ML18199A104: Difference between revisions

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{{Adams
#REDIRECT [[NL-18-049, 2018 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements]]
| number = ML18199A104
| issue date = 07/10/2018
| title = 2018 Form OAR-1 Owners Activity Report for Inservice Inspection and Repairs and Replacements
| author name = Vitale A J
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000247
| license number = DPR-046
| contact person =
| case reference number = NL-18-049
| document type = Inservice/Preservice Inspection and Test Report, Letter
| page count = 4
}}
 
=Text=
{{#Wiki_filter:* ~*Entergx NL-18-049 July 10, 2018 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11545 Rockville Pike, TWFN-2 F1 Rockville, MD 20852-2738 Entergy Nuclear Operations, Inc. Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 254 6700 Anthony J. Vitale Site* Vice President
 
==Subject:==
2018 Form OAR-1 Owners Activity Report for lnservice Inspection and Repairs and Replacements at Indian Point Unit No. 2 Indian Point Nuclear Generating Unit No. 2 Docket No. 50-247 License No. DPR-46
 
==Dear Sir or Madam:==
In accordance with ASME Section XI, Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission," Indian Point Unit No. 2 herein submits the 2018 "Form OAR-1 Owners Activity Report." This report describes relevant conditions that required evaluation and repairs and replacements to be performed during the period June 2016 through May 2018. There are no new commitments or revisions to existing commitments made by Entergy contained in this letter. If you have any questions, please contact Mr. Robert Walpole, Manager, Regulatory Assurance at (914) 254-6710.
Sincerely, AJV/gd
 
==Enclosure:==
 
Form OAR-1 Owners Activity Report cc: Mr. David Lew, Acting Regional Administrator, NRG Region I Mr. Richard Guzman, Senior Project Manager, NRG NRR DORL Ms. Bridget Frymire, New York State Department of Public Service Ms. Alicia Barton, President and CEO, NYSERDA NRG Resident Inspectors r ENCLOSURE TO NL-18-049 Form OAR-1 Owners Activity Report ENTERGY NUCLEAR OPERATIONS, INC. Indian Point Nuclear Generating Unit No. 2 Docket No. 50-24 7 License No. DPR-46 FORM OAR-1 OWNERS ACTIVITY REPORT Report Number: _N~L_-_1~8~-0~4~9
______ _ Page _l_of _1_ Plant: Indian Point Energy Center, Buchanan, New York 10511-0249 Unit No: --~2~ __ Commercial Service Date: (if applicable)
-~0~8~/0~l=/~1~97~4~
__ Refueling Outage No.: -~2R~23~--
Current Inspection Interval:
_______ 5~1_h ________________
_ ( I st, 2nd, 3rd, 4th, Other) Current Inspection Period: ------~1~'
1 _________________
_ (I st, 2nd, 3rd) Edition and Addenda of Section XI applicable to the Inspection Plans: 2007 Edition, 2008 Addenda Date and Revision of Inspection Plans: November 30, 2017 / ISi Program Plan, Rev. 6 No. SEP-ISI-IP2-00I Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the Inspection Plans: NIA Code Cases used for inspection and evaluation:
N-526, N-532-5, N-586-1, N-648-1, N-686-1, N-706-1, N-716-1, N-722-1, N-729-4, N-731, N-735, N-747, N-765, N-770-2 (if applicable, including cases modified by Case N-532 and later revisions)
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 2R23 conform to the requirements of Section XI. Signed: ~(t.-('.c.'&X:-
Pee<~
* Date: -~kt--.-( _2-7----+-\
1_8 __ CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by Hartford Steam Boiler Inspection and Insurance Company 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.
~-Inspector's Signature Date: -~1+--/z__./~,8~---
1 I Commissions:
---"'""'N=B_1~0~0~1~1 (National Board Number and Endorsement)
FORM OAR-1 OWNERS ACTIVITY REPORT Report Number: _N_L_-~1~8~-0~4~9
______ _ Page _1_of_2_ Plant: Indian Point Energy Center, Buchanan, New York 10511-0249 Unit No: --,---.,.,-.,=2--,--
__ Commercial Service Date: (if applicable)
----'0"""8""""/0~l=/~1~97~4.,_
__ .Refueling Outage No.: -~2R~23~--
TABLE 1: ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Description Evaluation Description Category and Item Number NIA NIA NIA TABLE 2: ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE Code Item Description Description of Work Date Repair/Replacement Class Completed Plan Number 3 Pipe adjacent to SWN-K\'eld repair local through-wall corrosion defect 9/9/16 16-2-85 2-2 3 24 FCU Elbow 24-S6 K\'eld repair local through-wall corrosion defect 11/22/16 16-2-89 3 Flange D/S of SWN-K\'eld repair local through-wall corrosion defect 12/21/16 16-2-90 41-4A 3 Flange UIS of SWN-K\'eld repair local through-wall corrosion defect 12/22/16 16-2-92 640 3 22 EDJC Cover !Repair/replace branch connection weld 6/7/17 17-2-36 1 21 Reactor Vessel !Replace reactor vessel stud due to failure of VT-12/18/17 17-2-83 3 inspection 2 Weld U/S of A-98 !Replace weld due to leak at 3/4" socket weld 3/29/18 NIA Vent Valve 3 Flange UIS of SWN-Weld repair local corrosion defect 2/15/18 18-2-5 640 1 21 Reactor Vessel [Perform embedded flaw weld overlay repair of 14/9/18 18-2-23 RVHP#3 3 !Line l lD 25 FCU 1W eld repair local corrosion below min. wall 14/7/18 18-2-26 !Elbows ~hickness}}

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