JAFP-02-0251, In-Vessel Visual Inspection Summary Report 2002 Refuel Outage (Reload 15/Cycle 16)
| ML030060077 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/26/2002 |
| From: | Ted Sullivan Entergy Nuclear Northeast, Entergy Nuclear Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| JAFP-02-0251 | |
| Download: ML030060077 (5) | |
Text
Entergy Nuclear Northeast Entergy Nuclear Operations, Inc "James A Fitzpatrick NPP En P0 Box 110
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Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan Vice President, Operations-JAF December 26, 2002 JAFP-02-0251 United States Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop O-Pl-17 Washington, DC 20555
SUBJECT:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 In-Vessel Visual Inspection Summary Report 2002 Refuel Outage (Reload 15/Cycle 16)
Dear Sir:
This letter and the associated attachment are being submitted to provide the In-Vessel Visual Inspection (IVVI) Summary Report for Refueling Outage 15 for the James A.
Fitzpatrick Nuclear Power Plant (Commercial Service Date: July 28, 1975). The IVVI examinations were conducted inside the reactor pressure vessel (RPV) by General Electric Nuclear Energy (GENE) utilizing personnel certified and qualified to ASME Code Section XI, and the guidelines as outlined in the Boiling Water Reactor Vessel Internals Project's (BWRVIP) BWRVIP-03, Revision 4, Section 2, "General Procedures" and Section 2.5, "Generic Standards for Visual Examination of Reactor Pressure Vessel Internals Components, and Associated Repairs", Sub-section 4.0, "Personnel Training/Experience". Per the requirements of these documents, specific training was provided for all inspection personnel addressing plant specific procedural requirements, core shroud, core spray and jet pump configuration details, previous inspection results, inspection procedures, and any other pertinent information related to the IVVI inspections. provides a summary report for the IVVI examinations conducted during the plant's fall 2002 Refuel Outage (Reload 15/Cycle 16) and their results.
Should you have any questions concerning this report, please direct them to Mr. Andrew Halliday at (315) 349-6055.
Very truly yours, T. A. Sullivan Vice President Operations TAS:GB Enclosure cc:
Regional Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Guy Vissing, Project Manager Project Directorate 1 Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop OWFN 8C2 Washington, DC 20555 Office of the Resident Inspector James A. FitzPatrick Nuclear Power Plant U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 IVVI Summary Report (RO15)
James A. FitzPatrick Nuclear Power Plant Components in Date or Inspection Summarize the Following Information:
BWRVIP Frequency of Method Inspection Results, Repairs, Replacements, Re-inspections Scope Inspection Used Core Shroud Fall 2002 EVT-1 Re-inspected, per BWRVIP-76 Guidelines, accessible areas of Vertical Welds (RO15)
SV2B, SV5B, and SV8A; and Radial Ring Welds SV3A and SV3D. Relevant indications were only noted on the SV5B weld, as follows:
SV5B ID and OD - There appear to be no discemable changes this outage (RO 15) affecting the cracks length from the previous inspection in R014; though one additional indication is noted on the ID CCW side of the weld approximately'1/2" long. This indication is in the vicinity of indications on the opposite side (OD) at the same location. Calculation No. JAF-CALC-NBS-04298 conservatively assumes and evaluates a through-wall condition and thus bounds and dispositions the indications identified in RO-15.
Core Spray Fall 2002 EVT-1 Re-inspected accessible areas of all Loop "A" and "B" creviced and T-box-to-pipe Piping (RO 15) welds; repair clamp welds at Loop "B" downcomer pipe; and rotating sample of pipe elbow upper/lower welds in Loop "A" (at 10 degrees downcomer), per.
BWRVIP-18 Guidelines. No relevant indications noted.
Core Spray Fall 2002 EVT-1 Re-inspected all T-box and end caps to sparger pipe welds at Loops "A", "B', "C",
Sparger (RO 15) and "D". No relevant indications noted.
VT-1 Re-inspected sparger "C" and "D" nozzle welds, and supporting brackets at "A" and "B". No relevant indications noted.
Standby Liquid Fall 2002 EVT-2 Performed Enhanced VT-2 on SLC nozzle-to-safe end weld during RPV System Control (SLC)
(RO 15)
Leakage Test per BWRVIP-27 Guidelines. Test was "Accepted" with no leakage System noted.
Page 1 of 3 d-.
IVVI Summary Report (R015)
James A. FitzPatrick Nuclear Power Plant Components in Date or Inspection Summarize the Following Information:
BWRVIP Frequency of Method Inspection Results, Repairs, Replacements, Re-inspections Scope Inspection Used Jet Pump Fall 2002 EVT-1, Completed inspection of Jet Pumps #5 and #6, and portions of Jet Pumps #19 and (RO 15)
VT-1, and
- 20, per BWRVIP-41 and 48 Guidelines. No relevant indications noted.
VT-3 Jet Pump Fall 2002 VT-i Inspected Jet Pump Beams at JP #5, #6, #19, and at #20, at locations recommended Beams (RO 15) by BWRVIP-41, and by latest industry operating experience. No relevant--:
indications noted.
Control Rod Fall 2002 EVT-1 and Inspected accessible surfaces at 4 Guide Tubes per BWRVIP-47 Guidelines: No Drive (RO 15)
VT-3 relevant indications noted.
(CRD) Guide Tube Dry Tube Fall 2002 VT-i Re-inspected SRM Core Dry Tube 20-17 per GE SIL 409 and GE RICSIL-073 (RO 15)
Guidelines. No relevant indications noted.
Instrument Fall 2002 VT-2 Performed a VT-2 ISI System Leakage Exam Test at 6 instrument nozzles (during Penetrations (RO 15)
RPV System Test) per BWRVIP-49 Guidelines. Test was "Accepted", no leakage noted.
Vessel ID Fall 2002 EVT-1, Inspected by EVT-1/VT-1, Jet Pump Riser Brace attachments (at JP #5/6 and Brackets (RO 15)
VT-1, &
- 19/20); and inspected by EVT-1/VT-3, Feedwater Sparger Bracket Attachments VT-3 (at all 8-locations), per BWRVIP-48 requirements. No relevant indications noted on these examinations.
Fuel Support Fall 2002 VT-3 Inspected accessible areas at four fuel support castings during in-process control Castings (RO 15) rod blade change-out. No relevant indications noted.
Page 2 of 3 IVVI Summary Report (R015)
James A. FitzPatrick Nuclear Power Plant Page 3 of 3 Components in Date or Inspection Summarize the Following Information:
BWRVIP Frequency of Method Inspection Results, Repairs, Replacements, Re-inspections Scope Inspection Used Feedwater Fall 2002 VT-3 Inspected Spargerpipe assembly at 45, 135, 225, and 315 degrees azimuth, sparger Sparger (RO 15) welds and end brackets, per NUREG 0619. No relevant indications noted.
VT-1 Inspected Junction T-box welds and Nozzle Inner Radius (NIR) at 45, 135, 225, and 3 15 degrees azimuth per NUREG 0619. No relevant indications noted.