W3F1-2013-0026, Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 18 / Refuel 18

Submittal of Owner'S Activity Report Form for Inservice Inspection Performed During Operating Cycle 18 / Refuel 18

ML13112A575
Person / Time
Site:	Waterford
Issue date:	04/18/2013
From:	Fugate C Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
W3F1-2013-0026
Download: ML13112A575 (7)

Text

Entergy Operations, Inc.

17265 River Road

• wýEnte-gy Killona, LA 70057-3093 Tel 504-739-6685 Fax 504-739-6698 cfugate@entergy.com Chester Fugate Licensing Manager Waterford 3 W3F1-2013-0026 April 18, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Submittal of Owner's Activity Report Form for Inservice Inspection Performed During Operating Cycle 18 / Refuel 18 Waterford Steam Electric Station, Unit 3 Docket No. 50-382 License No. NPF-38

Dear Sir or Madam:

Attached is the subject report which covers the Owner's Activity Report Form, OAR-i, for Waterford 3 Operating Cycle 18 / Refuel 18, enclosed as Attachment 1. This report is being submitted in accordance with ASME Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission," which was adopted for use at Waterford 3 commencing with the new Ten-Year Inservice Inspection (ISI) interval on June 1, 2008.

The OAR-1 form is prepared and certified upon completion of each refueling outage and submitted within 90 calendar days of the completion of the refueling outage. This OAR-1 form provides: (1) a listing of items with flaws or relevant conditions that exceeded the acceptance criteria of Division 1 and that required evaluation to determine acceptability for continued service and (2) an abstract for repair/replacement activities that were required due to an item containing a flaw or relevant condition that exceeded Division 1 acceptance criteria. A copy of this letter and the attached report is also being submitted to the office of the Louisiana State Fire Marshall.

There are no new commitments contained in this submittal.

Please contact Chester Fugate, Manager, Licensing at (504) 739-6685 should you have any questions regarding this submittal.

Sincerely, CF/RJP

Attachment:

1. Owner's Activity Report for Inservice Inspection Performed During Operating Cycle 18 / Refuel 18 .

W3F1 -2013-0026 Page 2 cc: Regional Administrator RidsRgn4MailCenter@nrc.gov U. S. Nuclear Regulatory Commission Region IV 1600 E. Lamar Blvd.

Arlington, TX 76011-4511 NRC Senior Resident Inspector Marlone.Davis@nrc.gov Waterford Steam Electric Station Unit 3 Mica.Baquera@nrc.gov P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Kaly.Kalyanam@nrc.gov Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Mr. H. "Butch" Browning, Jr.

Office of the State Fire Marshall 8181 Independence Blvd.

Baton Rouge, LA 70806

ATTACHMENT 1 To W3F1-2013-0026 Owner's Activity Report for Inservice Inspection Performed During Operating Cycle 18/ Refuel 18

CASES OF ASME BOILER AND PRESSURE VESSEL CODE FORM OAR-1 OWNERS ACTIVITY REPORT Report Number -Cycle 18 / Refuel 18 Plant Waterford Steam Electric Station, 17265 River Road, Killona, La. 70057 Unit No. 3 Commercial service date 09/24/1985 Refueling outage no. 18 (If applicable)

Current inspection interval 3rd

( 1', 2 nd, 3V 4"n, other)

Current inspection period 2nd

( 1`,2--, 3'")

Edition and Addenda of Section XI applicable to the inspection plans 2001 Edition, Through 2003 Addenda Date and revision of inspection plans 4/18/12 Revision 001 SEP-ISI-104 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Same as above.

Code Cases used: N-532-4, N-474-1 (If applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of Refuel 18 conform to the requirements of Section XI. (refueling outage number)

Signed -*P U

1 sseT Owner or Owner's Designee, Title Date q!L/ J/1)3 CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Louisiana and employed by HSB CT of Hartford, CT have inspected the items described in this Owner's Activity Report and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in Accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/

replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.

