IR 05000338/1989006
| ML20244B018 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/20/1989 |
| From: | Blake J, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20244B013 | List: |
| References | |
| 50-338-89-06, 50-338-89-6, 50-339-89-06, 50-339-89-6, NUDOCS 8904180324 | |
| Download: ML20244B018 (12) | |
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UNITED STATES -
g-lj NUCLEAR REGULATORY COMMISSION e
REGION 11
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- 101 MARIETTA ST., N.W.
y,,p ATLANTA, GEORGIA 30323 -
-Report Nos.:
50-338/89-06 and 50-339/89-06
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Licensee: ' Virginia -Electric and Power Company
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Glen Allen VA 23060
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l Docket Nos.: 50-338'and 50-339 License Nos.:
Facility Name: ' North Anna 1 and 2
Inspection-Conducted: March 6 thru 10,1989 Inspector:
-[._L h 3- /d-87 la t Signed
.W e som Approved b -
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V 3 vo
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.J.
lake, Chief Date signed
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at ials and Processes Section
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E ineering Brcnch
' Division of Reactor Safety
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SUMMARY Scope This routine, unannounced inspection was conducted in the areas of Inservice Inspection.(ISI) including the eddy current examination of the Unit 2 steam generator tubing.
The inspection included a review of the Unit 2 ISI plan for
.l 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
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equipment calibration and material certification documentation; and, a review i
of completed NDE examination data.
In addition to the above inspections, activities associated with the Unit 1 l
steam generator tube leak were observed and historical eddy current data was
reviewed for the leaking tube.
j Resul ts This inspection indicated that ISI nondestructive examinations were being j
conducted adequately.
The NDE personnel conducting the examinations appeared well qualified and the results of the examination verifications conducted by the NRC inspector agreed well with the reported results.
The licensee's newly imposed requirement that all contractor NDE personnel demonstrate their
- competency by satisfactorily passing an NDE method (s) examination (s) prior to
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I 8904180324 890330 PDR ADOCK 05000338 :
O PNU
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being allowed to conduct examinations in the field is an excellent safeguard i
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for assuring that the personnel in the field are well qualified. The licensee is requiring these examinations in all areas of NDE including a demonstration of competency for the evaluation of eddy current data.
The institution of these programs by the licensee indicates a willingness to go beyond the minimum requirements for assuring that ISI examinations are adequately addressed.
Eddy current activities associated with the Unit 1 steam generator tube leak indicated that the licensee's system for recalling historical eddy current data is adequate and a review of the historical data did not indicate evidence of tube degradation in the area of the tube where the leak is expected to be found.
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j REPORT DETAILS 1.
Persons Contacted (
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I Licensee Employees
- M. Bowling, Assistant Station Manager
- R. Driscoll, Manager, Quality Assurance
- L. Hartz, Supervisor, Configuration Management
- G. Kane, Station Manager
- P. Kemp, Supervisor, Licensing i
- J. Leberstien, Licensing Engineer
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- C. Sorrell, Supervisor, Engineer Mechanics
- H. Travis, Supervisor, NDE Services i
Other licensee employees contacted during this ir,spection included craf tsmen, engineers, security force members, technicians, and
administrative personnel.
NRC Resident Inspector
- J. Caldwell, Senior Resident Inspector
- Attended exit interview f
Acronyms and Initialisms used throughout this report are listed in the last paragraph.
2.
Inservice Inspection The inspector 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 commitments.
The applicable code for ISI is the American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME B&PV) Code, i
Section XI,1974 edition with addenda through Summer 1975, however, most of the NDE procedures have been updated to the 1983 edition of the ASME B&PV Code with addenda through Summer 1983.
Virginia Power personnel are
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primarily acting as coordinators for contractor personnel who are
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conducting the nondestructive examinations using Virginia Power procedures.
The liquid penetrant (PT), magnetic particle (MT), ultrasonic (UT), and visual (VT) examinations were being conducted by Virginia Corporation of Richmond (VCR), however, Westinghouse (W) personnel were being processed into the NDE group and will be conducting ISI NDE examinations for the licensee as well.
