IR 05000400/1989031
| ML18009A287 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/28/1989 |
| From: | Blake J, Chou R, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18009A286 | List: |
| References | |
| 50-400-89-31, NUDOCS 8912110208 | |
| Download: ML18009A287 (22) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323
/f +>>*<<~
Report No.:
50-400/89-31 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Shearon Harris Inspection Conducted:
November 11 thru 17, 1989
Inspectors: 'K~cu R.
W.
Newsome License No.:
NPF-63 Il-M gi)
Date Signed
I( ~&
Date Signed Approved by J. J.
lake, Chief M ter als and Processes Section ngi eering Branch iv>sion of Reactor Safety D
e Signed SUMMARY Scope:
This routine, announced inspection was conducted on-site in the area of Inservice Inspection (ISI).
The inspection included a
review of the ISI 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, reviews of completed NDE examination data, preliminary report documentation records of the Steam Generator tubing Eddy Current (EC) examinations, and the preliminary documentation records for the Ultrasonic (UT) examination of the Reactor Vessel nozzles.
Also, NRC previously opened items were addressed.
Results:
In the areas inspected, violations or deviations were not identified.
This inspection indicated that ISI nondestructive examinations were being conducted adequately.
The procedures and examination techniques used to F.o
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conduct the examinations were adequate and documentation of examination, results was very good.
In addition, independent examination verifications conducted by the NRC inspectors agreed well with examiner reported results.
C One unresolved item was identified, in the area of the licensee's program for visual examination of pipe hangers and snubbers that are located in areas open to the elements, such as the turbine building, paragraph 2.c.(4).
REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. Brown, Senior Specialist, Quality Assurance (QA)
R. Fichera, Senior Specialist, Inservice Inspection (ISI)
~C. Gibson, Director, Projects and Procedures
"J.
Hammond, Manager, Onsite Nuclear Safety
- C. Hinnant, Plant General Manager
- A. Howe, Senior Specialist, Regulatory Compliance R. Johnson, Senior Specialist, ISI-C.
Osman, Principal Nondestructive Examination Specialist
- M. Pugh, Project Specialist, ISI
- R. Richey, Manager, Harris Project
- C. Rose, Jr.,
Manager, QA
- M. Mallace, Senior Specialist, Regulatory Compliance L. Moods, Manager, Systems Engineering Other licensee employees contacted during this inspection included craftsmen, engineers, security force members, technicians, and administrative personnel.
Nuclear Energy Services (NES)
ST Larson, Project Engineer NRC Resident Inspectors
- J. Tedrow, Senior Resident Inspector M. Shannon, Res.ident Inspector
~Attended exit interview Acronyms and Initialisms used throughout thi,s report are listed in the last paragraph.
2.
Inservice Inspection (ISI)
The inspectors reviewed documents and records, conducted independent evaluations, 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 BE PV) Code,Section XI, 1983 edition with addenda through Summer 1983.
Carolina Power and Light (CP8L) personnel are acting as coordinators for contractor personnel.
NES has the primary responsibility as the ISI contractor for conducting the manual ultrasonic (UT), liquid penetrant (PT),
and magnetic particle (MT) examinations and has joint responsibility with CP&L for the visual (VT) examinations.
Conam has the responsibility for eddy current (EC) steam generator tubing data evaluation and collection while Westinghouse (W) had responsibility for the UT examinations of the Reactor Vessel Nozzles utilizing the automated UDRPS examination system.
ISI Program/Plan Review (70370)(730S1)
Technical Specification Equipment List Attachment 4, Snubbers The inspectors reviewed the inspection plan for this outage and the supporting documents listed below to determine whether
'the program/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 equality Assurance requirements including examination reports, deviations from previously established program, material certifications, and identification of components to'e 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 records.
