JAFP-04-0190, In-Vessel Visual Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17)

In-Vessel Visual Inspection Summary Report 2004 Refuel Outage (Reload 16/Cycle 17)

ML043640159
Person / Time
Site:	FitzPatrick
Issue date:	12/15/2004
From:	Ted Sullivan Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
JAFP-04-0190
Download: ML043640159 (6)

Text

Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

James A. Fitzpatrick NPP Entegy P.O. Box 110 Lycoming, NY 13093 Tel 315 349 6024 Fax 315 349 6480 T.A. Sullivan Site Vice President - JAF December 15, 2004 JAFP-04-0190 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

SUBJECT:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 In-Vessel Visual Inspection Summary Report 2004 Refuel Outage (Reload 16/Cicle 17)

Dear Sir:

This letter and the associated attachments are being submitted by Entergy Nuclear Operations, Inc. (ENO) to provide the [n-Vessel Visual Inspection (IVVI) Summary Report for Refuel Outage 16 (RO16) 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 6, Section 2, "General Procedures" and Section 2.5, "Generic Standards for Visual Inspection 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, jet pump and steam dryer configuration details, previous inspection results, inspection procedures, and other pertinent information related to the IVVI inspections.

Attachment I provides a summary report for the IVVI examinations conducted during the plant's fall 2004 Refuel Outage (Reload 16/Cycle 17) and their results. As noted in Attachment 1, some examinations scheduled for RO 16 were deferred to Refuel Outage 17 (RO17). As required by the applicable BWRVIP guidelines, the appropriate technical justification was prepared and documented in Reference 1, listed at the end of Attachment 1.

This letter contains one commitment to the NRC which is summarized in Attachment 2.

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Should you have any questions concerning this report, please direct them to Mr. Andy Halliday at (315) 349-6055.

Very truly yours,

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T. A. Sullivan Site Vice President TAS:GB Attachments cc: Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Patrick D. Milano, Senior Project Manager Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 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

Attachment I to JAFP-04-0190 .I IVVI Summary Report (RO116)

James A. FitzPatrick Nuclear Power Plant Components in Date or Inspection Summarize the Following Information:

BWRVIP and Frequency of Method Inspection Results, Repairs, Replacements, Re-inspections Industry Scope Inspection Used Core Shroud Fall 2004 EVT-I Inspected accessible areas of vertical welds SV2A, SV8C, SV9A, SV9B and (RO 16) SV9C, per BWRVIP-76 guidelines. No relevant indications noted.

Inspected two shroud support gusset plate welds and 12 inches along top side of H9 weld on each side of gussets, per BWRVIP 38 guidelines. No relevant indications noted.

• Vertical weld SV8B and four gusset plate weld exams, scheduled for RO16, were deferred to R017 based on technical justification provided in Reference I per the BWRVIP guidelines.

Core Spray Fall 2004 EVT-I Re-inspected accessible areas of all Loop "A" and "B" creviced and T-box-to-pipe Piping (RO 16) welds; repair clamp welds at Loop "B" downcomer pipe; and rotating sample of pipe elbow upper/lower welds in Loop "A" (at 1700 downcomer), per BWRVIP- 18 guidelines. No relevant indications noted.

Core Spray Fall 2004 VT-I Re-inspected all sparger bracket support welds at "C" and "D" spargers, per-Sparger (R016) BWRVIP-18 guidelines. No relevant indications noted.

Standby Liquid Fall 2004 EVT-2 Performed Enhanced VT-2 on SLC nozzle-to-safe end weld during RPV System Control (SLC) (RO16) Leakage Test per BWRVIP-27 guidelines. Test was "Accepted" with no leakage System noted.

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Attachment 1 to.JAFP-04-0190 IVVI Summary Report (RO116)

James A. FitzPatrick Nuclear Power Plant Components in Date or Inspection Summarize the Following Information:

BWRVIP and Frequency of Method Inspection Results, Repairs, Replacements, Re-inspections Industry Scope Inspection Used Jet Pump Fall 2004 EVT-l Inspected riser welds ("high-priority") at Jet Pumps #1, #2, #3, #4, #17 and #18, (RO16) per BWRVIP-41 guidelines. No relevant indications noted.

EVT-I Inspected diffuser/adapter assembly welds ("high-priority") at Jet Pumps #17 and

1. 18, per BWRVIP-41 guidelines. No relevant indications noted.

VT-I Inspected wedge bearing surfaces (WD- 1) at Jet Pumps #17 and #18, per BWRVIP-41 guidelines. No relevant indications noted.

• Thirty "high priority" ranked weld exams for Jet Pumps #1, #2, #3, #4, #19 and

1. 20, scheduled for RO 16, were deferred to RO 17 based on technical justification provided in Reference I per the BWRVIP guidelines.

Steam Dryer Fall 2004 VT-I and Inspected steam dryer integrity per GE SIL 644 Supplement I ("Steam Dryer and Moisture (RO16) VT-3 Integrity"), and per INPO OE 18796 ("Steam Dryer Hood Crack and Tie Bar Separator Recordable Visual Indications") guidelines. Two relevant indication areas were noted. These indications resulted in expanded scope with additional brushing and evaluations. These indications are in the heat affected zone of welds at eight vibration blocks and at a drain channel. All indications were satisfactorily dispositioned by calculations. Plans are to re-inspect the indications in RO 17. This activity was entered into the FitzPatrick corrective action system. (See Attachment 2 for the commitment to perform this activity.)

EVT-I and Inspected steam dryer hold-down brackets, steam dryer support brackets and VT-3 attachment welds. No relevant indications noted.

VT-3 Inspected steam separator lifting rod eye assemblies, and 25% of shroud head bolts.

No relevant indications noted.

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Attachment I to.JAFP-04-0190 IVVI Summary Report (ROG16)

James A. FitzPatrick Nuclear Power Plant Components in Date or Inspection Summarize the Following Information:

BWRVIP and Frequency of Method Inspection Results, Repairs, Replacements, Re-inspections Industry Scope Inspection Used Core Plate Fall 2004 VT-3 Inspected a total of six core plate plugs at two locations. No relevant indications (RO 16) noted.

Instrument Fall 2004 VT-2 Performed a VT-2 ISI System Leakage Exam Test at six instrument nozzles (during Penetrations (RO 16) RPV System Test) per BWRVIP-49 guidelines. Test was "Accepted" with no leakage noted.

Vessel ID Fall 2004 EVT-I Inspected shroud support gusset plate welds to RPV wall at two locations. No Brackets (RO 16) relevant indications noted.

EVT-1 Inspected all four steam dryer support brackets attachment welds to RPV wall.

No relevant indications noted.

VT-3 Inspected all four steam dryer hold-down brackets attachment welds to RPV top head, with no relevant indications noted.

VT-3 Inspected guide rod and bracket attachment welds to RPV wall at 1800, with no relevant indications noted.

Top Guide

• Two top guide hold-down assembly weld exams, scheduled for RO 16, were deferred to R017 based on technical justification provided in Reference I per the BWRVIP guidelines.

Reference 1: JAF-RPT-04-00476, Rev. 0, BWRVIP Program - Technical Justification RO16, dated 12/8/04.

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Attachment 2 to JAFP-04-0190 IVVI Summary Report (RO16)

James A. FitzPatrick Nuclear Power Plant The following table identifies those actions committed to by Entergy Nuclear Operations, Inc. (ENO) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.

SUMMARY

OF REGULATORY COMMITMENTS Commitment Description Completion Schedule The relevant indications on the steam JAFP-04-0190-01 dryer (identified in Attachment 1) will Refuel Outage 17 be re-inspected.

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