IR 05000395/1990013
| ML20042F791 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/26/1990 |
| From: | Blake J, Chou R, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20042F789 | List: |
| References | |
| 50-395-90-13, NUDOCS 9005090394 | |
| Download: ML20042F791 (14) | |
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l 9'o NUCLEAR REGULATORY COMMisslON i
REGloN il
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ATLANTA, GE oRGI A 30323
a.... e Report No.:
50-395/90-13 i
Licensee: South Carolina Electric and Gas Company
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Columbia, SC 29218
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Docket No.:
50-395 License No.: NPF-12
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Facility Name:
V. C. Summer
Inspection Conducted: April 16-20, 1990 Inspectors: f w l lAI.
Y Gk0 w _-
R. W. Newsome (
Va te ' Signed
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Dat ig d Approved by d n -- #
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4 [d K J.
. Chief ff
'/DatV51gned Mat and Proc f Section k Engi eering Br Division of actor Safety SUMMARY Scope:
This routine, announced inspection was conducted on-site in the areas of Inservice Inspection (ISI), including the a:tivities associated with the eddy current examination, of the' steam generator tubing and snubber testing and examination activities.
This inspection included a review of the ISI and snubber related programs and plans-for this outage; a review of program related administrative procedures; a review of nondestructive examination (NDE)
procedures and snubber testing and e'xamination procedures; observations of in-progress examinations and tests; independent examination verifications; reviews of personnel qualifications and NDE equipment-and material I
certifications; and, a review of completed examination data.
Results:
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In the areas inspected, violations or deviations were not identified.
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The licensee's ISI and snubber testing programs are effective in the areas i
reviewed.
The procedures and examination techniques being used by the NDE l
examiners and snubber testing and examination personnel on safety related items and welds was adequate.
The examiners appeared to be adequately qualified for the NDE methods and snubber tests observed. and documentation of examination results appeared adequate.
' A potential problem with the method used for verification of snubber settings in i
50-395/90-13-01, paraaraph 2.c.(5)s matter is identified as Unresolved Item
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field was identified and thi a
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9005090394 900427 PDR ADOCK 05000395
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REPORT DETAILS L
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Persons Contacted L
Licensee Employees
- R. Campbell, Senior Engineer, Inservice Examination Group
- R. Clary, Manager, Design Engineering M
- R. Cox, e,upervisor, Design Engineering
- H. Donnelly, Senior Engineer, Regulatory Compliance
- S. Hunt, Manager, Quality Systems
R. Kelso, Inservice Examination (ISE)
-*A. Koon, Manager, Nuclear Licensing B. Mather, ISE c
- D. Moore.-General Manager, Engineering Services
- K. Nettles, General Manager, Nuclear Safety
- C, Price, Manager, Technical Oversight
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- J. Skolds, General Manager, Nuclear Plant Operations I
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- A. Torries. Supervisor, NDE/ISE Other licensee em)loyees contacted during this inspection included engineers, mechandes, security force members, technicians, and administrative personnel.
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NRC Resident Inspectors R. Prevatte, Senior Resident Inspector
- L. Modenos Resident Inspector
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragraph.
2.
InserviceInspection(ISI)
The inspectors reviewed documents and records, observed in-progress
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testing and examinations, and conducted independent evaluations and i
L examinations, as indicated below, to determine whether ISI and snubber testing and examinations were being conducted in accordance with applicable procedures, regulatory requirements and licensee commitments.
The applicable code for testing and examination activities is the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME B&PV)
Code,Section XI 1977 edition with addenda through Sunner 1978.
Nuclear Energy Services (NES), under direct control and supervision of South
(SCE&G), were conducting the manual
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Carolina Electric and Gas _ Company (PT), Magnetic Particle (MT), and some l
Ultrasonic (UT), Liquid Penetrant Visual. (VT) examinations.
Eddy Current (EC) examinations of the steam i
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generator tubing was conducted by Babcock and Wilcox (B&W) with B&W performing data acquisition and a manual primary data analysis and an automated secondary data analysis.
