ML19031C039

03/02/1977 Letter Supplementary Response to IE Circular 76-06 on Stress Corrosion Cracks in Stagnant, Low Pressure Stainless Piping Containing Boric Acid Solution at Pwr'S

ML19031C039
Person / Time
Site:	Salem
Issue date:	03/02/1977
From:	Schwalje E Public Service Electric & Gas Co
To:	O'Reilly J NRC/IE, NRC Region 1
References
IEC-76-006
Download: ML19031C039 (2)

Text

Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/622-7000 March 2, 1977 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement*

Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. O'Reilly:

IE CIRCULAR 76-06 STRESS CORROSION CRACKS IN STAGNANT, LOW PRESSURE STAINLESS PIPING CONTAINING BORIC ACID-SOLUTION AT PWR'S -

SUPPLEMENTAL REPORT NO. 1 UNIT SALEM NUCLEAR GENERATING STATION Pursuant to the subject circular and our initial response of December 23, 1976, the following supplemental report is hereby submitted for your information.

Examination of stagnant low pressure stainless steel piping required by NRC IE Circular 76-06 will be performed as part of the First Inservice Inspection Program and in accordance with Section XI of the ASME Boiler and Pressure Vessel Code, 1974 Edition through the Summer 1975 Addenda as amended by the Program Plan. The Program Plan is currently in preparation but amendments and exceptions to the Code have been reported in a letter of 2-28-76 to the Director of Nuclear Reactor Regulation, USNRC.

The Plan itself will be completed at least 60 days prior to the first scheduled inspection.

The first Inservice Inspection Program will be for the first ten.

year inspection interval. 100% of the nuclear class piping, including stagnant and low pressure portions of the Safety Injection, Containment Spray, Residual Heat Removal and Chemical and Volume Control systems, will be visually examined during each inspection period (three and one-third years) . Volumetric *(ultrasonic) examination will be performed on portions of the Safety Injection,

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.e Mr. J. P. O'Reilly, March 2, 1977 Residual Heat Removal and eve Systems, including some stagnant sections of these systems. Examinations will commence during the first scheduled outage, tentatively scheduleQ for September 10, 1977, at which time approximately 33% of the nuclear-piping and components will be visually examined, and approximately 10-20% of the welds covered by the Plan will be ultrasonically examined. The extent and location of piping to be examined is described in the Inservice Inspection Boundary Diagrams.

In addition to the preceding examinations, contained fluid in critical systems will be sampled periodically and analyzed for chloride and oxygen content as stated in the Salem Sampling Schedule PD 3.8.020. Significant flaw indications found by ultrasonic examinations will also be examined radiographically when conditions permit.

Adverse findings will be reported promptly to the NRC Region 1 Office and a summary report will be submitted on the aforementioned outage.

Very truly yours,

// /1 \

,Q.)'\j_/2~~ .

E. N (

• Schwal}Z

• Manager of Quality Assurance Engineering and Construction Department CC NRC Off ice of Inspection & Enforcement Division of Reactor Inspection Programs Washington, D.C. 20555