ML052080173
| ML052080173 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/27/2005 |
| From: | Bannister D Omaha Public Power District |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-04-001, LIC-05-0087 | |
| Download: ML052080173 (3) | |
Text
m Omaha Public Power District 444 South 16th Street Mall Omaha NE 68102-2247 July 27,2005 LIC-05-0087 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Reference:
- 1. Docket No. 50-285
- 2. NRC Bulletin 2004-01, "Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors"
- 3. Letter from OPPD (R. L. Phelps) to NRC (Document Control Desk) dated July 27, 2004 (LIC-04-0080)
SUBJECT:
Omaha Public Power District (OPPD) Response to NRC Bulletin 2004-01, Report Due 60 Days After Plant Restart In accordance with NRC Bulletin 2004-01 (Reference 2) and OPPD's commitment of Reference 3, attached is the report due 60 days after plant restart.
If you have additional questions, or require further information, please contact T. C. Matthews at (402) 533-6938. No commitments to the NRC are made in this letter.
Sincerely, Manager - Fort Calhoun Station Attachment -
NRC Bulletin 2004-01, Report Due 60 Days After Plant Restart Employment with Equal Opportunity 4 1 7 1
LIC-05-0087 Attachment Page 1 NRC Bulletin 2004-01 Report Due 60 Days After Plant Restart
LIC-05-0087 Attachment Page 2 OPPD completed its inspection of the Fort Calhoun Station, Unit No. 1 (FCS) pressurizer penetrations and piping connections as required by NRC Bulletin 2004-01 during the Spring 2005 reheling outage (RFO), which ended June 1, 2005. A 100% bare metal visual inspection of all eighty-six (86) pressurizer penetrations was performed in accordance with Bulletin 2004-01 (specifically excluded from Bulletin 2004-01 requirements was the surge nozzle). The information requested by Bulletin 2004-01 follows.
- 1.
Description of the as-found condition of the pressurizer shell.
Asbestos insulation was removed from the bottom shell of the pressurizer in order to assess the condition of the seventy-two (72) heater sleeve nozzles and four (4) level nozzles. No boric acid deposits were found on any of the heater sleeve or level nozzles. However, deposits of an unknown type were found close to several heater sleeve annuli. When the deposits were analyzed, no significant concentrations of boron were found. The deposits would not dissolve in water and it was concluded that the deposits were primarily composed of tightly adhering insulation.
No boric acid deposits were found on the remaining ten (10) pressurizer penetrations. Two (2) of these ten (10) penetrations are j-groove weld thermocouple penetrations, and the remainder are butt weld penetrations. A 100% bare metal visual inspection was performed on all safe end and weld connections in compliance with Bulletin 2004-01.
- 2.
Description of any findings of relevant indications of through-wall leakage.
The inspection did not find any relevant indications of through-wall leakage.
- 3.
Description of follow-up NDE performed to characterize flaws in leaking penetrations or steam space piping connections.
No additional follow-up NDE was required based on the initial eddy current results.
- 4.
Summary of all relevant indications found by NDE.
No relevant indications were found.
- 5.
Summary of the disposition of any findings of boric acid.
No boric acid residue was identified during the inspection of the FCS pressurizer.
- 6.
Description of any corrective actions taken and/or repairs made as a result of the indications found.
No corrective actions or repairs were necessary.
The FCS pressurizer is scheduled for replacement during the 2006 RFO. Penetrations on the new pressurizer are fabricated from type 3 16 stainless steel.