SCE&G personnel conducted the functional tests on snubbers and conducted the in-field VT examinations of i
snubbers and pipe supports.
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ISIProgram/PlanReview(70370)(73051)
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The inspectors reviewed the below listed documents relating to the
licensee's inservice inspection program and plan for the current
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outage in the areas of:
program approval; Quality Assurance (QA)-
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program requirements including organizational structure; audit requirements; general QA requirements (examination reports, control of deviations from established program; quality documentation and
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identification of components); work and quality inspection
procedures; control of processes; corrective action; document control; control of examinatiot 5 and exan.ination equipment; quality records;- irspection scope; iMpection intervals; personnel qualifications, and NDE records including provisions for storage.
QSP-208(R1'
Housekeeping Inspection
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QSP-210 (RO)
Inservice Inspection Non-Destructive Examination
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QSP-213 (RO)
NDE Inservice Examination Program
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Al-104 (RI)
Qualification And Certification Of Quality
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Control Inspection Personnel NDE Plan Interval-1, Exam Period-2 IMS-94B-1221(RO)
Inservice Examination Manual-For Non-Destructive Examination
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SAP-10d(R4)
Guidelines For Controlling Station Work
Activities SAP-150(R6)
Records Managemo t And Document Control
STP-804.901(RO)
Steam Generator Tube Inspection GTP-303 (R4)
Inservice Inspection Non-Destructive Examination with change C
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ReviewofProcedures(70370)(73052)
(1) The inspectors reviewed the procedures listed below to determined whether these procedures were consistent with t
regulatory requirements and licensee commitments.
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procedures were also reviewed in the areas of procedure approval, requirements for qualification of personnel, and i
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compilation of required records; and if applicable, division of
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responsibility between the licensee and contractor personnel if
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contractor personnel are involved ir. the ISI effort.
.i NES/83A0282(R4)
Procedure For Ultrasonic Examination Of L
Piping Systems NES/83A0288(R2)
Ultrasonic Examination Of Vessel Welds'
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In Ferritic Materials Greater Than Two l-Inches In Thickness NES/83A0281(R2)
Liquid Penetrant Examination (Color i
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with addendum'VCS-001 Contrast,SolventRemovable)
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NES/83A0284(R2)
Magnetic Particle Examination Wet And with addendum VCS-001 Dry Methods
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SCE8G/QSP-505(R2)-
Visual Examination i
SCE&G/STP-803.002(RO)
Mechanical Snubber Visual Examiantion
,SCE&G/STP-803.003(RO)
Mechanical Snubber Basic Operational
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Test-8&W/ISI-424 (R15)
Multi-Frequency Eddy Current
Examination Of.750" OD x.044" Wall
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RSG Tubing For ASME Exam-And Tube Wear
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At Tube Support Plates
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B&W/ISI-460(R14)
Technical Procedure For The Evaluation
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Of Eddy Current Data Of Nuclear Grade Steam Generator Tubing
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B&W/ISI-510(R8)
Eddy-360/RDAU System Operating l
Procedure
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SCE&G/QSP-519(R1)
Steam Generator Eddy Current Data Analyst Guidelines
All procedures listed above have been reviewed during previous. NRC inspections.
Only current revisions were reviewed-during this
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inspection.
(2) The inspectors reviewed the Ultrasonic procedures to ascertain
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whether they had been reviewed and approved in accordance with the licensee's established QA procedures.
The procedures were
also reviewed for technical adequacy and conforn.ance with ASME, r
Section V Article 5 and other licensee commitments / requirements
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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
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discontinuities; method for demonstrating penetration; limits for evaluating and recording indications; recording significant indications; and, acceptance limits.
(3) The inspectors reviewed the Liquid Penetr;-t procedure to ascertain whether it had been reviewed and approved in accordance with the licensee's established QA procedures.
