ML20086C546

Interim Deficiency Rept Re Dye Penetrant Indications on Surface of 67 F Reactor Coolant Nozzle safe-end During Insp of Adjacent Field Weld.Initially Reported on 730722. Indications Ground Out

ML20086C546
Person / Time
Site:	Salem
Issue date:	07/24/1973
From:	Betz J Public Service Enterprise Group
To:	Knuth D US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20086C542	List: ML20086C546
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8311280115
Download: ML20086C546 (2)

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- u6 John F. Betz Fublic Service Electric and Gas Company 80 Park Place Newark, N J. 07101 201/622 7000 Vice President in Charge of Electric Operation July 24, 1973 U. S. Atomic Energy Commission Directorate of Regulatory Operations 7920 Norfolk Avenuo Bethesda, Maryland 20014 Attention of Mr. Donald F. Knuth Director Gentlemen:

NO. 1 REACTOR PRESSURE VESSEL 67o REACTOR COOLANT LOOP N0ZZLE SAFE END SALEM NUCLEAR GENERATING STATION On June 22, 1973, a verbal report was made to the Region I Directorate of Regulatory Operations advising of dye penetrant indications observed on the surface of the 670 reactor coolant nozzle safe end during inspection of.the adjacent field weld. The safe end is on the reactor. coolant piping loop to the No. 14 Steam Generator of No. 1 Unit Reactor Vessel and -is associated with field weld 4-5-1B.

The dye penetrant revealed a series of short unconnected linear indications ranging-from pinpoints to a maximum of approximately .060" - .080" in a band of approxi-mately 1-1/2" wide and 360 around the circumference of the' safe end. The band was located immediately adjacent to the-nozzle shop weld and ran to within 1/2" - 3/4" of the recently.

completed field weld. The amount of dye at the time:of inspection suggested that the condition was very shallow.

Subsequent to the verbal report, we have comple ted the following investigation:

1. Exploratory grinding to .005" depth removed'.some indications..

2. An in-place metallographic examination of selected areas, including remaining. indications,Leonfirmed the. condition as rounded-pits. No cracking or-intergranular attack:was found. ,/

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.- ', 4 U.S. Atomic Energy 7-24-73 Commission 3 Indications were removed by grinding to a maximum depth of .020".

4. Dye penetrant examination of the remaining six nozzles upon which welding has been completed did not reveal any similar condition.

5 Scattered indications were found on two other reactor coolant piping nozzles:

a. Two short unconnected indications in the 316 SS safe end of the 22 nozzle, 2" from the shop transition weld. These were removed with a light polish at negligible depth and checked metallographically,

b. Two indications approximately 0.10" long in the transition weld on the 113 nozzle.

These were identified as mechanical marks and had no metallurgical significance.

On removal of the indications and examination of the 22 0 and 67 nozzle safe ends, it was determined that no repair or further work will be necessary. Howe ve r , we plan to examine the remaining six nozzles, on which no indications were found, metallographically in the same manner as the 220 and 670 nozzles.

An additional dye penetrant and metallographic examination will be made of the I.D. surface of the 67 norzle and one other reactor coolant piping nozzle selected at random to provide further assurance. A current work stoppage at Salem, due to a labor problem, has prevented completion of the latter planned investigation. Inspection to date would sup;7rt a conclusion that no repairs or additional work would be required. No furthe r reports are planned unless subsequent inspections reveal the.t re;: air work will be necessary. The results of this investigation will be available for your inspectors at the Salem site .

Please c ontact us if you have further questions on this subject.

Very truly yours,

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CC Mr. J. P. O'Reilly V

Newark, New Jersey

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