ML20080L367
| ML20080L367 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/07/1984 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20080L369 | List: |
| References | |
| RTR-NUREG-0313, RTR-NUREG-313 IEB-80-07, IEB-80-7, IEB-81-13, IEB-83-02, IEB-83-2, JPN-84-08, JPN-84-8, NUDOCS 8402160336 | |
| Download: ML20080L367 (2) | |
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-c-February 7, 1984 JPN-84-08 Director of Nuclear Reactor Regulations U.S.
Nuclear Regulatory Commission Washington, DC 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 Inservice Inspection Summary Report - Summer
[
1983 Outage
References:
1.
NYPA letter, J.
P.
Bayne to D.
B.
Vassallo, dated July 7, 1983 (JPN-83-64).
l 2.
NYPA letter, C.
A.
McNeill, Jr. to T.
E.
Murley, dated August 24, 1983 (JAFP-83-0880).
3.
NRC letter, D.
B.
Vassallo to J.
P.
- Bayne, dated September 1, 1983.
Dear Sir:
Attached are two (2) copies of the James A.
FitzPatrick Inservice Summary Report for the Summer, 1983 ettage.
This report covers inspections performed in three general areas:
- 1) pipe supports, pipe weld and other pressure retaining component examinations performed in accordance with the FitzPatrick Inservice Inspection program; 2) the examination of susceptible stainless steel piping for evidence of intergranular stress corrosion cracking in accordance with NUREG 0313, Rev. 1 and IE Bulletin, 83-02;
- 3) examination of the jet pump beams and core spray spargers in accordance with IE Bulletin Nos. 80-07 and 81-13, as well as other in-vessel components.
The results of these inspections were acceptable.
Intergranular stress corrosion cracking was discovered in the control rod drive hydraulic return line, and in the Reactor Recirculation System in one of the end cap welds on the
'A' distribution manifold.
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.tj The control-rod drive hydraulic return line was cut and capped as reported in Reference 1.
The cracking in the recirculation system
. distribution manifold cap.was analyzed for effect on piping structurc1: margin and founa'to be of acceptable size for operation for at least one cycle.
This analysis was reported in Reference 2,
.and found acceptable in your safety evaluation dated September 1, 1983 (Reference 3).
~This report <has been reviewed by the Authority and by the Hartford il Steam Boiler' Inspection and Insurance Company authorized inservice inspector.
The approval of the authorized inspector is shown on
. data _ form NIS-1.
Enclosure'lfto this letter is an acknowledgement of receipt.
'Please sign and return to Mr. J. A. Gray, Jr. of my staff at the
. address shown above.
If you have any questions, please contact Mr.
Gray.
Very?truly yours,
/h. b J..P.'Bayne f
Executive-Vice-President i~
' Nuclear Generation cc:
Resident Inspector-U.S. Nuclear Regulatory Commission P.
O. Box 136 Lycoming, NY 13093 R. W.
Bar ton United Engineers & Constructors, Inc.
30 South 17th Street Post Office Box 8223 Philadelphia, PA 19101 c
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