Steam Generator eddy current (EC)
data collection and primary data analysis was being done by W utilizing an automated data analysis system and a secondary manual data analysis of the same data is being accomplished by a pool of analysts from various companies.
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.ISI Outage' Plan Review, Unit 2 (73051)
The : inspector reviewed the;ISI plan for this outage and the below listed associated administrative procedures 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:
duties of personnel responsible for ISI; scope of the inspection including description'of areas to be examined, examination category,. method of inspection, extent of examinations, and justifi-cation for any exception; definition of insperrion interval and extent of examination; qualification of NDE personnel;; and, controls of generation, approval, custody, storage and maintenance of NDE.
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records.
NDE-2.4 (R3)
Requisition and Reporting of NDE Services
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NDE-3.1(RS)
Preparation, Issue and Control of Nondestructive Examination Procedures NDE-4.1 (R10) Virginia Power Written Practice For Certification i
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Of Nondestructive Examination Personnel l
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NDE-6.3 (RO)
. Storage And Control Of NDE Calibration Standards
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Steam Generator Eddy Current Data Analysis Program (RO)
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Attachment I (RO)
Eddy Current Data Analysis Qualification
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Program Attachment II lR0) Protocol Of Data Evaluation AttachmentIII(RO) Analysis Rules - Bobbin Coil b.
Review of NDE Procedures, Units 1 and 'i (73052)
(1) The' inspector reviewed the procedures listed below to determine j
whether these procedures were consistent with regulatory i
requirements and licensee commitments.
The procedures were also j
reviewed in the areas of procedure approval, requirements for i
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 effort.
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NDE-7.3 (RO)
General Requirements For ISI No.1 destructive Examination
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DAT-GYD-001 (R2)
Data Analysis Guideline
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WDE-MT-301 (RO)
Magnetic Particle Examination I
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NDE-M7-302(RO)-
Magnetic Particle Examination Of Bolting
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NDE-PT-301(RO)
Liquid Penetrant Examination NDE-UT-301 (RO)
Manual Ultrasonic Examination Of
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Piping Welds (2) The. inspector reviewed the eddy current data analysis procedure for technical content relative to:
multichannel examination unit, multichannel examination indication equipment is specified, examination sensi tivity, method of examination, method of calibration and calibration sequence, and, acceptance criteria.
(3) The inspector reviewed the magnetic particle procedures to ascertain whether they had been reviewed and approved in accordance with the licensee's established QA procedures. The procedures were reviewed for technical adequacy and for conformance with the ASME Code Section V, Article 7, and other licensee commitments / requirements in the following areas:
examination methods; con +rast of dry powder particle color with
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background; surface temperature; suspension medium and surface
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temperature requirement for wet particles; viewing conditions; i
examination overlap and directions; pole or prod spacing-
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current or lifting power (yoke); and, acceptance criteria.
l (4) The-inspector reviewed liquid penetrant procedure NDE-PT-301 to ascertain whether it had been reviewed and approved in accordance with the licensee's established QA procedures.
The procecure 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 halogens; surface temperature; acceptable pre-examination surface conditioning; method used _for pre-examination surface cleaning; surface drying time prior to penetrant application; i
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;
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examination technique; evaluation techniques; and, procedure
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requalification.
(5) The inspector reviewed ultrasonic procedure NDE-UT-301 to ascertain whether it had been reviewed and approved in accordance with the licensee's established QA procedures. The
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procedure - was also reviewed for technical adequacy aad conformance with ASME, Section t, 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 limits.
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Observation of Work and Work Activities, Unit 2 (73753)
The inspector 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 outage. _ The observations and
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reviews conducted by the inspector are documented below.
l (1) The inspector observed calibration activities and 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 NOE personnel qualified to the proper level; type of apparatus used; calibration requirements; search units; beam angles; DAC curves; reference
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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 limits.
Drawing No.
