AEP-NRC-2018-14, Form OAR-1, Owner'S Activity Report

From kanterella
Jump to navigation Jump to search
Form OAR-1, Owner'S Activity Report
ML18059A777
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 03/23/2018
From: Lloyd M
Indiana Michigan Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
AEP-NRC-2018-14
Download: ML18059A777 (6)


Text

m INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWIER One Cook Place Bridgman, Ml 49106 A unit ofAmerican Electric Power lndianaMichiganPower.com AEP-NRC-2018-14 February 23, 2018 10 CFR 50.55a Docket No.: 50-315 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 Form OAR-1, Owner's Activity Report This letter provides a copy of Form OAR-1, Owner's Activity Report, for inservice inspection activities performed at Donald . C. Cook Nuclear Plant Unit 1 through the completion of the Unit 1 Cycle 28 Refueling Outage. This report meets the requirements of the American Society of Mechanical Engineers (ASME) Code Case N-532-5, "Repair/Replacement Activity Documentation Requirements and lnservice Inspection Summary Report Preparation and Submission Section XI, Division 1." This code case is used as an alternative to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-6000, as approved by Regulatory Guide 1.147, "lnservice Inspection Code Case Acceptability, ASME Section XI, Division 1," Revision 17, for the current inspection interval.

I I

The Authorized Code Inspection Company is OneCIS Insurance Co., of Lynn, Massachusetts. The Authorized Nuclear Inspector is Timothy H. Merchant.

There are no new or revised commitments in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.

Sincerely, ffl1al!lr('

Mark Lloyd Engineering Vice President MBE/mll

Enclosure:

Form OAR-1, Owner's Activity Report for Donald C. Cook Nuclear Plant Unit 1 Cycle 28 Refueling Outage

U. S. Nuclear Regulatory Commission AEP-NRC-2018-14 Page2 c: R. J. Ancona - MPSC, w/o enclosure MDEQ - RMD/RPS, w/o enclosure NRG Resident Inspector J. K. Rankin - NRG Washington DC K. S. West- NRG Region Ill A. J. Williamson - AEP Ft. Wayne, w/o enclosure I

ENCLOSURE TO AEP-NRC-2018-14 FORM OAR-1, OWNER'S ACTIVITY REPORT FOR DONALD C. COOK NUCLEAR PLANT UNIT 1 CYCLE 28 REFUELING OUTAGE

D. C. Cook Nuclear Unit 1 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number 1-2017-4-3-01 Plant Donald C Cook Nuclear Plant, One Cook Place, Bridgman, Michigan 49106 Unit No. Commercial service date 8/23/1975 Refueling outage no. U1C28 (if applicable)

Current inspection interval 4th for Components and Supports (C&S) and 2nd for Containment ISi (GISI) Program (1st, 2nd, 3rd, 4th, other)

Current inspection period 3rd for C&S and 3rd for GISI (1st, 2nd, 3rd)

Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition/No Addenda Date and revision of inspection plans 12/18/2016 Rev 8 for C&S; and 1/27/2017 Revision 5 for GISI Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans - - - - - - - - - - - -

Edition and Addenda are the same as the Inspection Plans Code Cases used for inspection and evaluation: _N_-_5_66;;..-.;;;2...ca.c..n;.;;;d...;.N.;..-.;..72cc2_-...;.1...;.fo.;..r_C.;..&c...S-'-'-,N_-_6_4_9_fo_r_C_l;.;;S..;..I_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

(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 U1C28 conform to the requirements of Section XI. (refueling outage number)

Signed ~ .*et'-~"--'


~~-----------~--~------ ,ISi Program Owner Date ---~-~--------- z{ I z..12..LI I 8°'

Owners or Owne(s Designee, Title 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 OneCIS Insurance Co. of Lynn, MA 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.

Commissions _ _T..,_..J tu~ Be ~~..:r. ,,

_ _ _ _ _ _ _ _ _ _ _~ - - - - - - - - - - -

National Board Number and Endorsement Date Page 1 of3 L

D. C. Cook Nuclear Unit 1 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category and Item Number Item Description Evaluation Description None None None Page 2 of 3

D. C. Cook Nuclear Unit 1 Table 2 Abstract of Repair/replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number Steam generator 1-0ME-3-2 outlet manway stud had recordable indications that failed to meet the acceptance criteria of IWB-3515.1 for surface examination performed per Note 7 of Table 2500-1, Examination Category: B-G-1 Examination Category B-G-1. Reference WO 55484434-06, Item No.: 86.90 1 inspection report U1-VE-17-030 and AR 2017-9655. 10/18/2017 55453144-06 Parts Examined: Steam Generator Bolts and Studs The stud was replaced with a spare under WO 55453144-06. The satisfactory preservice examination of the replacement stud was performed as documented in inspection report U1-VE-17-040.

1 Steam Generator 1-0ME-3-1 Mechanical plugging of 25 tubes due to wear indications 10/25/2017 55457232-49 1 Steam Generator 1-0ME-3-2 Mechanical plugging of 20 tubes due to wear indications 10/3/2017 55457231-27 1 Steam Generator 1-0ME-3-3 Mechanical pluqqinq of 16 tubes due to wear indications 10/3/2017 55457230-26 1 Steam Generator 1-0ME-3-4 Mechanical pluqqinq of 25 tubes due to wear indications 10/3/2017 55457229-26 Examination Category: B-N-3 Item No.: 813.70 1 Replace 212 Baffle Former Bolts 11/11/2017 55493304-18 Parts Examined: Core Support Structure Page 3 of3