ML051680494
| ML051680494 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 05/31/2005 |
| From: | Rosalyn Jones Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-04-001 | |
| Download: ML051680494 (4) | |
Text
Duke RONALD A JONES LPowere Oconee Nuclear Site Duke Power ONOI VP / 7800 Rochester Hwy.
Seneca, SC 29672 May 31, 2005 864 885 3158 864 885 3564 fax U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852
Subject:
Oconee Nuclear Station, Unit 1 Docket No. 50-269 60-Day Response to NRC Bulletin 2004-001: "Inspection of Alloy 82/182/600 Materials used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors" Pursuant to 10 CFR 50.54(f), this letter and enclosure provide Duke Energy Corporation's (Duke) response to NRC Bulletin 2004-01, Item (2)(a), for the Oconee Nuclear Site Unit 1 (ONS-1). This item requested that Duke provide inspection results within 60-days of plant restart following the next inspection of the Alloy 82/182/600 materials used in the fabrication of pressurizer penetrations and steam space piping connections.
The purpose of this inspection was to detect leakage and adequately characterize potential flaws due to the primary water stress corrosion cracking (PWSCC) associated with components containing these alloys. No component leaking was observed for any of the ONS-1 pressurizer Alloy 82/182/600 components. In addition, the examination results were reviewed by the NRC and documented in NRC Resident's Inspection Report 2005-03. Results of the ONS-1 NRC inspection did not identify any deficiencies, findings or other issues.
If there are any questions regarding this registration, please contact Stephen Newman, Oconee Regulatory Compliance Group, at (864) 885-4388.
Very tru
- urs, R. A.
s President Oconee lear Site ENCLOSURE www.dukepower. corn
U. S. Nuclear Regulatory Commission Page 2 May 31, 2005 cc:
W. D. Travers, Regional Administrator Region II M. C. Shannon, Senior Resident Inspector Oconee Nuclear Site Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation
U. S. Nuclear Regulatory Commission Page 3 May 31, 2005 R. A. Jones, being duly sworn, states that he is Vice President, Oconee Nuclear Site, and that all the statements and maiters set forth herein are true and correct to the best of his knowledge.
R. A. Jon iresident Oconee Nucr ite Subscribed and sworn to before me this 3L day of at t 2005 Notary Public My Commission Expires:
(date)
-- -SEAL
ENCLOSURE Oconee Nuclear Site Response to NRC Bulletin 2004-01, Item (2)(a)
Requested Information As required by Bulletin 2004-01, Item (2)(a): Within 60 days of plant restart following the inspection of the Alloy 82/1821600 pressurizer penetrations and steam space piping connections, submit to the NRC a statement indicating that the inspections described in Duke's previous response to item (1)(c) of this bulletin were completed and a description of the as-found condition of the pressurizer shell, and findings of relevant indications of through-wall leakage, follow-up NDE performed to characterize flaws in leaking penetrations or steam space piping connections, a summary of all relevant indications found by NDE, a summary of the disposition of any findings of boric acid, and any corrective actions taken and/or repairs made as a result of the indications found, Oconee 1 Response: The inspections described in Duke Power's response to NRC Bulletin 2004-01, paragraph (1) (c) were all completed for the ONS1 Pressurizer components during the 1 EOC22 refueling outage between April and May, 2005. No relevant indication of any through-wall leakage was observed from any of the Pressurizer connections examined in response to the 2004-01 Bulletin. Dry boron residue was identified near the Pressurizer thermowell. This area was visually examined by engineering and the residue was determined to be pre-existing, dry residue, and not a relevant indicator of any Alloy 600 component leakage or corrosion concern.
or (b) if the licensee was unable to complete the inspections described in response to item (1)(c) of this bulletin, submit to the NRC summary of the inspections performed, the extent of the inspections, the methods used, a description of the as-found condition of the pressurizer shell, any findings of relevant indications of through-wall leakage, follow-up NDE performed to characterize flaws in leaking penetrations or steam space piping connections, a summary of all relevant indications found by NDE, a summary of the disposition of any findings of boric acid, and any corrective actions taken and/or repairs made as a result of the indications found. In addition, supplement the answer which you provided to item (1)(d) above to explain why the inspections that you completed were adequate for the purpose of maintaining the integrity of your facility's RCPB and for meeting all applicable regulatory requirements which pertain to your facility.
Oconee 1 Response: No response to this paragraph is required, as all the ONS1 Pressurizer component examinations scheduled for 1 EOC22 were performed and no through-wall leakage indications were observed.