Weld ID VGB-1-4503 1-DM VGB-1-4503
VGB-1-4503
The inspector conducted an independent ultrasonic verification
examination, using Virginia Power equipment, on portions of
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welds 1-DM and 10. These examinations were performed in order to evaluate the technical adequacy of the ultrasonic examination procedure being used by the licensee's contractor to perform l
ultrasonic examinations and to assess the validity of the information being reported by the ultrasonic examiners.
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The verification ultrasonic examinations conducted by the j
inspector indicated that the procedure being used to conduct the j
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examinations' is ~ adequate. and the verification)F examination -
results compared favorably with the information being reported -
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by the ultrasonic examiners.
(2) The following listed ultrasonic equipment and materials-certification records were reviewed:
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Ultrasonic Instruments-Manufacturer /Model Serial No.
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-Sonic /MK1 02307E Sonic /MK1 10159E-Sonic /MK1-13041E-The inspector reviewed spectrum analysis data for the ultrasonic transducers listed below:
i Serial No.
Size Frequency K05966-
.25" 2.25 MHz (raegahertz)
43107
.5"
.2.25 MHz J02184
.5" 2.25 MH Z
42743
.5" 2.25 MH z F18164
.5" 2.25 MHz Ultrasonic Couplant Batch Number 8557 Ultrasonic Calibration Blocks VRA-14, VGB-17, VGB-19, VRA-07-(3) The' inspector reviewed the below listed liquid - penetrant materials certification records to ascertain if the sulfur and j
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halogen content of the material was within acceptable content limits.
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Materials Batch Number Liquid Penetrant 85LO45
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Cleaner / Remover 88J029-j Developer 86A055 l
(4) The inspector reviewed documentation indicating that a 10 pound
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lift test had been performed on magnetic particle alternating
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Certification records for lift test
plate MT-03 was reviewed to confinn the weight of the test l
plate.
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(5), Steam Generator _ Tubing Eddy Current Examination-
.The inspector observed the EC activities indicated below.
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 refer _ence and is
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recalibrates at predetermined frequency; -required coverage of steam generator tubes occurs dur.ing 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) Steam generator tube eddy current data collection is being
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accomplished by ~W personnel.
In-process tube data acquisition, including calibration confirmation and tube
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location verifications were observed for the steam
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generator "C" tubes listed below:
Row Col.
Row Col.
38 15.38
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38
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38
20
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25
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29 38'
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In-process. Eddy Current data evaluation, including
calibration confirmation, was observed for the below listed j
"C" tubes.
Data analysis was accomplished
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by first having the data evaluated by the W Intelligent Eddy-Current Data Analysis (IEDA) automated system followed by an independent manual data analysis utilizing other than W analysts.
If differences are noted between the two evaluations, they are resolved by a designated lead analysts.
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i Primary (IEDA) Analysis Secondary Analysis Row Column Row Column
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43 (c) During the observations of the secondary analysis
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activities for the above listed tubes, the inspector
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jointly evaluated the data with the analysts.
No
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significant discrepancies were noted.
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(d) Certification records of EC calibration standards Z-3282, l
04523, and Z-3179 were reviewed for material type, correct l
fabrication, and artificial flaw location / size.
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(6) The inspector 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 decertification.
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I Company Examiner Method-Level ECHO RAP EC-IIA NDE-T JMC EC-IIA W
DJT EC-III W
KAI EC-III ANA TH EC-IIA j
VCR RTS VT1-II/UT-II/PT-II/MT-II
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VCR KDH UT-II VCR ABN VT1-II/UT-II/PT-II/MT-II VCR MJB VT1-II/UT-II/PT-II/MT-II j
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Inservice Inspection, Data Review and Evaluation, Unit 2(73755)
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'
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procedures; findings were properly recorded and evaluated by l
qualified personnel ; programmatic deviations were recorded as j
requi red; personnel, instruments, calibration blocks, and NDE
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materials (penetrants, couplants) were designated.
Records selected for this review are listed below.
j Drawing No.
