ML17045A469

Oyster Creek Nuclear Generating Station - 1R26 Refueling Outage Inservice Inspection (ISI) Form OAR-1 Owner'S Activity Report

ML17045A469
Person / Time
Site:	Oyster Creek
Issue date:	02/10/2017
From:	Stathes G L Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RA-17-014
Download: ML17045A469 (5)

Text

Exelon Generation@ RA-17-014 February 10, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

• Oyster Creek Nuclear Generating Station Renewed Facility Operating License No. DPR-16 Docket No. 50-219 Oyster Creek Route 9 South P.O. Box388 Forked River, NJ 08731 ASME Code,Section XI 1 OCFR50.55a

Subject:

Oyster Creek Nuclear Generating Station (OCNGS) 1 R26 Refueling Outage lnservice Inspection (ISi) Form OAR-1 Owner's Activity Report The purpose of this letter is to provide the Oyster Creek Nuclear Generating Station Owner's Activity Report (OAR-1) for lnservice Inspections as required by the American Society of Mechanical Engineers (ASME) Code,Section XI, 2007 Edition with 2008 Addenda ASME Code Case N-532-4 Repair/Replacement Activity Documentation Requirements and lnservice Summary Report Preparation and Submission -Section XI, Division 1. Attachment 1 is the Form OAR-1 Owner's Activity Report covering ISi activities associated with the 1 R26 Refueling Outage which started on September 19, 2016, and was the first outage of the second period of the current ISi inspection interval. OCNGS was unable to complete the Form OAR-1 within 90 calendar days of the completion of the refueling outage as required by Code Case N-532-5. This non-compliance was entered into the site corrective action program under Issue Report Number 3961771 and communicated to the NRC per letter RA-16-112 dated January 11, 2017 (Accession Number ML 17018A073). If you should have any questions, please contact the Oyster Creek ISi point of contacts, Valmicky Samlal at 609-971-4112 or Tedd Nickerson at 609-971-2197. Sincerely, Vice President Oyster Creek Nuclear Generating Station U.S. Nuclear Regulatory Commission February 10, 2017 Page 2 of 2

Enclosures:

Attachment 1 -Form OAR-1 Owner's Activity Report-1 R26 Outage cc: USNRC, Regional Administrator, Region I USNRC, Senior Project Manager, NRR USNRC, Senior Resident Inspector Gary Gustafson, Hartford Steam Boiler l&I Co.

FORM OAR*l OWNER'S ACTIVITY REPORT Plant: Oyster Creek Nuclear Generating Station, US Route 9 South, Forked River. NJ 08731 Unit No: _1'"'--____ Commercial service date: December 23, 1969 Refueling Outage No: _.2=6,__ ___ _ {if appncableJ Current Inspection -""IS"-l ==Sth_,_/""'C"'"IS:.:..l ll11, 2!14,. 3m, other} Current inspection period: _1 ... s ... 1 .... Edition and Addenda of Section XI appl!cable to the Inspection plans: 2007 Edition with 2008 Addenda for ISi and 2001 Edition with 2003 Addenda for CISI Date and revision of inspection plans: 09/02/2015, Revision 2 for ISi and 07 {26/2011. Revision 1 for ClSI Edition and Addenda of Section XI applicable to repa;r/replacement activities, if different than the inspection plans NA Code Cases used for inspection and evaluation: N-432-1, N-513-3. N-516-3, N-526, N-532-5. N-537. N-561-2, N-583. N-586*1, N-597-2, N-600, N-606-1, N-609, N-613-1, N-629, N-638-4, N-639, N-641, N-647, N-648-1, N-649. N-651, N-658, N-661-2, N-663, N-665, N-666, N-683, N-696, N-700, N-705, N-712,

• N-730. N-733, N-735, N-747, N-762, N-765, N-769, N-773, N-786. and N-789 CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (bl 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 ""'o""'c .... 1 .. R""'2""6 ________ conform to the requlrements of Section XI. (refueling outage number) Signed Gene Navratil. 151 Program Owner Ownor or Owner's Des!gnee, Title Date a/t/17 CERTIFICATE OF INSERVICE INSPECTION !, the undersigned, holding a valid commission Issued by the National Board of Boiler and Pressure Vessel Inspectors and employed by The Hartford Steam Boiler Inspection and Insurance Company 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 requlrements of Section XI. By signing this certificate neither the Inspector nor his employer makes any warranty, el!pressed or implied, concerning the repalr/replacemen.t a(..iivities and evaluation descrribed in this report. Furthermore, nelther the inspector nor his employer shall be liable in any manner for any personnel injury or property damage or a loss of any kind arising ftom or Ga!Y 13855 ANIC N.1948 (Notional B"trd M"mbe< a>nd Endcrs*men!) Date __ -zht 7 Table 1 Items with Flaws or Relevant Conditions That Required Evaluation for Continued Service Examination Category Item Description Evaluation Description and Item Number F-A, F1.20C Containment Spray piping support Support evaluated with one anchor bolt not 241-0080 credited for structural support per Engineering Change 617885. B-P, BlS.10 Mechanical joint leakage identified Mechanical joint leakage evaluated as acceptable during Class 1 leakage test per IR 3968718.

Table 2 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Completed Repair/Replacement Plan Number 3 P-3-3A Replace ESW pump. 02/07/2017 R2131578 1 P-37-4 Replace recirculation 02/02/2017 C2036150 pump seal. 3 Y-11-2 Replace expansion 01/29/2017 CZ036974 joint. 1 V-1-164 Replace main steam 01/10/2017 R2181961 relief valve due to failed lift test. Valve lifted at -3.3% of set pressure (-4 psig out of tolerance) and would have fulfilled its function to relieve reactor pressure If reauired. 1 Control Rod Drive Replace control rod 02/06/2017 C2036154 14-47 drive due to flange joint leak.