IR 05000272/1979024
| ML18081A475 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/20/1979 |
| From: | Sanders W, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18081A473 | List: |
| References | |
| 50-272-79-24, NUDOCS 7911050030 | |
| Download: ML18081A475 (5) | |
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Report No. 50-272/79-24 Docket No. 50-272 U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
License No. OPR-70
Priority ---------
Category _c _____ _
Licensee:
Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101 Facility Name:
Salem Nuclear Generating Station, Unit 1 Inspection at :
Hancocks Bridge, New Jers~y Inspection conducted:
August 7-9, 1979 Inspectors:
4/.~ ~du-s/
W. F. Sanders, Reactor Inspector 4z 1.a, 1 r 7.2___
date signed
_/
date signed Approved by:
Inspection Summary:
date signed
'l/Ml1r Tripp, CHief, Engineering Support Section '
date signed 1, RC&ES Branch Jnspection on August 7-9, 1979 (Report No. 50-272/79-24)
Areas Inspected:
Routine, unannounced inspection by one regional based inspector of the quality related activities associated with the inspection requirements of IE Bulletin 79-1 The inspection consisted of an examination of radiography film, personnel qualification records of the NOE examiner and welders, NOE procedures, welding procedures and post weld heat treat procedures, and calibra-tion of equipmen The inspection involved 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> at the site by one NRC regional inspecto Results:
Of the one area inspected, no items of noncompliance were identifie Region I Form 12 (Rev. Apri 1 77)
DETAILS Persons.Contacted Public Service Electric and Gas Company
- H. J. Mtdura, Plant Manager
- S. LaBruna, Maintenance Engineer
- L. F. Lake, Maintenance Department
- M. F. Metcalf, Quality Assurance Engineer
- J. L. Stillman, Station Quality Assurance Engineer
- W. P. Treston, Resident Quality Assurance Engineer Catalytic Incorporated
- J. Wanner, Quality Assurance Supervisor
- p. Lindale, Quality Control Inspection C. Perez, Field Welding Engineer General This inspection was made to examine and inspect the quality related activities tn progress that respond to the requirements of IE Bulletin 79-1 The tnspection consisted of a review of procedures, procedure qualifications, personnel qualtfi'cations, review of x-ray film, and randomly selected tnspection record No items of noncompliance were identifie.
Radiography Procedures A review was made of the Catalytic Incorporated procedure CI-QAP-712.7-RT, 11Radiography Inspection of Nuclear Components 11 to determine if the require-ments of IE Bulletin No. 79-13 had been met for the required actions. It was noted that there was a difference in the tables used for the selection of penetrameters required by the bulletin and the tables actually used for the selection *. The inspector was informed by the licensee representative tflat tfle penetrameter selection was made from the Table T272 of ASME Section V, Article 2, in lieu of Table NC 5111.1 of ASME Section III, Subsection NC, which was spectfied in the bulleti In discussing this with the licensee representative, the inspector was informed that the differences had been noted and a deci'sion had been made to use Table T272, Sectiori V, tnstead of that required by the bulletin, and the decision had been based on the rationale that this table was specifically designated for the double wall radi.ography technique where as Table No. 5lll. l is designated for
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single wall material thickness. After reviewing the possible differences in the two charts and reviewing the radiograph quality and visable image of the penetrametic outline and 2T penetrameter hole size, it appeared that the intent of the bulletin regarding the radiography sensitivity had been me No item of noncompliance was identifie.
Review of Radiographs The review of radiographs was made by randomly selecting radiograph film of the nozzle and elbows on the No. 11 and No. 13 steam generator and film from the x-ray of four welds in the designated high stress points of the feedwater piping syste The inspector noted that the radiograph procedure employed for this program was a double wall technique, using Iridium-192, KodaR M film, and a required 2T sensitivity. The film reviewed did exhibit the required essential hole and outline of the penetrameter and had the required radiographic quality to make meaningful interpreta,t~ons. The films reviewed are listed:
No. 13 SG, Nozzle to Elbow - Final RT of New Weld No. 13 SG, El bow to Pipe - Final RT of New Weld No. 11 SG, Elbow to Pipe - Final RT of New Weld No. 13 Steam Generator Weld No. 14 - Existing Wel No. 13 Steam Generator Weld No. 15 - Existing Wel No. 13 Steam Generator Weld No. 16 - Existing Wel No. 13 Steam Generator Weld No. 17 - Existing Wel No. 11 Steam Generator Weld No. 7 - Existing Wel No. 11 Steam Generator Weld No. 15 - Existing Wel No items of noncompliance were identifie Personnel Qualification The qualification records were selected for examiners or inspectors in the following positions for examination:
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_ _) Level II, Radiography Level II, Welding Inspector Level II, Dye Penetrant Level II, Welding Inspector The inspector audited the qualification records of one examiner in each of the above categories to determine compliance with the requirements of SNT-TC-lA, ANSI 45.2.6, and the contractor procedure CI-QAP-712-2, 11Training and Qualification of RT Personnel.
An inspection was made of the certifica-tions in the discipline in which the individual was trained, the resume of experience, level of certification and the date certifie T~e inspect~r noted tflat the physical examination records were current and included visual acuity and color vision test No items of noncompliance were identified.
Welding An inspection was made of the weld joints and the related weld procedures used to weld the nozzle to reducer and the reducer to pip Procedure - SP-420-D(N)lll, Revision l Procedure - M-13-Al-GTAW, Root of Weld with EB Insert Procedure - M-l3-A2-SMAW, For Butt Weld and Remainder of Groove The procedures and the related procedure qualification records were examined for essential variables and general compliance with requirements of ASME Sectton I The weld performance qualifications were examined for three welders on a random selection basis for compliance with the requirements of ASME Section I No. l. Welder Symbol F.136, Specification M-13-Al and M-13-A2 G6 No. 2, Welder Symbol F.80, Specification M-13-Al and M-13-A2 G6 No. 3, Welder Symbol F.147, Specification M-13-Al and M-13-A2 G6 No items of noncompliance were identifie aJ...- *.**
5 Post Weld Heat Treat An inspection was made of post weld heat treat (PWHT) performed on the feedwater nozzle reducer to pipe on the No. 13 steam generator. The stress relieving temperature of 11250 + 250F with a temperature increase spread of 50°F between monitored points were shown to have been attained by a sign
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off on the process record; however, a review of the recorder charts to determi'ne if the thermal gradients on temperature increase and decrease had not been verified by the contractor or licensee representatives at the time of this tnspectio The inspector was informed that this would be don Further tnquiri'es were made regarding the calibration of the equipment used to control and record the temperature The inspector was informed that the equipment was bench calibrated at the contractors laboratory and sent to the site. The records on site did not reference the calibration to known tra,cea,ble standards or error accurac The record available gave absolute values. The inspector was informed that the calibration records had been on site, but had become misplaced and that new copies would be sent to the stte for review by the resident inspecto Subsequent to the inspection the licensee obtained calibration certificate and conformance records which were reviewed by the resident fospecto This matter is considered resolve Exit Interview At the conclusion of tfte inspection on August 9, 1979, a meeting was held at the plant site, witfi representatives of the licensee. The inspector summarized the results of the inspection described in this report.