The procedure was also reviewed for technical adequacy and conformance with ASME,Section V, Article 6, and other licensee commitments / requirements in the following areas:
specified method; penetrant material identification; penetrant materials
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analyzed for sulfur; penetrant materials analyzed for total
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halogens; surface temperature; acceptable pre-excmination 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
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developer application, if applicable; type of developer; examination technique; evaluation techniques; and, procedure requalification.
(4) The inspectors reviewed the Magnetic Particle 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 conunitments/ requirements in the following areas:
examination methods; contrast of dry powder particle color with background; surf ace temperature; suspension medium and surface temperature requirement for wet particles; viewing conditions; examinatiun overlap and directions; pole or prod spacing; current or lifting power (yoke); and, acceptance criteria.
(5) The inspectors reviewed the Visual 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 -
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direct visual, remote visual or translucent visual; application
- hydrostatic testing, fabrication procedure, visual examination
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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 i
criteria is specified and consistent with the applicable code
section or controlling specification; and, report form comple-l tion.
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(6)-The inspectors reviewed the Eddy Current procedures for l
technical content relative to:
multichannel examination unit.
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i multichannel examination indication equipment is specified.
examination sensitivity, method of examination, method of calibration and calibration sequence, and acceptance criteria.
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All procedures reviewed appeared to. contain the necessary elements for conducting the specific examination.
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c.
Observation of Work and Work Activities (70370)(73753)
The inspectors observed work activities, conducted independent
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verification examinations, reviewed certification records of NDE i
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equipment and materials, and reviewed NDE personnel qualifications i
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examinations during this outage.
The observations, verification examinations, and reviews conductud by the inspectors are documented below.
(1) The NRC inspectors observed calibration activities and the
in-process UT examinations being conducted on 1 Component i
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Cooling 8" dia, circumferential pipe weld,1 Loop B 18" dia.
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Teedwater circumferential pipe weld, and 1 Safety Injection
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System 6" dia. circumferential pipe weld.
These observations
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were compared with the applicable procedures and. the = ASME B&PV
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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
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angles; DAC curves; reference level for monitoring
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discontinuities; method of demonstrating penetration; extent of weld /componeht examination coverage; limits of evaluating and r
recording indications; recording significant indications; and, acceptance limits.
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The inspectors conducted an independent ultrasonic verificetion i
examination, using NES equipment, on portions of the Feedwater
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weld previously observed being examined.
The examination was conducted in order to evaluate the technical adequacy of the ultrasonic examination. procedure being used and to assess the validity of the information being reported by the ultrasonic.
examiners.
The verification ultrasonic examination conduct *d by the inspectors indicated that the procedure being used to conduct
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the examinations is adequate and the verification examination results compared favorably with the information being reported by the ultrasonic examiners.
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The following listed ultrasonic equipment and materials certification records were reviewed:
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i Ultrasonic Instruments
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Manufacturer /Model Serial No.
KB/USK-7 3409 KB/USK-7 4163 KB/USK-7 3776
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KB/USK-7 3425
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The -inspectors reviewed spectrum analysis data for the
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ultrasonic transducers listed below:
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Size Frequency
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E16053
.5" 2.25 MHz J28907
.5" 2.25 MHz C17617
.25" 2.25 MHz M19552
.25" 2.25 MHz
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i Ultrasonic Couplant Batch Numbers 8868, 9084, and 0927843001
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Ultrasonic Calibration Blocks CGE-37, CGE-29, CGE-14, CGE-18, and CGE-35 (2) The NRC inspectors observed the in process liquid penetrant (PT)
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examinations of 2 circumferential pipe welds and 1 integral attachment weld to a-6" diameter Safety Injection pipe.
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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 temaerature; surface drying time prior to penetrant application; metnod of penetrant application; penetrant dwell time; method used for excess penetrant removal; surface drying prior. to developing, if applicable; tyne of developer; examination technique; evaluation technique; nd, reporting of examination results.
The NRC inspectors re-evaluated the 2 circumferential pipe welds.
following the PT examiners evaluation of the welds but prior to
the developer being removed from the weld surfaces.
