ML052360301
| ML052360301 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/22/2005 |
| From: | Bezilla M FirstEnergy Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3179, BL-04-001, TAC MC3475 | |
| Download: ML052360301 (4) | |
Text
FENOC FEN
~5501 North State Route 2 FirstEnergy Nuclear Operating Company Oak Harbor. Ohio 43449 Mark B. Bezilla 419-321-7676 Vice President - Nuclear Fax. 419-321-7582 Docket Number 50-346 10 CFR 50.54(f)
License Number NPF-3 Serial Number 3179 August 22, 2005 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001
Subject:
Davis-Besse Nuclear Power Station Supplemental Information Regarding Bulletin 2004-01 Cycle 14 Mid-Cycle Outage Pressurizer Inspection Results (TAC No. MC3475)
Ladies and Gentlemen:
By letter dated May 28, 2004, the NRC issued 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. Item (1)(c) requested Pressurized Water Reactor licensees to submit a description of the Alloy 82/182/600 pressurizer penetration and steam space piping connection program that would be implemented during the next and subsequent refueling outages.
By letter dated July 26, 2004, FirstEnergy Nuclear Operating Company (FENOC) submitted its response for the Davis-Besse Nuclear Power Station (DBNPS). FENOC's response stated that all Alloy 600 pressurizer connections are visually inspected each refueling outage. FENOC's response also stated that DBNPS planned to visually inspect the Alloy 600 connections in the pressurizer steam space during the Cycle 14 Mid-Cycle Outage.Bulletin 2004-01 requested PWR licensees to submit a statement within 60 days of plant restart following the next inspection of Alloy 82/182/600 pressurizer penetrations and steam space connections, describing the as-found conditions and any relevant indications of through-wall leakage.
Docket Number 50-346 License Number NPF-3 Serial Number 3179 Page 2 As noted in NRC Special Inspection 05000346/2005003 (DRS), dated March 23, 2005, all pressurizer Inconnel Alloy 82/182 or Alloy 600 locations were visually inspected, and no indications of boric acid leakage from pressure-retaining components were identified.
The visual inspections were completed in late January 2005, during the Cycle 14 Mid-Cycle Outage. Due to a misinterpretation of the reporting requirements in Bulletin 2004-01, the post-inspection response was not submitted within 60 days as requested.
This oversight has been entered into the FENOC corrective action program.
The following text provides information regarding this supplemental inspection, consistent with the reporting requirements of Bulletin 2004-01, paragraph (2)(a):
Description of the as-found condition of the pressurizer shell The penetration nozzles and steam space piping components were generally free of debris and dirt, and no boric acid deposits were identified. Some minor dirt, rust stains and debris existed on the pressurizer vessel and insulation, but this did not mask or impede the inspection.
Any findings of relevant indications of through-wall leakage No relevant indications of through-wall leakage were found.
Followup NDE performed to characterize flaws in leaking penetrations or steam space piping connections This item is not applicable, because FENOC did not identify any indications of boric acid leaks from pressure-retaining components in the pressurizer.
Summary of all relevant indications found by NDE This item is not applicable, because only visual examinations were performed.
Summary of the disposition of any findings of boric acid This item is not applicable, because FENOC did not identify any indications of boric acid leakage during the pressurizer inspections described above.
Corrective actions taken and/or repairs made as a result of the indications found This item is not applicable, because FENOC did not identify any indications of boric acid leakage during the pressurizer inspections described above.
Docket Number 50-346 License Number NPF-3 Serial Number 3179 Page 3 Should you have any questions or require additional information, please contact Mr.
Henry L. Hegrat, Supervisor - Fleet Licensing, at (330) 315-6944.
The statements contained in this submittal, including its associated enclosures and attachments are true and correct to the best of my knowledge and belief. I am authorized by the FirstEnergy Nuclear Operating Company to make this submittal. I declare under penalty of perjury that the foregoing is true and correct.
Executed on:
45,2-0o By:_______
Mark B. Bezilla, Vice Preside -Nuclear MSH Enclosure cc: J. L. Caldwell, Regional Administrator, NRC Region III W. A. Macon, DB-1 NRC/NRR Project Manager C. S. Thomas, DB-1 NRC Senior Resident Inspector Utility Radiological Safety Board
Docket Number 50-346 License Number NPF-3 Serial Number 3179 Enclosure Page 1 of 1 COMMITMENT LIST The following list identifies those actions committed to by the Davis-Besse Nuclear Power Station, Unit Number 1, (DBNPS) in this document. Any other actions discussed in the submittal represent intended or planned actions by the DBNPS. They are described only for information and are not regulatory commitments. Please notify Henry L. Hegrat, Supervisor
- Licensing (330-315-6944) of any questions regarding this document or associated regulatory commitments.