W3F1-2008-0049, Day Report for Reactor Pressure Vessel Head and Pressurizer Inspection/Repair for the Spring 2008 Refueling Outage

Day Report for Reactor Pressure Vessel Head and Pressurizer Inspection/Repair for the Spring 2008 Refueling Outage

ML082100076
Person / Time
Site:	Waterford
Issue date:	07/24/2008
From:	Gaudet T Entergy Nuclear South
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MD4196, W3F1-2008-0049
Download: ML082100076 (6)

Text

Entergy Nuclear South Entergy Operations, Inc.

17265 River Road Killona, LA 70057-3093

%§Enteigy. Tel 504-739-6496 Fax 504-739-6698 tgaudet@entergy.com Timothy J. Gaudet Acting Nuclear Safety Assurance Director Waterford 3 W3F1-2008-0049 July 24, 2008 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555

SUBJECT:

60-Day Report for Waterford Steam Electric Station, Unit 3 Reactor Pressure Vessel Head and Pressurizer Inspection/Repair for the Spring 2008 Refueling Outage Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38

REFERENCES:

1. NRC letter to Entergy dated March 20, 2007, ConfirmatoryAction Letter- Waterford Steam Electric Station, Unit 3 (TAC NO. MD4196)

(CAL No. NRR-07-006)

2. Entergy letter to NRC dated February 21, 2007, Inspection and Mitigation of Alloy 600/82/182 PressurizerButt Welds (CNRO-2007-00005)

3. Entergy letter to NRC dated February 26, 2007, 60-Day Report for Waterford Steam Electric Station, Unit 3 ReactorPressure Vessel Head and PressurizerInspection for the Fall 2006 Refueling Outage (W3F1-2007-0009)

4. Entergy letter to NRC dated July 27, 2004, Response to NRC Bulletin 2004-01 Regarding Inspection of Alloy 82/182/600 Materials Used In PressurizerPenetrationsand Steam Space Piping Connections (W3F1-2004-0058)

Dear Sir or Madam:

On March 20, 2007, NRC transmitted Confirmatory Action Letter CAL No. NRR-07-006 to Entergy to confirm commitments made regarding Alloy 82/182 butt welds in the Waterford Steam Electric Station, Unit 3 (Waterford 3) pressurizer. In Reference 2, Entergy committed to report the results of the mitigation actions taken on the remaining Alloy 82/182 Pressurizer butt welds associated with the pressurizer spray, surge, and relief lines to the NRC within 60 days following startup from the Spring 2008 refueling outage. In Reference 3, Entergy provided inspection-results for the Fall 2006 refueling outage, as required by NRC Order EA-03-009, Reactor Pressure Vessel head inspection requirements, and commitments

W3F1-2008-0049 Page 2 of 3 associated with the bare metal visual (BMV) inspections of the pressurizer penetrations, as stated in Entergy's response to NRC Bulletin 2004-01 (Reference 4).

Waterford 3 resumed operation on June 2, 2008 from the Spring 2008 refueling outage. The results of the RPV head inspection (NRC Order EA-03-009), Bulletin 2004-01 Pressurizer bare metal inspections, and the mitigation actions taken on the remaining Alloy 82/182 Pressurizer butt welds associated with the pressurizer spray, surge, and relief lines 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. In addition, the remaining Alloy 82/182 Pressurizer butt welds had structural weld overlays installed.

This letter contains no additional NRC commitments. If you have any questions or require additional information, please contact Robert Murillo at 504-739-6715.

Sincerely, TJG/RLW/

Attachment:

60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2008 Refueling Outage

W3F1-2008-0049 Page 3 of 3 cc: Mr. Elmo E. Collins, Jr.

Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Louisiana Department of Environmental Quality Office of Environmental Compliance Surveillance Division P. 0. Box 4312 Baton Rouge, LA 70821-4312 American Nuclear Insurers Attn: Library Town Center Suite 300S 2 9 th S. Main Street West Hartford, CT 06107-2445 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter _

1111 Pennsylvania Avenue, NW Washington, DC 20004

0 Attachment To W3FI-2008-0049 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2008 Refueling Outage

Attachment to W3F1-2008-0049 Page 1 of 2 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2008 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, NRC Bulletin 2004-01 and Confirmatory Action Letter CAL No. NRR-07-006 (Reference 1). Entergy performed inspections of the Waterford 3 RPV head and pressurizer during the Spring 2008 Refueling Outage 15 and completed the mitigation actions on the remaining Alloy 82/182 Pressurizer butt welds associated with the pressurizer spray, surge, and relief lines. The RPV head inspections were conducted in accordance with Section IV.C of the Order; the pressurizer inspections were conducted in accordance with Response 1(c) of Entergy's response to Bulletin 2004-01 (Reference 4); and the remaining Alloy 82/182 Pressurizer butt welds had structural weld overlays installed in accordance with Entergy letter CNRO-2007-00005 (Reference 2) and CAL No.-NRR-07-006 (Reference 1). The following provides the results of the RF-15 inspections and repairs.