Technical Specification 3/4.7.8 PLP-106 (R1)
ISI-202 (R2)
Safety-Related Component Supports (Hangers and Snubbers)
Examination and Testing Program Pre-Outage Checklist (R-LLS) Outage 1-1-02 - Interval
- Ol Period
EST-216 (Rl/AC1)
Steam Generator Tube Indication Tracking and Reporting Procedure
1989 Refueling Outage Steam Generator Eddy Current Sample Plan ISI-100 (R3/Ch.1)
Control of Inservice Inspection Activities ISI-102 (R3)
Inservice Inspection Drawing Preparation and Control ISI-103 (R2)
Receiving Inspection Procedure for Inservice Inspection Calibration Standards and Controlled Materials IST-102 (R2/Ch.1)
NES-.80A9003 (R11)
NES-80A9099 (R6)
NES-80A0283 (R1)
NES-80A9054 (R4)
Areas and Volumes of Welds and/or Components Subject to ISI Examinations NES Document Control Identification, Storage, And Retention Of Quality Assurance Records PSI/ISI Examination Areas And Volumes Calibration Of Magnetic Particle Examination Equipment During the, review of the inspection plan for this outage, the NRC inspectors noted that in some cases the NDE procedure numbers identified in the plan were not the procedures being utilized in the field examinations.
Discussions with the CP&L ISI Project Specialist indicated that the plan was currently undergoing a mass edit in this area and would be available for our review prior to the completion of this inspection.
The corrected plan was.
submitted to the NRC inspectors prior to the inspection completion and the edited plan correctly identified the NDE procedures being utilized during this outage'he review of the ISI plan and supporting administrative documents indicated that the supporting administrative documents appeared to be adequate and that the plan was pr'operly approved and contained the necessary information.
b.
Review of NDE Procedures (70370)(73052)
(1)
The inspectors reviewed the procedures listed below to determine whether these procedures were consistent with regulatory requirements and licensee commitments.
The procedures were also reviewed in the areas of procedure approval, requirements for qualification of examination 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 NES-83A0282 (R3/A3)
NES-83A0288 (R3/A2)
W-CQL-ISI-153 (RO)
W-CQL-ISI-154 (RO)
NES-83A0281 (R2/A3)
NES-83A0284 (R2/A1)
NES-83A0291 (R2)
CPS(L-MST-M0033 (R3)
CPS(L-NDEP-613 (R10)
CPS(L-NDEP-614 (R8)
CONAM-42-EC-179 (R2)
CONAM-42-DA-020 (RO)
Procedure For Ultrasonic Examination Of Piping Systems Ultrasoni c Examinati on of Vessel We 1 ds In Ferri tic Materials Greater Than Two Inches In Thickness General Requirements For The Ultrasonic Examination Of The Reactor Pressure Vessel Using UDRPS For Shearon Harris Unit No.
Ultrasonic Examination Requirements For Outlet Nozzles And Piping Welds From The Nozzle Bo~es Using UDRPS For Shearon Harris Unit No.
Liquid Penetrant Examination (Color Contrast, Solvent Removable)
Magnetic Particle Examination Wet And Dry Methods Visual Examination Procedure For Nuclear Power Systems And Related Components Mechanical Snubber Operational ( Functional) Test VT-3 Visual Examination of Nuclear Power Plant Components VT-4 Visual Examination of Nuclear Power Plant Components Multifrequency Eddy Current Procedure Westinghouse Model D4 Steam Generator Tubing MIZ-18 Digital Eddy Current System Shearon Harris Nuclear Power Plant Data Analysis For MIZ-18 Data Utilizing DDA-4 Digi tal Data Analysi s System Bobbin Coil Examination Shearon Harris All procedures listed above have been reviewed during previous NRC inspections.
Only current revisions *were reviewed during this inspectio The inspectors reviewed the Ultrasonic procedures to ascertain whether they had been reviewed,and approved in accordance with the'icensee's established gA procedures.
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 limits.