Weld / Component ID NDE Method
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VGB-2-2524
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VGB-2-2524
UT VGB-2-2202-
UT VGB-2-2200
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VGB-2-2200
UT VGB-2-2526
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VGB-2-2532 WS-1 PT
l VGB-2-2526 H-1 PT VGB-2-2531 WS-1 PT
VGB-2-2523
UT f
VGB-2-2202 WS-1 MT j
VGB-2-2102 WS-1 MT
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ECI-104C 2-SI-SH-55 VT-3
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ECI-104H 2-RH-R-19 VT-3
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ECI-104C 2-SI-R-56 VT-3 ECI-104H 2-RH-R-20 VT-3 Within this area of inspection, no violations or deviations were identified.
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3.
Steam Generator C Tube Leak Activities, Unit 1 (73755)
Background:
On February 25,1989, Unit 1 experienced an automatic reactor trip from approximately 75% power.
During the activities that followed this event, a Steam Generator "C" tube, apparently leaking near the 7th tube support plate, was identified.
(Refer to NRC report 50-338, 339/09-03 for details of the reactor trip cause und additional information regarding the reasons for the steam generator
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tube leak and the corrective actions initiated by the licensee).
On March 6,1989, a remote visual examination of the hot leg (inlet) side of the tube sheet revealed the location of the leaking tube to be at the Row 3 Column 60 position and the tube appeared to be leaking around and/or through a mechanical plug in the tube end.
A remote visual j
examination of the tube plug was conducted sometime later
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which revealed the plug had fractured with the top, sealed end, portion becoming separated from the plug body.
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location of the plug end top had r.ot been determined by the l
end of this inspection.
Historical eddy current reports indicated that the Row 3 Col. 60 tube had
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been plugged in November 1985 following the eddy current examinations conducted at that time.
The tube had been identified as having an indication of 65% through wall at the 1st tube support plate on the hot leg side of the steam generator but there was no record of indications near the 7th tube support plate where the current leak is thought to be i
occurring.
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Following the determination of which tube was actually leaking and the information that the tube had been plugged in 1985 as a result of the eddy current evaluation of the tube at that time, the licensee was requested by the NRC inspector to obtain the 1985 recorded eddy current data tape of the leaking tube.
The eddy current data tape for the tube was located and reviewed by the NRC inspector and W personnel.
Westinghouse had conducted the examinations of the steam generator tubing during the 1985 outage.
The reviews of the eddy current tube data indicated the tube had been examined from the hot leg side and from the tube sheet face to just above the 7th tube support plate on the hot leg side.
The data revealed an indication at the 1st tube support plate but there was no evidence of indications at the 7th tube support plate on the hot leg side of the steam generator.
The absence of indications at the 7th tube support plate in the eddy current data would logically indicate that the leak, if located at the anticipate location, must have occured sometime after the examination conducted in 1985 e the leak could be near the 7th tube support plate on
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the cold leg '(outlet)? side of-the steam generator for which there is no
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historical eddy current data.
The licensee had not positively identified where the tube. leak was occurring and was continuing to investigate this matter at the. conclusion of this NRC inspection'.-
Within this area of inspection, no violations or deviations were identified.
4.
Exit Interview The inspection scope and results were summarized on March 10, 1989, with.
those persons-indicated in paragraph 1.
The' inspector described the areas
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inspected and discussed in detai1 the inspection results. Although reviewed during this inspection, proprietary information is not contained in tnis report. Dissenting comments were not received from the licensee.
5.
Acronyms and Initialisms.
Alternating Current AC
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ANA Allen Nuclear Associates
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American Society of Mechanical Engineers ASME
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B&PV Boiler and Pressure Vessel
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Col.
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Distance Amplitude. Curve
.DAC
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Eddy Current EC'.-
Echoram Technology ECHO
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ID Identification
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IEDA Intelligent Eddy-Current Data Analysis
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Inservice Inspection ISI
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Magnetic. particle MT
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Megahertz'
MH
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- NDI Nondestructive Examination
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NDE Technology Number No.
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Nuclear Power Facility NPF
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Nuclear Regulatory Commission NRC
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Quality Assurance QA
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Revision R
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Virginia Corporation of Richmond j
VCR
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VT Visual
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W Westinghouse Electric Corporation
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