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re-evaluations were conducted in order to determine if the evaluations conducted by the PT_ examiners were in accordance with-
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the applicable procedure acceptance criteria and to determine if.
the examination results were being reported as required.
The re-evaluations conducted by the NRC inspectors indicated that L
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the proper evaluation was made by the PT examiners and that the examination results were being reported as required.
The inspectors review of the below listed liquid penetrant
materials certification records indicated that the sulfur and halogen content of the material was within acceptable content limits.
- Materials Batch Number
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Liquid Penetrant 321J47 Cleaner / Remover 46F4, 431H4 Developer 45F6, 115E6 (3) The inspectors observed the in-process magnetic particle (MT)
examination of 1 Component Cooling circumferential pipe weld.
This observation was compared with the applicable procedure and the Code in the following areas:
examination methods; contrast of dry powder particle color with background; surface temperature; suspension medium for wet particles, if applicable; viewing conditions; examination overlap and directions; pole or prod spacing; current or lifting power (yoke); and acceptance criteria.
The inspectors conducted an MT verification examination, using NES equipment, on portions the weld previously observed being examined.
This examination was conducted in order to evaluate the technical adequacy of the examination procedure being used by the examiners to perform examination and to assess the validity of the information being reported by the MT examiners.
The information reported by the MT examiners compared favorably with the verification examinations.
P The inspectors reviewed documentaticn indicating that a 10 pound l
lif t test had been performed on magnetic particle alternating
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current (AC) yokes 4769, 756, 6853, 423, and 415.
The certification record for the lift test plate that was used to conduct the test,10.09 (AC-12), was reviewed to confirm the weight of the test plate.
A review of. the magnetic particle material certification records for batch numbers 84F007 and 87A030 indicated the pa ticles met i
the applicable specifications requirements.
(4) Observation of Snubber Functional Tests Technical Specification 4.7.7 c and e and Procedure STP-803.003 define the test procedure, plan, equipment, and acceptance criteria for the functional testing of snubbers.
The tests include, an acceleration test for snubber sizes PSA-10, PSA-35,
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i and PSA-100, and a drag force test for all snubber sizes.
The initial inspection plan required 133 mechanical snubbers be tested this outage.
The inspection plan required the testing of an additional 8 snubbers if I snubber fails testing.
To date. I snubber has failed the functional test.
The failed snubber has been replaced and the new replacement snubber was tested before installat;on.
Any snubbers which are found to be inoperable will have an engineering evaluation performed on the snubber attachment components to assure there are no adverse effects on other components.
The NRC inspectors observed 3 mechanical snubbers being functional tested.
All 3 snubbers were tested acceptable.
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NRC inspectors observation of these tests indicated that the
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tests were performed adequately in compliance with applicable procedures.
(5)
Independent Verification of Visual Examinations The licensee's ISI program contains a total population of 11000-
pipe supports which are subject to VT-3 AND VT-4 examination
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under requirements of ASME Section XI.
Of the 11000 supports, 250 were scheduled for examination during this refueling outage.
Most other supports and snubbers required for this inspection interval have been completed between the last and this refueling outages.. In addition,100 percent of all snubbers are required to be examined during each refueling outage per Technical Specification 4.7.7.
The snubber population is divided into two types, of which, 2000 (approximately) are mechanical snubbers and 15 are hydraulic snubbers.
A portion of these snubbers are also included in the 11000 pipe support population and the requirements of ASME Section XI for VT-3 and VT-4 visual examinations apply.
Therefore, in some instances, some of the snubbers must be examined under the dual requirements of ASME Section XI and Technical Specifications.
The NRC inspectors conducted independent visual exainin6tions of 40 pipe supports and snubbers selected at random. These items included 5 mechanical snubbers, examined under Technical Specification requirements, and 7 pipe. supports and 11 snubbers, examined under ASME Section XI requirements, that are located in the Reactor Building.