The inspectors reviewed the Liquid Penetrant procedure to asc'ertain whether,it had been reviewed and approved in accordance with the licensee's
established gA 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 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 requalification.
The inspectors reviewed the Magnetic Particle procedure to ascertain
" whether it had been reviewed and approved in accordance with the licensee's established gA procedures.
The procedure was 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; contrast of dry powder particle. color with background; surface temperature; suspension medium and surface temperature requirement for 'wet particles; viewing conditions; examination overlap and di rections; pole or prod spacing; current or lifting power (yoke); and, acceptance criteria.
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 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 comple-tion.
(6)
The inspectors reviewed the Eddy Current procedures for technical content relative to:
multichannel examination unit, multichannel examination indication equipment is specified, examination sensitivity, method of examination, method of calibration and calibration sequence, and acceptance criteria.
All procedures reviewed appeared to contain the necessary elements for conducting the specific examination.
Observation of Work and Work Activities (70370)(73753),
The inspectors observed in-process examination activities, conducted independent verification examinations, 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, independent examination verifications, and reviews conducted by the inspectors are documented below.
(1)
The inspectors observed calibration activities and the in-process UT examinations being conducted on 1 circumferential Chemical and Volume Control pipe weld and 8 feet of the Steam Generator (SG)
A tube sheet to head girth weld. These welds were being examined manually by NES examiners.
These observations were compared with the applicable procedures and the ASME BKPV.
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 UT scope
. used; calibration requirements; search units; beam angles; DAC curves; reference level for monitoring discontinuities; method of demonstrating penetration; extent of examination coverage; limits of evaluatirg
.and recording indications; recording significant indications; and, acceptance limits.
The inspectors conducted an independent ultrasonic verification examination, using NES equipment, on portions of the circumferential pipe weld and
feet of the SG girth weld previously observed being examined.
These examinations were 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 UT examiners.
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 examiners.
The following listed ultrasonic equipment and materials certification records were reviewed:
Ultrasonic Instruments Manufacturer/Model Serial No.
KB/USL-48 KB/USL-38 KB/USK-7 KB/USK-7 KB/USK-7 212200 211596 27276-3797 27276-4155 27276-3425 The inspectors reviewed spectrum analysis data for the ultrasonic transducers listed below:
Serial No.
B20930 B24650 30111 KB3105 123608~
123614*
Size
II
.25n
.375" 375" 5 II 5ll
~Fee uenc 2.25 MHz 2.25 MHz 2.25 MHz 2.25 MHz 2.00 MHz 2.00 MHz
"used by M for-RV nozzle examination Ultrasonic Couplant Batch Number 8981 Ultrasonic Calibration Blocks UT024-1 12" Dia.
X.425" SS UT014-1 3" Dia.
X
. 473" SS UT028-,1 14" Dia.
X 1.399" SS UT020-1 6" Dia.
X.722" SS UT019-1 6" Dia.
X
. 583" CS The inspectors observed the in-process liquid penetrant (PT)
examinations of
RHR and.
The observations were compared with the applicable procedure and the ASME BEPV 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 re: sits.
The NRC inspectors independently evaluated portions of
RHR and 1 SIS weld following the PT examiners evaluation of the welds but prior to the developer being removed from the weld surfaces.
The above observations and independent evaluations were conducted in order to determine if the examination technique and evaluations conducted by the PT examiners were in accordance with the applicable procedure acceptance criteria and to determine if the examination results were being reported's required.
The. observations and evaluations conducted.
by the NRC inspectors indicated that the proper examination technique and 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.
Material's Batch Number Liquid Penetrant Cleaner/Remover Developer 88M058 89H02K 88J012 The inspectors observed the in-process magnetic particle (MT)
examinations of Reactor Vessel replacement stud and nut No.
49.
The stud was subsequently rejected for excessive linear indications which were orientated with the axial direction of the stud.
The nut did not exhibit excessive linear indications and was considered acceptable.
