ML20078B073
| ML20078B073 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 01/20/1995 |
| From: | William Cahill POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-94-03, GL-94-3, NUDOCS 9501250255 | |
| Download: ML20078B073 (6) | |
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123 Main Street Who Plains, New York 10601 914 681.6200 1
~ #> NewYorkPower 4# Authority January 20,1995 JPN-95-001 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1 137 Washington, DC 20555
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Rote _Shtoud_ Inspection Resulla
References:
- 1. NRC letter, "Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors (Generic Letter 94-03)," dated July 25,1994.
- 2. NYPA letter, W. J. Cahill, Jr. to NRC (JPN-94-053), " Request for NRC Approval of the FitzPatrick Core Shroud Repair," dated October 21,1994.
Dear Sir:
This letter transmits the results of the core shroud inspections performed during the current refueling outage at the James A. FitzPatrick Nuclear Power Plant. The submittal confonns with reporting requirement No. 3 in Generic Letter 94-03 (Reference 1).
The core shroud inspection results are presented in Attachment 1. The scope of the inspections performed exceeds that described in the inspection plan submitted to the NRC (Reference 2, Attachment 2). As shown in Attachment 1, the relevant indications detected are limited to minor intermittent planar flaws in the weld above and below the top guide support ring (welds H2 and H3). provides the results of the top guide and core plate inspections that were perfonned in response to a General Electric Service Information Letter, dated November 22, 1994, advising of cracking observed in the same reactor components of a foreign plant.
9501250255 950120
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If you have any questions, please contact Ms. C. D. Faison.
Very truly yours, William J. Ca ill, Jr.
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Chief Nuclear Officer Nuclear Generation STATE OF NEW YORK COUNTY OF WESTCHESTER Subscribed and swom to before me
-this aO day of h0AMa^tp 1995.
10rubau Og Jaggau Notary Public ggAgN,N_TAGG_ ART, e 2$$b$tTilt.
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Enclosure:
Attachment 1, Core Shroud Inspection Results., Top Guide and Core Plate Inspection Results.
cc:
Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Eugene Carpenter, Project Manager Project Directorate 1-1 Division of Reactor Projects - I/II U.S. Nuclear Regulatory Commission Mail Stop 14 B2 Washington, DC 20555 Office of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 I
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4 ATTACHMENT 1 Core Shroud Inspection Results James A. FitzPatrick Nuclear Power Plant
'T WELD I. D.
INSPECTION TOTAL AREA INSPECTED RESULTS METHOD d
H2 UT 82% of total weld length.
Intermittent planar flaws less than 0.75 inches deep.
Approximately 35 inches aggregate length i
H3 UT 82% of total weld length.
Two small planar flaws. 1.42 inches aggregate length.
H6a UT 58% of total weld length.
No relevant indications.
H6b UT 61% of total weld length.
No relevant indications.
H9 EVT-1 Two inches on each side of the No relevant indications.
ten gusset plates.
Approximately 40 inches aggregate length.
i Gusset EVT-1 Accessible welds on both sides No relevant indications.
plate welds of the ten gusset plates.
Approximately 463 inches aggregate length.
Page 1 of 3 i
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ATTACHMENT 1 (Continued)
Core Shroud Inspection Results James A. FitzPatrick Nuclear Power Plant WELD 1. D.
INSPECTION TOTAL AREA INSPECTED RESULTS METHOD SV2a EVT-1
- 37% of total weld length.
No relevant indications.
SV2b EVT-1
- 37% of total weld length.
No relevant indications.
SV3a EVT-1
- 100% of total weld length.
No relevant indications.
SV3b EVT-1
- 100% of total weld length.
No relevant indications.
SV3c EVT-1
- 100% of total weld length.
No relevant indications.
SV3d EVT-1
- 100% of total weld length.
No relevant indications.
SV3e EVT-1
- 100% of total weld length.
No relevant indications.
SV3f EVT-1
- 100% of total weld length.
No relevant indications.
- The EVT-1 examinations of the SV2 and SV3 welds were performed from the outside diameter of the shroud.
Page 2 of 3
m ATTACHMENT 1 (Continued) l l
Core Shroud Inspection Results James A. FitzPatrick Nuclear Power Plant WELD NO.
INSPECTION TOTAL AREA INSPECTED RESULTS l
METHOD SV4a UT 17% of total weld length.
No relevant indications.
SV4b UT 17% of total weld length.
No relevant indications.
SV5a UT 6% of total weld length.
No relevant indications.
SV5b UT 6% of total weld length.
No relevant indications.
SV8b EVT-1
- 100% of total weld length.
No relevant indications.
Notes: H2, H3, H6a, H6b, and H9 are circumferential welds. The SV2, SV4, SV5, and SV8 welds are vertical welds. The SV3 welds are radial welds. See Drawing No. FV-26B submitted with Reference 2 for weld locations.
- Performed from the outside diameter of the shroud.
Page 3 of 3
.N ATTACHMENT 2 Top Guide and Core Plate inspection Results James A. FitzPatrick Nuclear Power Plant AREA INSPECTION TOTAL AREA INSPECTED RESULTS METHOD Top Guide Wedges VT-3 100% of wedges (24 wedges)
Acceptable Top Guide Hold Down Bolts VT-3 100% of bolts.
Acceptable Top Guide Ring Weld EVT-1 30% of total weld length.
Acceptable Top Guide Hold Down Latch Bolts VT-3 100% of bolts.
Acceptable Top Guide Hold Down Plate Welds EVT-1 None inaccessible Core Support Plate Studs VT-3 18 studs out of a total of 72.
Acceptable i
m.
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