings and Field Condition This matter concerned the discrepancies found in as-built drawings such as insufficient weld sizes, members that require removal not having been removed, and the installed base plate thickness being less than require The inspectors held discussions with the responsible licensee's engineer and reviewed the commitment for corrective actio In the response, the licensee stated that all of the supports identified in the inspection report with discrepancies had been reviewed and found to be operable in their existing condition and that drawings and calculations had been revised to reflect the actual condition in the field and the items were requalified if require The inspectors sampled the revised drawings and calculations to verify the licensee commitments in the respons These reviews of revised
drawings and calculations were acceptable and this item is considered close (Closed) UNR 50-269/88-23-05, Inadequate Pipe Support Calculation This matter concerned inadequate qualifications on pipe support calculations due to joint release on the computer model, the wrong allowables being used for anchor bolt size, and dimension and load analysis being inadequate. The inspectors held discussions with the responsible licensee's engineer and reviewed the commitment for corrective actio In the response, the licensee stated that all of the support calculations identified in the inspection report with discrepancies had been revised and the supports remained acceptabl The inspectors sampled the revised calculations to verify the licensee commitments in the respons The reviews of the revised calculations were acceptable and this -item is considered close. Exit Interview The inspection scope and results were summarized on June 9, 1989, with those persons indicated in paragraph 1. The inspectors described the areas inspected and discussed in detail the inspection result Dissenting comments were not received from the license O 6. Acronyms and Initialisms AC
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Alternating Current ASME -
American Society of Mechanical Engineers B&PV
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Boiler and Pressure Vessel B&W
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Babcock and Wilcox Col
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Column DAC
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Distance Amplitude Curve DC
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Direct Current DPC
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Duke Power Company EC
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Eddy Current ID
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Identification ISI
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Inservice Inspection KB
-
Krautkramer/Branson MT
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Magnetic particle MH
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Megahertz NDf
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Nondestructive Examination N Number NRC
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Nuclear Regulatory Commission OTSG -
Once Through Steam Generator PT
-
-
Quality Assurance QC
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Quality Control R
-
Revision RT
-
Radiographic Test SG
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Steam Generator TFC
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Temporary Field Change
-
Unresolved Item UT
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Ultrasonic VT
-
Visual
0