These observations were compared with the applicable procedures 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 di rections; pole or prod spacing; current or lifting power (yoke);
and acceptance criteria.
Observations of these MT examinations indicated that the examinations were being conducted in accordance with applicable procedures and specifications.
The inspectors reviewed documentation indicating that a
10 pound lift test had been performed on magnetic particle alternating current (AC) yoke 415.
The certification record for the lift test plate that was used to conduct the test, SRO-MT-001, was reviewed to confirm the weight of the test plat A review of the magnetic particle material certification records for batch numbers 88L080 and 9D1414 indicated the particles met the applicable specifications requirements.
Independent Verification of Visual Examinations The licensee's ISI program contains a total population of 2443 pipe supports which are subject to VT-3 AND VT-4 examination under requirements of ASME Section XI.
Of the 2443 supports, 377 were scheduled for examination during this refueling outage.
In addition, 100 percent of all snubbers are required to be examined during each re'fueling outage per Technical Specification 3/4.7.8.
The snubber population is divided into two types of which 1507 are mechanical snubbers and
are hydraulic snubbers.
A portion of these snubbers are also included in the 2443 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 o>
ASME Section XI and Technical Specifications.
The NRC inspectors conducted independent visual examinations of 18 pipe supports and snubbers selected at random.
These items included
mechanical snubbers, examined under
,Technical Specification requirements, and 4 pipe supports, examined under ASME Section XI requirements, that are located in the Reactor Building.
Additionally, 2 hydraulic snubbers and
mechanical snubbers, examined under Technical Specification requirements, and
pipe supports, examined under ASME Section XI requi rements, that are located in the Turbine 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.
However, during the verification examination of Snubber No.
771 for support No.
MS-H-345, in the open areas of the Turbine Building, the inspectors noted that water was -trapped in the small cubicles which were formed by stiffener plates at the base plates.
Anchor bolts and nuts were submerged in the water which in turn was causing the bolts, nuts, and stiffener plates to rust.
Several other supports in this area were identified with similar problems.
The structural components for these supports are degraded and may not perform their intended functions and the degradation of the structural components has a safety impact on the snubber operability.
The licensee's engineers stated that only the snubber itself is inspected and that the rest of the components of the support structure do not require examination by either the procedure or local practice.
The NRC
inspectors pointed out, however, that the second requirement in pa-agraph 4.3, of the Visual Inspection Acceptance Criteria of At,:achment 4,
Snubbers, to Technical Specification PLP-106, Rev.
1, states that visual inspections shall verify that attachments to the foundations or supporting structure are functional.
Pending the licensee's resolution of the intent of the Technical Specification requirement, this matter is identified as Unresolved Item 50-400/89-31-01, Visual Inspection Of Snubbers.
Observation of Snubber Functional Tests Technical Specification PLP-106 and Procedure MST-M0033 define the test procedure, plan, machine, and acceptance criteria for the functional testing of snubbers.
The tests include an acceleration test and a drag force test.
The initial inspection plan required 39 mechanical snubbers be tested this outage.
The inspection plan requires the testing of an additional
snubbers if 1 snubber fails testing.
To date,
snubbers have failed the functional tests, eight snubbers failed the drag force tests, one snubber was broken, and three snubbers were bound.
Therefore, a total of 253 mechanical snubbers currently require testing.
All failed snubbers have been replaced and all new replacement snubbers were tested before installation.
To date, 165 mechanical snubbers have been tested.
The four hydraulic snubbers, which were required to be tested this outage, were tested in the field and found to be acceptable.
Any snubber s 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
mechanical snubbers being functional tested.
All 4 snubbers were tested acceptable.
The NRC inspectors observation of these tests indicated that the tests were performed adequately in compliance with applicable procedures.
The inspectors reviewed personnel qualification documentation as listed below.
These qualifications were reviewed in the following areas:
employer's name; person certified; activity qualified to 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.