Table I Summary of Waterford 3 Spring 2006 Refueling Outage Alloy 600 Inspections Inspection Area Inspection Method Extent of Inspection Results BMV Inspection of RPV Head BMV Inspect the RPV head surface 3600 around each BMV performed on 91 CEDM nozzles, 10 ICI nozzles, vent RPV Head penetration for boric acid. line, and general head condition. No boric acid deposits were identified.

[NRC Order] Pressure Retaining Inspect the-CEDM and ICI housings for potential No boric acid deposits were identified from welded Components boric acid leakage. connections.

NDE of CEDM UT/ECT of 91 CEDM Inspect 2" above the J-weld to the blind zone of 91 CEDM nozzles were examined and analyzed from the Nozzles nozzles the CEDM nozzle. ID using Westinghouse UT/ECT probes. No flaws were detected.

[NRC Order and UT of Nozzle Annulus Review interference fit in nozzle annulus above As part of the CEDM ID exams a zero degree UT probe NRC approved (leak path) J-weld for leakage path. was used to establish that there was no leak path Relaxation] (wastage) from the nozzle annuli.

NDE of ICI UT/ECT of ICI Nozzles Inspect 2" above the J-weld to the end of the ICI The 10 ICI nozzles were UT/ECT examined from the ID. A Nozzles nozzle. zero degree UT probe was used to establish that there was no leak path (wastage). No flaws were detected.

[NRC Order]

UT/ECT of ICI Nozzle Perform UT/ECT exam of ICI nozzle face where An automated UT/ECT on the face of the ICI nozzles was Face ID delivered UT/ECT tooling does not provide -performed. No flaws were detected.

inspection coverage.

NDE of Vent Line ECT of wetted surface Perform ECT of entire wetted surface of vent line. The ECT exam of the vent line did not reveal any flaws.

[NRC Order] area

Attachment to W3F1`-2008-0049 Page 2 of 2 60-Day Report for Reactor Vessel Head and Pressurizer Inspection for the Waterford 3 Spring 2008 Refueling Outage Inspection Area Inspection Method Extent of Inspection Results Pressurizer Heater Sleeve N/A All J-welded nozzles on the pressurizer were replaced or Inspection repaired by the end of RF-13.

[Bulletin 2004-01] Side Shell, Steam Space N/A All J-welded nozzles on the pressurizer were replaced or

& Bottom Instrument repaired by the end of RF-13.

Nozzle Pressurizer nozzle to safe Removed insulation and performed bare metal BMV of large bore nozzles and safe ends did not reveal end welds and large bore visual inspection, any leakage.

steam space welds-BMV Pressurizer Pressurizer nozzle to safe 1. Removed insulation and performed bare 1. BMV of nozzle to safe end welds did not reveal any Inspection/Repair end welds metal visual inspection leakage.

[Conirmaory2. Install weld overlays.

[Confirmatory C 2. Completed installation of structural weld overlays over Action Letter CAL the remaining PZR nozzle to Stainless Steel Safe-End No. NRR-07-006 alloy 82/182 butt welds.

and Entergy Letter CNRO-2007- a. PZR to Safety Relief Valve (RC-317A), 6" 00005] b. PZR to Safety Relief Valve (RC-317B), 6"

c. PZR Spare Safety Relief (Capped), 6"

d. PZR to Spray Line, 4"

e. PZR to Surge Line, 12" Note: Additional structural weld overlays were also installed on: (a) Hot Leg 1 to Shutdown Cooling Line, 14"; (b) Hot Leg 2 to Shutdown Cooling Line, 14"; (c)

Hot Leg 1 to Surge Line, 12"; and (d) Hot Leg 1 to Drain, 2" Legend:

BMV = Bare Metal Visual MNSA = Mechanical Nozzle Seal Assembly CEDM = Control Element Drive Mechanism NDE = Non-Destructive Examination ECT = Eddy Current Examination RPV = Reactor Pressure Vessel ICI = Incore Instrument TE = Temperature Element ID = Inside Diameter UT = Ultrasonic Examination