ML18078B000
| ML18078B000 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/05/1979 |
| From: | Martin T Public Service Enterprise Group |
| To: | Grier G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML18078A996 | List: |
| References | |
| NUDOCS 7903140083 | |
| Download: ML18078B000 (2) | |
Text
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rhornas J. Martin lice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-8316
- ngineering and Construction Mr. Boyce H. Grier, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 February 5, 1979
Dear Mr. *Grier:
NRC INSPECTION POST WELD HEAT NO. 2 UNIT
'31/ /77.... z.(,
REPORT 50-~/~
TREATMENT -
NUCLEAR PIPING SALEM NUCLEAR GENERATING STATION EF:
- 1) Letter of May 9, 1978, T. J. Martin of PSE&G to B. H. Grier of NRC
- 2) Letter of November 20, 1978, T. J. Martin of PSE&G to B. H. Grier of NRC We have reviewed the report of your inspection transmitted with your letter dated June 27, 1978, which was received on June 29, 1978.
The following information is provided as a response to your report:
The subject report identified certain areas where the heat treat-ment of some welded joints at Salem was not in full accord with the requirements of ANSI B31.7.
The main discrepancy was in the heating and cooling rates of some joints where the wall thickness exceeded one inch.
Reference 1 detailed what steps PSE&G would take to conform to B31.7 and to demonstrate the integrity of non-conforming welded joints.
This consisted of a revision to our field procedures, a review of heat treatment records and stress calculations, NDE of sample joints and a heat treatment test.
Reference 2 summarized the results of this testing and notified the NRC of the availability of a test report.
Meetings were held at Salem on December 19, 1978 and January 4, 1979 between the NRC and PSE&G to review the test report and the post weld heat treatment problem.
As a result of these meetings, dditional information has been generated and is included in a evised report.
This report shows that:
7 90 s 14 o og~
Mr. B. 2/5/79
- 2.
- 3.
Radiographic, ultrasonic, and magnetic particle testing and acoustic monitoring detected no defects related to the heat treatment in three field welded joints and a test pipe.
There were no apparent differences in the material properties of samples taken from heat treated and non-heat treated areas of the test pipe.
Although a tensile specimen of a shop weld from the test pipe had an ultimate strength of 67,500 lbs/in2, calcula-tions based on this valuB show that design stresses are below 25% of combined allowable stresses in the penetration area as committed to in the Salem FSAR.
In fact, design stresses for the entire main steam system are significantly lower than that allowed by code, ranging from 3% to 35% of the combined allowa_ble stress.
In view of this exhaustive analysis, it is the position of PSE&G that no safety problem exists with the nuclear piping and that the post weld heat treatment problem identified in the subject report be considered resolved.
A copy of the complete report will be available for review by the NRC on February 6, l979 in Newark, New Jersey.
Very truly yours,