ML19350B420

Final Deficiency Rept Re Area Noted on Reactor Pressure Vessel 2 Which Included Porosity & Linear Indications Approx one-inch in Diameter,Initially Reported 791213.Investigation Revealed That Item Is Not Significant Deficiency

ML19350B420
Person / Time
Site:	05000355
Issue date:	01/27/1981
From:	Martin T Public Service Enterprise Group
To:	Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19350B418	List: ML19350B420
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8103200505
Download: ML19350B420 (2)

Text

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Thomas J. Martin Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 201/430-8316 Vice President Erigineering and Construction January 27, 1981 Mr. Boyce H. Grier, Director U. S. Nuclear Regulatory Commission Of fice of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. Grier:

SURFACE INDICATION - RpV NO. 2 10CFR50.55(e), " POTENTIAL SIGNIFICANT DEFICIENCY" NO. 2 UNIT (50-355)

HOPE CREEK GENERATING STATION On December 13, 1979, a verbal report was made to Region 1, Office of Inspection and Enforcement representative, Mr. R. McGaughy, advising of a potential significant item regarding a surface indication on Reactor Pressure Vessel No. 2. Interim written reports were provided to your office on January 21, 1980, and February 11, 1980. The following final report is provided in response to Mr. R. T. Carlson'~s request of March 6, 1980.

Following sand blasting of Reactor Vessel 2 at the Hope Creek Site in preparation for pai _ .ing, a small area was noted on the Reactor Vessel which included porosity and linear indications of approxi-mately one (1) inch'in diameter. This condition was noted on Bechtel Nonconformance Report No. 565 and was subsequently documented on General Electric Field Deviation Disposition Request KT-2-007.

Grind-out of this indication was initiated on May 5, 1980, and completed on May 14, 1980. Investigation of the indication as well as its removal and the nondestructive examinations were documented on Revision 1 of KT-2-007. Following grind-out to a minor depth, the vessel wall remaining in the area of the grind-out was still 6.558". The initial stress report on the reactor vessel was based upon a required thickness of 6.101" and thus the grind-out did not exceed the stress report calculational basis. Additionally, General 6108200GC(

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.' . S To Mr. Boyce ~2. Grier 2 1/27/81 Electric has notified PSE&G that their investigations indicate that this indication would not have led to an unsafe condition if it had gone undetected. The safety, reliability, design and operating life of the reactor vessel are unaffected by the indication or its removal.

Therefore, this item is not a "significant deficiency" as defined by 10CFR50. 55 (e) and we consider the matter closed.

Very truly yours, cc: Office of Inspection & Enforcement Division of Reactor Construction Insp,ection Washington, D. C.

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