___ g Commissions LA 1184 (A, N, I)

Inspector's Signature National Board, State, Province, and Endorsements Date /"

2

CASES OF ASME BOILER AND PRESSURE VESSEL CODE TABLE 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Category and Item Description Evaluation Description Item Number F-A SIRR-1280 EC-40844 Rigid Restraint for Evaluation signifies no structural integrity compromised F1.10A Safety Injection of the rigid restraint SIRR-1280 by the condition.

System Returned component to the design settings.

F-A SISH-126 EC-40842 Spring Hanger for Evaluation concludes that the as-found condition of the F1.20C Safety Injection spring hanger SISH-126 would have no adverse effects System on the structural integrity of the subject SI piping and its pipe supports, and is within the tolerable range.

F-A MSRR-268 EC-40580 Rigid Restraint for Evaluation concludes that the structural integrity of the F1.30A Main Steam System pipe support MSRR-268 is not adversely affected by the corrosion of the beam flanges 3

CASES OF ASME BOILER AND PRESSURE VESSEL CODE TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Date Repair/Replacement Work Completed Plan Number 1 RC MRCT0001 Pre-Outage work to 12/07/2012 Work Order Control Element Drive assemble, weld, 231621-01 Mechanism to Reactor and inspect, new Vessel Closure Head Control Element Drive Mechanism (CEDM) housings.

1 RC MRCT0001 Assemble and 12/30/2012 Work Order Reactor Vessel Closure Prepare the 231881-04 Head Replacement RVCH for Installation 2 2FW20-12 Install Feed Water 12/29/2012 Work Order Inlet Steam Generator piping on Steam 227153-01

1. 1 Penetration #3 Generator 1 2 2FW20-14 Install Feed Water 12/29/2012 Work Order Inlet Steam Generator piping on Steam 227155-01

1. 2 Penetration #4 Generator 2 1 SG MSGO001 Install Steam 12/12/2012 Work Order Steam Generator #1 Generator 1 227588-01 1 SG MSGO002 Install Steam 12/17/2012 Work Order Steam Generator #2 Generator 2 227589-01 1 SI MVAAA142 A Replace Safety 11/30/2012 Work Order Low Pressure Safety Injection Check 284112-01 Injection Header to Valve (142A)

Reactor Coolant Loop 2B 1 SI MVAAA142 B Replace Safety 11/27/2012 Work Order Low Pressure Safety Injection Check 284113-01 Injection Header to Valve (142B)

Reactor Coolant Loop 1B 4

TABLE 2 (Continued)

ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Class Item Description Description of Date Repair/Replacement Work Completed Plan Number 1 Sl MVAAA143 A Replace Safety 11/27/2012 Work Order Low Pressure Safety Injection Check 284114-01 Injection Header to Valve (143A)

Reactor Coolant Loop 2A 1 SI MVAAA143 B Replace Safety 11/29/2012 Work Order Low Pressure Safety Injection Check 284116-01 Injection Header to Valve (143B)

Reactor Coolant Loop 1A 1 1RC42-1RL1 Reinstall Reactor 12/24/2012 Work Order Loop 1 from Reactor Coolant System 227168-01 Vessel to Steam piping on Steam Generator #1 Generator 1 I1 RC42-2RL2 Reinstall Reactor 12/16/2012 Work Order Loop 1 from Reactor Coolant System 227169-01 Vessel to Steam piping on Steam Generator #2 Generator 2 2 2BD4-2 Install Blowdown 12/20/2012 Work Order Blowdown from Steam piping on Steam 228808-01 Generator #2 Generator 2 2 2BD4-1 Install Blowdown 12/22/2012 Work Order Blowdown from Steam piping on Steam 228807-01 Generator #1 Generator 1 3 CCRR-395 Replace Coupling 12/25/2012 Work Order Pipe Support for Pipe for Rigid Restraint 331276-01 3CC20-3B (Component Cooling Water Dry Tower B Outlet to Heat Exchanger B) 2 2MS40-163 Install Main Steam 12/21/2012 Work Order Main Header from Piping on Steam 227209-01 Steam Generator #1 Generator #1 2 2MS40-165 Install Main Steam 12/21/2012 Work Order Main Header from Piping on Steam 227210-01 Steam Generator #2 Generator #2 5