ML20111A401

Updates 850115 Response Re IGSCC Insp During Feb 1985 Refueling Outage.Util Will Reexamine Five Uncracked Safe Ends to Riser Welds.Technique to Inspect Welds Being Developed

ML20111A401
Person / Time
Site:	FitzPatrick
Issue date:	03/05/1985
From:	Corbin McNeil POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
References
RTR-NUREG-1061 JPN-85-17, NUDOCS 8503120487
Download: ML20111A401 (2)

Text

o 123 Mvn Street 4 White Plains, New York 10601

• 014 681.6240

1. b NewYorkPower 2 "A"'"1 1sf Authority " " " ' - " "

March 5, 1985 JPN-85-17 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Inspections for Intergranular Stress Corrosion Cracking during February, 1985 Refuelino Outage

References:

1. NYPA letter, C. A. McNeill to D. B. Vassallo, dated January 15, 1985 (JPN-85-02).

2. PASNY letter, J. P. Bayne to T. A. Ippolito, dated July 31, 1981 (JPN-81-54).

3. NYPA letter, C. A. McNeill, Jr. to D. B. Vassallo, dated October 25, 1984 (JAFP-84-1001).

4. NRC letter. D. B. Vassallo to J. P. Bayne, dated October 24, 1984.

5. NRC Generic Letter 84-11, dated April 19, 1984

6. NYPA letter, J. P. Dayne to D. B. Vassallo, dated June 20, 1984 (JPN-84-40).

Dear Sir:

This letter updates the response we provided in Reference 1. As discussed therein, the Authority has pursued a program of Intergranular Stress Corrosion Cracking (IGSCC) detection and mitigation at the James A. FitzPatrick (JAP) plant. In this program most welds susceptible to IGSCC, as stated in Reference 2, were subjected to Induction Heating Stress Improvement

( Ills I ) . The IllSI program, including the associated ultrasonic inspections, are described in Reference 3.

In Reference 4 the NRC stated that these inspections and related weld overlay repairs were acceptable. It is also our understanding, based on NUREG-1061, that the overlays will be acceptable for at least one to two operating cycles.

In Reference 4 the NRC requested that we provide a detailed plan of weld inspections per Reference 5 for the 1985 outage.

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In Reference 6, and in subsequent telephone conversations, the Authority indicated its conformance to the Reference 5 recommendations regarding inspectors, crack evaluation and repair, and, in general, with the weld selection basis.

Reference 1 detailed IGSCC inspections done to date and scheduled for 1985.

After the NRC reviewed Reference 6, a telephone conversation was held in which W. Hazelton, M. Hum, W. Koo and H. Abelson of the e NRC and J. A. Gray, Jr. of our office discussed the Authority's inspection plans.

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As a result of that discussion, the Authority will reexamine 5 i uncracked safe end to riser welds with a team other than the one I which had inspected these five welds in 1984. In addition, we

. will inspect 6 Core Spray welds out of a total of 9 (not l'

counting 316L welds). Of the 6 welds to be inspected. 4 are new inspections, and 2 are re-inspections. The Authority will also inspect 4 out of 6 24" Residual Heat Removal System welds.

.i Since there are 3 welds per train, this means-that 1 complete j train will be inspected plus a fourth weld from the second train.

l The Authority does not plan performing augmented inservice inspection of Inconel butter on binetallic welds. i

{ It is our understanding that a technique for examining such i

! welds is being developed by the Electric Power Research Institute, and was presented to the NRC early in February of this year. However, it came to our attention too late for us to evaluate its applicability, train personnel in its use and obtain necessary equipment in time for the current outage which j began on February 16.

l The Authority is currently developing a technique to inspect l l these welds. Although it was not ready in time to be used during this outage, we will, however, pursue development for i

future use and will keep the NRC informed of our progress. l 4

1 4 Please contact Mr. J. A. Gray, Jr. if you require any more ,

j information. l

! Very truly yours,

) Corbin A. McNeill, Jr. /*

! Senior Vice President

Nuclear Generation i I  !

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Office of the Resident Inspector i f

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