NES Personnel:
6-UT, 7-PT, 6-MT, 2-VT-1, 2-VT-3/4 CONAN Personnel:
5-EC-analysts, 4-EC-data collection W Personnel:
4-UT CPRL Personnel:
3-ASME-VT, 6-Snubber-VT
d.
Data Review and Evaluation (70370)(73755)
Records of completed ISI examinations for the below listed examinations were reviewed.
These records were 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; programma.ic deviations were recorded as required; personnel, instruments,'alibration blocks, and NDE materials (penetrants, couplants)
were designated.
23 Ultrasonic'Reports 44 Liquid Penetrant Reports
'5 Magnetic Particle Reports 6.Visual VT-1 Reports 18 Pipe Supports and.Snubber Visual Reports 1 Failed Snubber Engineering Evaluation (2)
The inspecto.
s performed a
sampling review of the TM)
"""
f'nalysis report for 300 SG tubes, 100 tubes from each of three Steam Generators.
The reviews were compared with the applicable procedures and the ASNE BEPV Code in the following areas:
the multichannel eddy current examination equipment has been identified; method of examination has been recorded; and, results are consistent with acceptance criteria.
This report indicated that
tube in SG-A and
tubes in SG-C were unacceptable for continued service.
These 3 tubes were plugged making a total of
SG-A,
SG-B, and
SG-C tubes that have been taken out of service to date.
(3)
During the review of the above report the NRC inspectors noted that there was no apparent program for requiring dual evaluations of EC data, even though dual evaluations of data has become an industry accepted practice.
Discussions with the ISI Project Specialist indicated that the data had been evaluated by two different analysts eventhough there was currently no formal CPS L program requirement for'ual data analysis and that the final report, which will be forwarded to the NRC, would document the procedure used for evaluation of the data.
In addition, the Specialist indicated that a
program for requiring dual evaluation of data and site specific data analyst training and qualification was being pursued with the program expected to be in place in the near future.
T T>>
T f
report for the automated UDRPS ultrasonic examination of the
Reactor Vessel outlet nozzle to shell welds, the nozzles inner radius area, and the nozzle to pipe welds.
The final report had not yet been completely assembled as. the examinations had very
recently been completed.'-
The final report will'e reviewed in me ~e depth during a future inspection.
i All of the examination reports reviewed appeared to contain the required examination information including disposition of indications, if any..
A random sample of current examination results were compared with h',storical examination results.
No major discrepancies were noted during this comparison.
In the areas inspected, violations or deviations were not identified.
Licensee Action on Previously Opened Items (Close)
Unresolved Item 50-400/87-27-01, Special Process Records Storage Requirements.
This item identified the absence of Objective guality Evidence to support the range of temperature and humidity stipulated in the licensee's procedure for maintenance of required ISI records, RMP-006, as meeting the requirements of ANSI N45.2.9,'equirements for Collection, Stor'age and Maintenance of guality Assurance, Records for Nuclear Power Plants, which states, under paragraph 5.4.3, special processed records (such as radiographs, photographs, negatives,
. and microfilm)
which are light-sensitive, pressure sensitive or temperature sensitive shall be packaged and stored as recommended by the manufacturer of these materials.
The licensee has obtained supporting documentation from manufacturers of these products via letter transmittal to the licensee.
The inspectors have reviewed response letters from Kodak, Tracor Westronics, Dupont, Minnesota Minning and Manufacturing (3M),
and Leeds and Northrup relative to their recommendations for storage of these records.'he manufacturers all recommend the storage of this type record be within the constraints of temperature and humidity as established by the licensee.
In addition, the licensee has purchased a special Stat,ic Free cabinet for the storage of data reels and has placed acid free paper betw'een all film and photographs held in storage.
The inspectors conducted a general walk through of the storage facilities and at random verified the addition of the static free cabinet,
.and that acid free paper was inserted between film and photographs.
