IR 05000272/1982030
| ML20028D300 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/20/1982 |
| From: | Durr J, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028D298 | List: |
| References | |
| 50-272-82-30, NUDOCS 8301170300 | |
| Download: ML20028D300 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION Region I Report No. 50-272/82-30 Docket No. 50-272 License No. DPR-70 Priority Category C
Licensee:
Public Service Electric and Gas Company P. O. Box 2360 Hancock's Bridge, New Jersey 08038 Facility Name:
Salem Nuclear Generating Station, Unit 1 Inspection At:
Hancock's Bridge, New Jersey Inspection Conducted:
November 8-12, 1982 Inspectors:
[
/2/28/M R. A. McBrearty, Reactor [/nspector date signed date signed Approved By:
/ bow j sJz,/fs_
l g P. Durr, Chief, Materials and Processes dat'e (igned
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Inspection Summary:
Inspection Conducted on November 8_-11,1982 (Report No. 50-272/82-30)
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Areas Inspected:
Routine, unannounced inspection of inservice inspection activities including observation of NDE in progress, review of procedures, program and data; and review of data and procedures associated with eddy current examination of steam generator tubes.
The inspection involved 34
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hours onsite by one regional based inspector.
Results: No violations were identified.
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8301170300 830103 i
PDR ADOCK 05000272 O
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DETAILS I.
Persons Contacted Public Service Electric and Gas Company (PSE&G)
- R. F. Brandt, Nuclear Plant Services Engineer J. Driscoll, Assistant General Manager, Salem Operations
- R. T. Grif fith Sr., Sr. Staf f Engineer, QA
- L. F. Lake, ISI Engineer
- H. J. Midura, General Manager, Salem Operations W. Treston, ISI Supervisor Southwest Research Institute (SwRI)
- W. M. Howell, Inspection Engineer
- R. L. Turner, Team Supervisor NRC Personnel
- R. J. Summers, Resident Reactor Inspector 2.
Inservice Inspection Activities a.
Program Review The examination plan for the 1982 inservice examination of Salem Generating Station, Unit 1, was reviewed to ascertain compliance with the ASME Code,Section XI, 1974 Edition, and the facility technical specification. The facility commenced commercial opera-tion on June 30, 1977, therefore, the first ten year inspection interval will end on June 30, 1987.
In accordance with IWA-2400 of Section XI, the interval may be extended by as much as one year to permit inspections to be concurrent with plant outages.
The items listed for examination during the current outage agreed with code requirements with respect to type of examination and extent of coverage.
Records were available which indicated the
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status of scheduled examinations, and the licensee stated that the ISI contractor, SwRI, maintains a computer printout of the ten year program status which is updated after each outage.
No violations were identified.
b.
Review of NDE Procedures The inspector reviewed selected NDE procedures to ascertain compli-ance with the applicable edition of the ASME Code,Section XI, regulatory requirements and licensee commitments. Additionally the procedures were reviewed for technic il adequacy.
The following were included in the inspector's review.
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SwRI-NDT-600-15, Revision 49, " Manual Ultrasonic Examination of
Pressure Vessel Welds" SwRI-NDT-700-6, Revision 11, ' Mechanical Ultrasonic Examination
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of Ferritic Vessels 2h Inches or Greater in Thickness" SwRI-NDT-800-36, Revision 26, " Manual Ultrasonic Examination of
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Thin Wall Piping Welds" Regulatory Guide (R.G.) 1.150 is referenced by procedure 700-G Revision 11 which indicates that SwRI accepts the provisions of the R. G. without exception. The licensee representative stated that a position paper, describing the SwRI official position regarding implementation of R. G. 1.150, was available and provided the inspector with a copy.
The inspector's review of the document entitled " Appendix E - Southwest Research Institute's Implementation of Regulatory Guide 1.150 Requirements" indicates that SwRI will not meet fully the requirements of the R. G.
