ML20114A776
| ML20114A776 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/15/1985 |
| From: | Corbin McNeil POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| GL-84-11, JPN-85-02, JPN-85-2, NUDOCS 8501280437 | |
| Download: ML20114A776 (3) | |
Text
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FE 123 Main Street White Plains, New York 10601 914 681.6240
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January 15, 1985 JPN-85-02 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 Operating Reactors
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Inspections for IGSCC during February 1985 Refueling Outace
References:
1.
PASNY letter, J.P. Bayne to T.A.
Ippolito, dated July 31, 1981 (JPN-81-54).
2.
NYPA letter, C.A. McNeill Jr.,
to D. B. Vassallo, dated October 25, 1984 (JAFP-84-1001).
i 3.
NRC letter, D. B. Vassallo to J. P. Bayne, dated October 24, 1984.
4.
NRC Generic Letts 84-11, dated April 19, 1984.
i 5.
NYPA le t te r, J. P. Bayne to D.B. Vassallo, dated June 20, 1984 (JPN-84-40)
Dear Sir:
The Power-Authority has been engaged in an aggressive program of detection and mitigation of Intergranular Stress Corrosion Cracking (IGSCC) at the James A. FitzPatrick (JAF) plant.
As part of that program, Induction Heating Stress Improvement (IHSI) was applied to a number of welds in the Reactor Water Recirculation and Residual Heat Removal (RHR) Systems.
The welds selected are susceptible to IGSCC as stated in Reference 1.
The extent of IHSI application and results of the associated ultrasonic examinations are detailed in Reference 2.
L The NRC, in Reference 3, stated that the performance and results of these inspections and the weld overlay repairs were acceptable.
Additionally, it was requested that the Authority provide a detailed plan of our weld inspection activities, per Generic Letter 84-11 (Reference 4), during the 1985 refueling outage.
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4 In Reference 5, and in subsequent telephone conversations, the Power Authority indicated its conformance to the Generic Letter 84-11 opecific recommendations regarding qualification of inspectors, crack evaluation and repair criteria, and, in general, with the recommended basis of weld selection for inspection.
The attached Table details the IGSCC inspections done to date and the inspections and re-inspections scheduled for the 1985 refueling outage.
It should be noted that the combination of post-IHSI inspections performed in March and September / October, 1984, with those scheduled for February, 1985 represent 100% of the large diameter recirculation piping and well over half of the welds in the remaining piping.
As required by Generic Letter 84-11, all unrepaired cracks will be reexamined.
We consider, therefore, that following.the February, 1985 outage, the Authority will have completed the inspections required by Generic Letter 84-11.
Please contact Mr. J. A. Gray, Jr. of my staff if any further information is required.
Very truly yours, Corbin A. McNeil Senior Vice President cc:
Office of the Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 136 Lycoming, NY 13093 Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza Albany, New York 12223
TABLE 1 IGSCC INSPECTIONS Welds inspected Welds Welds Welds scheduled Pipe Total No. Susmeer 1983 inspected inspected Feb. 1985:
System OD of welds (IEB-83-02)
March 1984 Fall. 1984 Re-insp.
'New' insp.
Remarks l
R; circulation 4"
20 7
0 0
2 8
No cracking found to date C circulation 12" 40 16 6
36 2
.0 Reinspections of unrepaired cracked welds R; circulation 22" 16 12 1
15 1
0 Reinspection of one end-cap where an apparent indication had been subsequently re-evaluated as geometric reflection R: circulation 28" 41 21 4
35 4
2 Reinspection of all unrepaired cracked welds 3
LHR 20" 5
4 0
2 1
1 RHR 24" 6
0 0
0 NA 3
Inspections of i
binetallic welds, (inconel buttered) t RWC 6"
2 1
0 0
1 1
'New' inspection on binetallic weld Coro Spray 10" 9
5 0
0 2
3 One half of system replaced with 316L and not counted in total no. of welds 3
i
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