Also, the inspectors reviewed historical entries to the Temperature And Humidity Log to confirm that the environment was being maintained as stipulated.
Based on the above.stated reviews and observations this item is closed.
(Close)'nspector Followup Item ( IFI) 50-400/88-26-01, Repair Of Primary Side Head Drain For Steam Generators AEB.
This item was established in order to followup on the proposed repair of the drain lines on the bottom head of the three steam generators.
In early August 1988, during a visual inspection of the three ste'am generator
primary side head drains, an accumulation of a residue, appearing to be boric acid crystals, on A and B
steam generators was discovered; no residue was noted on steam generator C. It was concluded that the residue was a result of reactor coolant system. leakage and a repair was necessary.
Westinghouse advised CP8 L that the three Unit
steam generators are the only ones that westinghouse fabricated with this specified primary head drain design.
Accordingly, it was decided to apply the repair to all three steam generators.
The repair of the steam generator drain lines consisted of cutting the existing line below the channel head to remove the socket portion of the line.
Weld buildup was placed on the steam generator channel head around the remaining portion of.the old drain line, using the temper bead weld technique.
A new section of drain line pipe was machined to slip over the remaining section of the old existing drain pipe and welded to the temper bead weld area on the bottom of the channel head.
The NRC inspectors have reviewed PCR-3550, Steam Generator Primary Drain Weepage, which describes the repair and examination requirements and documents the hold point requirements.
The inspectors reviewed welder and NDE personnel qualifications and special welder training documentation.
In addition, NDE examination documentation was reviewed, and applicable WPS's, PgR's, and material certification documentation was reviewed.
The inspectors also reviewed the Title
Code Of Federal Regulations, Part 50.59, safety evaluation conducted by the licensee.
Based on the adequacy of the above documentation reviews, this matter is considered closed.
(Close) IFI 50-400/88-26-02, UT Scanning Techniques.
While NRC inspectors observed the in-progress UT examination of weld No.
1MS-FW-293, during the refueling outage in August 1988, the inspectors became concerned that precise measurements of UT indication signals were not being taken.
Exact measurements are necessary in order to compare current examination data with the data recorded during preservice to ensure that any indications involved are not new indications.
The NRC inspectors discussed this concern with licensee personnel and the licensee agreed to:
re-examine the weld, conduct additional training to insure that examiners discriminate ultrasonic reflectors carefully and use preservice data in order to interpret and evaluate any recorded indications, and have CPEL corporate NDE group monitor future examiner performance.
The NRC inspectors have reviewed examination documentation, examiner training documentation attendance sheets, surveillance reports, personal surveillance log entries, and conducted in field direct observations of UT examinations in progress during this inspection, as noted in paragraph
of this report.
Based on the reviews conducted above and the in field observations, this item is considered close Exit Interview The inspection scope and results were summarized on November 17, 1989, 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 from the licensee.
Unresolved Item 50-400/89-31-01, Visual Inspection Of Snubbers, paragraph 2.c.(4).
Acronyms and Initialisms A
-
Amendment AC
-
Alternating Current ASME
-
American Society of Mechanical Engineers BEPV
-
Boiler and Pressure Vessel Ch.
-
Change CP&L -
Carolina Power and Light CS-
-
-
Distance Amplitude Curve EC
-
Eddy Current IFI
Inspector Followup Item ISI
Inservice Inspection MT
-
Magnetic particle MHz
-
Megahertz NDE
-
Nondestructive Examination NES
-
Nuclear Energy Services No.
-
Number NRC
-
Nuclear Regulatory Commission PQR
-
Procedure Qualification Record PT
-
-
Quality Assurance R
-
Revision RHR
-
-
-
Safety Injection System SS
-
Stainless Steel UDRPS -
Ultrasonic Data Recording and Processing UT
-
Ultrasonic VT
-
Visual W
-
Westinghouse Electric Corporation WPS
-
Welding Procedure Specification System
'