Additionally,11 mechanical snubbers,
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examined under Technical Specification requirements, and 6 pipe supports, examined under ASME Section XI requirements, that are located outside of the reactor building, were selected.
These examinations were conducted in order to evaluate the adequacy of the examination procedures being used by the licensee and to assess the validity of the information being reported by the examiners.
These verification examinations generally agreed with the findings of the visual examiners except for the minor discrepancies noted for the 4 supports listed below:
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Support No.
Discrepancy / Licensee Remedy CCH-294 Two lock nuts at pipe clamp have 1-1/2 threads short of engagement /The visual inspection procedure will be revised to add the inspection
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L criteria for lock nuts.
CCH-295 Three nuts at a clamp bolt are loose /MWR 90R "
was issued to tighten the loose nuts.
CCH-448 Snubber pin has rusted /lhe licensee will re-evaluate the condition.
SFH-052 The orientation of lugs is different from drawings /The calculations will be re-evaluated and drawings will be changed per the as-found condition.
During the verification examinations of snubbers and pipe supports, the inspectors noted that water was trapped in the small cubicles which were formed by the stif fener plates at the base plates for support numbers 13-436-FW-M, H and G, reference drawing No. E-513-163.
If the water remains tropped for a substantial period of time without being removed, the structural components for these supports may be degraded and may not perform their intended function. The degradation of the
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structural components has a safety impact on the system operability.
The licensee issued a housekeeping and fire protection inspection report to remove the trapped water and agreed to revise the Housekeeping Inspection procedure, QSP-208, to include a periodic check for trapped water in areas where
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water leakage or flooding might occur.
Per Section 8.4.4.B of QSP-505 and IWA-2214(b) of ASME,Section XI, the snubbers are required to have the settings verified during inspection.
The NRC inspectors noted that the QC inspectors did not perform verification of settings for snubbers during the visual inspections and functional tests.
The QC inspectors verify the snubber L-dimension (the dimension from the bottom of the snubber housing plate to the pin at the end cap) before disconnection and after assembly of the snubbers to see if the snubber position is within the L-minimum and L-maximum dimension.
The final L-dimension (or measured L-dimension) is recorded but is not compared to the required snubber setting L-dimension shown on the snubber drawing.
The L-minimum and L-maximum were derived from the manufacturer's catalog for the snubbers working range by adding 1/4" to the L-minimum and by deducting 1/4" from the L-maximum in order to establish a buffer to avoid the snubbers from bottoming out at either end. During examination the QC inspector makes a determination of the snubber L-dimension to verify that the snubber is within the
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L-minimum and L-maximum dimensions.
This is done to determine whether or not the snubber is out of range (inoperable or operable per manufacturer's catalog).
In order to verify that the cetting is correct, it is necessary to compare the final
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(measured) L-dimension against the L-dimension shown on the
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drawing.
A measured L-dimension could be located at any point
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within L-minimum and L-maximum but the snubber may not have enough travel distance for the temperature or seismic movements for the direction required to avoid a bottom out and thus deviate from the design basis.
Also, the snubber setting location may change slightly due to the systems operation but if it changes significantly the engineers should re-evaluate the change in snubber setting position.
Therefore, a verification of the setting is a necessary step to determine if ttie snubber is located at the correct point to assure bottoming out will not occur.
The licensee has agreed to submit a document of theory and practice to demonstrate that the final (measured) L-dimension is adequate to verify that the setting is acceptable.
Pending NRC review of the licensee's submittal concerning verification of snubber settings, this matter is identified as Unresolved Item 50-395/90-13-01, Verification of Snubber Settings.
The licensee has indicated that a request for interpretation of the ASME Code requirements, regarding this matter, may be submitted to the ASME Code Committee. The licensee was informed that the documentation relative to this matter will be transferred to NRR for their evaluation.
(6) SteamGenerator(SG)TubingEddyCurrentExamination
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The NRC inspectors observed the EC activities indicated below.