The areas where compliance is incomplete are related to beam angles used to scan welds and to flaw sizing and appear to be associated with equipment limitations.
The inspector advised the licensee representative on November 24, 1982 by telephone that the above is considered unresolved pending clarification of the SwRI position regarding use of the R. G.
(82-30-01).
Procedure 800-36 Revision 26 requires the use of machined notches for establishing examination sensitivity of the ultrasonic system.
The 1974 ASME Section XI requires the use of drilled holes for that purpose.
This is further discussed in Section 2.c of this report.
c.
Observations of NDE in Progress The inspector observed the ultrasonic examination of pipe to elbow weld number 8-RH-2173-6, a class 2 weld in the 8" diameter residual heat removal system.
The observation was made to ascertain compli-ance with program requirements, the applicable NDE procedure and with personnel qualification and certification requirements.
l The inspector noted that the examination was done using a
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l diameter, 2.25 MHz transducer calibrated on machined notches (10"4 of thickness in depth) in calibration block 8-SS-40-330-44-SAM. A Sonic Instruments, Inc. Mark I instrument was used by two technicians certified as UT Level II and UT Level I respectively.
Records indicated that the individuals were properly certified in accordance with SNT-TC-1A, the governing document.
During the course of the examination indications were observed on the cathode ray tube, but were not recorded because their amplitude was below the recording level (50*s of DAC) established by SwRI-NDT-800-36, Revision 26, the governing procedure.
It is left
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to the examiner's judgement whether indictier.
less than 50% of DAC should be recorded.
The inspector questioned the calibration technique using notches rather than the code required drilled holes.
Calibration based on drilled holes has been found to result in a more sensitive test than is produced by notch calibration techniques.
Mr. S. Walker, SwRI Level III, was contacted by telephone from the site, and he discussed SwRI comparison data based on comparisons made from 2" and 2 " pipe using a 55 angle beam dual transducer.
The inspector asked for data based on the comparison of notches and holes in larger diameter piping and with 45 angle beam single transducers which will more closely simulate the equipment used to perform examinations at the site.
The onsite examination observed by the inspector involved a 45 angle beam transducer on 8" diameter piping. This item is considered unresolved pending the availability of the requested information and subsequent NRC review of the data.
(272/82-30-02)
No violations were identified.
d.
Review of NDE Data Data associated with the ultrasonic examination of weld number 12-STG-24, a transition weld in steam generator number 12 was reviewed. The weld is 553" long and was completely examined in accordance with procedure SwRI-NDT-600-15, Revision 49. The examination was done from both sides of the weld using 2.25 MHz, 45 and 60 shear wave, and 0 longitudinal beam. The equipment sensitivity was established from drilled holes and machined nutches.
One indication was detected using the 0 transducer, and was found to be acceptable when it was evaluated to the acceptance standards of ASME Section III, NC 5330.
The examination and evaluation was found to meet the applicable ASME code and regulatory requirements.
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No violations were identified.
3.
Eddy Current Examination of Steam Generator Tubes The inspector reviewed data and the examination procedure associated with the eddy current examination of steam generator tubes. The examinations were done by Westinghouse Electric Corporation personnel during the current refueling outage, and were completed at the time of this in-spection.
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Approximately 1450 tubes in each of the four steam generators were examined and five tubes were found defective and to require removal from service by plugging. Other tubes were found to exhibit indications and were classified as degraded in accordance with the facility technical specification. The defective tubes are as follows:
Steam Generator Row Column
- 12
42
67
81
- 14
50
53 No violations were identified.
4.
Unresolved Items
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Unresolved items are matters about which more information is required to ascertain whether they are acceptable items, violations or deviations.
Unresolved items identified during this inspection are discussed in paragraph 2.b and 2.c.
5.
Exit Interview The inspector met with the licensee representatives denoted in paragraph 1 at the conclusion of the inspection on November 12, 1982. The inspector summarized the purpose, the scope and the findings of the inspection.
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