ML070580437
| ML070580437 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 02/26/2007 |
| From: | Ridgel J Entergy Nuclear South, Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-04-001, W3F1-2007-0009 | |
| Download: ML070580437 (6) | |
Text
a teray t m c2t Entergy Nuclear South Entergy Operations, Inc.
17265 River Road Killona, LA 70057-3093 Tel 504-739-6485 jridgel@entergy~com Jerry A. Ridgel Acting Nuclear Safety Assurance Director Waterford 3 W3F1-2007-0009 February 26, 2007 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
REFERENCES:
60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Fall 2006 Refueling Outage Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38
- 1.
Entergy letter dated July 19, 2005, 60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection for the Spring 2005 Refueling Outage (W3F 1-2005-0045)
- 2.
Entergy letter dated July 27, 2004, Response to NRC Bulletin 2004-01 Regarding Inspection of Alloy 82/182/600 Materials Used In Pressurizer Penetrations and Steam Space Piping Connections (W3F11-2004-0058)
Dear Sir or Madam:
On July 19, 2005 (Reference 1), Entergy provided the results of the bare metal visual (BMV) inspections of the pressurizer penetrations for the spring 2005 refueling outage. In Reference 2, Entergy provided the response to NRC Bulletin 2004-01.
Waterford Steam Electric Station, Unit 3 (Waterford 3) resumed operation on December 27, 2006. The results of both the RPV head Order and Bulletin 2004-01 inspections are summarized in the attachment.
In summary, Entergy did not identify any boric acid leakage or primary water stress corrosion cracking of the reactor vessel head or the pressurizer during the inspections of welded connections.
W3F1-2007-0009 Page 2 of 3 This letter contains no NRC commitments. If you have any questions or require additional information, please contact Ronald L. Williams at 504-739-6255.
Sincerely, JR/RLW/jbh/
Attachment:
60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Fall 2006 Refueling Outage
W3F17-2007-0009 Page 3 of 3 cc:
Dr. Bruce S. Mallett U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 NRC Senior Resident Inspector Waterford 3 P.O. Box 822 Killona, LA 70066-0751 U.S. Nuclear Regulatory Commission Attn: Mr. Mel Fields MS O-7D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway Attn: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn Attn: N.S. Reynolds 1400 L Street, NW Washington, DC 20005-3502 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. O. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 29th S. Main Street West Hartford, CT 06107-2445 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004
Attachment To W3F1-2007-0009 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Fall 2006 Refueling Outage
Attachment to W3F1-2007-0009 Page 1 of 2 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Fall 2006 Refueling Outage Waterford Steam Electric Station, Unit 3 (Waterford 3) is a Combustion Engineering (CE) designed unit with Alloy 600 reactor pressure vessel (RPV) head and pressurizer penetrations which are subject to NRC First Revised Order EA-03-009 and NRC Bulletin 2004-01.
Entergy either complied with the Order or sought relaxation in accordance with the Order (referenced letters contained in Reference 1) and committed to perform NDE per NRC Bulletin 2004-01 (Reference 2). Entergy performed inspections of the Waterford 3 RPV head and pressurizer during the fall 2006 refueling outage 14. The RPV head inspections were conducted in accordance with Section IV.C of the Order, and the pressurizer inspections were conducted in accordance with Response 1(c) of Entergy's response to Bulletin 2004-01 (Reference 2). The following provides the results of the RF-14 inspections.
Table 1 Summary of Waterford 3 Fall 2006 Refueling Outage Alloy 600 Inspections Inspection Area Inspection Method Extent of Inspection Status BMV Inspection RPV Head BMV Inspect the RPV head surface 3600 around BMV performed on 91 CEDM nozzles, 10 ICI of RPV Head each penetration for boric acid.
nozzles, vent line, and general head condition. No boric acid deposits were identified.
[NRC Order]
Pressure Retaining Inspect the CEDM and ICI housings for No boric acid deposits were identified from welded Components potential boric acid leakage.
connections. Minor leak on ICI # 5 Swagelok fitting was addressed by corrective action CR-WF3-2006-03673.
NDE of CEDM UT/ECT of 91 CEDM Inspect 2" above the J-weld to the blind zone 91 CEDM nozzles were examined and analyzed Nozzles nozzles of the CEDM nozzle.
from the ID using Westinghouse UT/ECT probes.
No flaws were detected.
[NRC Order and NRC approved UT of nozzle Annulus Review interference fit in nozzle annulus As part of the CEDM ID exams a zero degree UT Relaxation]
(leak path) above J-weld for leakage path.
probe was used to establish that there was no leak path (wastage) from the nozzle annuli.
NDE of ICI UT/ECT of ICI nozzles Inspect 2" above the J-weld to the end of the The 10 ICI nozzles were UT/ECT examined from Nozzles ICI nozzle.
the ID. No flaws were detected.
[NRC Order]
UT/ECT of ICI Nozzle Perform UT/ECT exam of ICI nozzle face An automated UT/ECT on the face of the ICI Face where ID delivered UT/ECT tooling does not nozzles was performed. No flaws were detected.
provide inspection coverage.
Attachment to W3F1-2007-0009 Page 2 of 2 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Fall 2006 Refueling Outage Inspection Area Inspection Method Extent of Inspection Status NDE of Vent ECT of wetted surface Perform ECT of entire wetted surface of vent The ECT exam of the vent line did not reveal any Line area line.
flaws.
[NRC Order]
Pressurizer Heater Sleeve N/A All J-welded nozzles on the pressurizer were Inspection proactively replaced or repaired by the end of RF-13.
[Bulletin 2004-01]
Side Shell, Steam N/A All J-welded nozzles on the pressurizer were Space & Bottom proactively replaced or repaired by the end of RF-Instrument Nozzle 13.
Pressurizer nozzle to Removed insulation and performed bare metal BMV of large bore nozzles and safe ends did not safe end welds and visual inspection, reveal any leakage.
large bore steam space welds BMV These weld configurations were reviewed in RF-1 3 for future inservice inspection and potential weld overlay in RF-15 (Spring 2008).
Legend:
BMV = Bare Metal Visual CEDM = Control Element Drive Mechanism ECT = Eddy Current Examination ICI = Incore Instrument ID Inside Diameter MNSA = Mechanical Nozzle Seal Assembly NDE = Non-Destructive Examination RPV = Reactor Pressure Vessel TE = Temperature Element UT = Ultrasonic Examination