The observations were compared with the applicable procedures and
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the Code in the following areas: method for maximum sensitivity
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I is applied; method of examination has been recorded; examination
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equipment has been calibrated in accordance with the applicable L
l 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 criteria.
(a)
In-process SG tube eddy current data acquisition, including calibration confirmation and tube location verifications, was observed for 5 SG tubes located in SG-B.
(b)
In-process eddy current primary data evaluation, including calibration confirmation, was observed for 33 SG-C tube i
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The NRC inspectors co-evaluated 16 of the SG-C tubes during the observations of the primary analyst's evaluations.
The sample of evaluations, some having reportable indications and some with
no reported indications, was conducted in order to confirm the validity of the reported tubing condition.
The co-evaluation analysis conducted by the inspectors agreed well with the i
reported results.
t Certification records for EC calibration standards Z-3955 and Z-3956 were reviewed for material type, correct fabrication, and artificial flaw location and size.
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(6) The inspectors reviewed personnel qualification documentation for 6 UT examiners. 3 PT exeminers, 3 MT examiners, 9 VT examiners, and 10 EC data collection and EC data analysis
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personnel.
These qualifications were reviewed in the following areas:
employer's name; person certified; activity qualified to
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perform; current period of certification; signature of employer's designated representative; basis used for certification; and, annual visual acuity, color vision examination, and periodic recertification.
The personnel appeared to be adequately qualified in all cases reviewed.
d.
DataReviewandEvaluation(70370)(73755)
l (1) Records of completed ISI nondestructive examinations for 25 UT,
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20 PT, 47 MT, and 40 VT examinations were selected and reviewed to ascertain whether:
the method (s), technique, and-extent of the examination complied with the ISI plan and applicable NDE procedures; findings were properly recorded and evaluated by
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qualified personnel; programmatic deviations were recorded as required; personnel, instruments, calibration blocks, and NDE materials (penetrants, couplants) were designated.
(2) The NRC inspectors reviewed the eddy current data analysis results and a sample of associated records for more than 300 SG tubes, 100 tubes from each of tl % e Steam Generators. 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 criteria.
At the conclusion of this inspection all EC examinations had been completed, however, final determination of the number of tubes that will be plugged had not yet been established.
Final tube plugging will depend on how many tubes can be sleeved in each of the three steam generators.
Final examination results
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will be reported to the NRC in accordance with technical
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specification requirements.
Preliminary plans for tube plugging -
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L and sleeving is listed below.
SG-A SG-B SG-C To be Sleeved 125 108
To be Plugged
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Previously Plugged 280 507. 304
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Total tubes Plugged 1T5 T!i5 iti0
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All of the examination reports reviewed appeared.to contain the required examination information including ' disposition of
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indications, if any; In the areas-inspected, violations or deviations were not identified.
3.
Exit Interview
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The inspection-scope and results were summarized on April 20,.1990, with those persons indicated in paragraph 1.
The inspectors described the
areas. inspected and discussed in detail the inspection results listed below. -Although reviewed during this inspection, proprietary information is not contained in this report.
Dissenting comments were not received
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Unresolved Item 50-395/90-13-01, Verification of Snubber Settings, paragraph 2.c.(5).
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Acronyms and Initialisms Alternating Current AC
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American Society of Mechanical Engineers ASME
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Boiler and Pressure Vessel
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Babcock and Wilcox B&W
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. Distance Amplitude Curve Dia.
Diameter
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EC Eddy Current
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Inservice Examination
.lSE
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Inservice Inspection
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Krautkramer/Branson KB
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Magnetic particle MT-
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MWR
' Megahertz MHz-
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Maintenance Work Request
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Nondestructive Examination NDE
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NES Nuclear Energy Services
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. Number No.
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' Nuclear Regulatory Commission NRC
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Liquid' penetrant PT
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Quality Assurance QA
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Quality Control QC~
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Revision R
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South Carolina Electric and Gas Co.
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Surveillance Test Procedure-
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Ultrasonic UT-
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Visual VT.
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