IR 05000289/2013004
| ML13301A503 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/28/2013 |
| From: | Hunegs G NRC/RGN-I/DRP/PB6 |
| To: | Pacilio M Exelon Generation Co, Exelon Nuclear |
| HUNEGS, GK | |
| References | |
| IR-13-004 | |
| Download: ML13301A503 (34) | |
Text
October 28, 2013
SUBJECT:
THREE MILE ISLAND STATION, UNIT 1 - NRC INTEGRATED INSPECTION REPORT 05000289/2013004
Dear Mr. Pacilio:
On September 30, 2013, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Three Mile Island, Unit 1 (TMI) facility. The enclosed inspection report documents the inspection results, which were discussed on October 18, 2013 with Mr. Rick Libra, Site Vice President, and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings were identified.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRCs document system (ADAMS). ADAMS is accessible from the NRC website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Gordon K. Hunegs, Chief Reactor Projects Branch 6 Division of Reactor Projects
Docket Nos.: 50-289 License Nos.: DPR-50
Enclosure:
Inspection Report 05000289/2013004
w/Attachment: Supplemental Information
REGION I==
Docket No:
50-289
License No:
Report No:
Licensee:
Exelon Generation Company
Facility:
Three Mile Island Station, Unit 1
Location:
Middletown, PA 17057
Dates:
July 1 through September 30, 2013
Inspectors:
D. Werkheiser, Senior Resident Inspector, Division of Reactor Projects (DRP)
J. Heinly, Resident Inspector, DRP
T. Setzer, Senior Resident Inspector (Acting), DRP T. OHara, Reactor Inspector, Division of Reactor Safety (DRS)
T. Moslak, Health Physicist, DRS
S. Pindale, Senior Reactor Inspector, DRS
Approved by:
G. Hunegs, Chief
Reactor Projects Branch 6
Division of Reactor Projects
Enclosure
SUMMARY SHEET, 32-9075183-220, TMI-1, NEI 9706 AREVA ENGINEERING INFORMATION RECORD, Document No: 51-9121190-000, EOTSG Empirical Wear Projections AREVA NP Inc. 77-5071314-004, Enhanced Once-Through Steam Generator (EOTSG)
Report For Exelon Inc. Three Mile Island, October 2009 AREVA NP Inc., Engineering Information Record, Document No: 51-9121190-000, AREVA NP Inc., Engineering Information Record, Document No: 51-9172250-000, Condition Monitoring and Operational Assessment of TMI-1 Steam Generators at 1R19, 11/14/11 Design Analysis No.: 32-9057611; TMI EOTSG Operational Transients FIV Analysis, Revision 2, 12/3/09 Design Analysis No.: 51-9023556; TMI EOTSG Tube Bundle FIV Summary Report, Revision 2, 11/17/09 Design Specification For TMI-1 Replacement Steam Generator; 08-5056319-10, Revision 10, 12/17/2009; ATTACHMENT 4, OWNERS REVIEW OF DESIGN SPECIFICATION EOTSG Empirical Wear Projections, 9/30/09 ECR 06-00935, 50.59 SCREENING FORM - TMI-1 ONCE THROUGH STEAM, Revision 2 ECR 06-00935, 50.59 APPLICABILITY REVIEW FORM - TMI-1 ONCE THROUGH STEAM GENERATOR REPLACEMENT, Revision 2 ECR 06-00935, 50.59 REVIEW - TMI-1 ONCE THROUGH STEAM GENERATOR REPLACEMENT, Revision 2 TMI UNIT 1 OUTAGE T1R19 STEAM GENERATOR DEGRADATION ASSESSMENT, REVISION 0, 10/19/11 TMI UNIT 1 OUTAGE T1R19 STEAM GENERATOR CONDITION MONITORING AND OPERATIONAL ASSESSMENT, REVISION 0, 11/16/11 TMI-1 RSG ASME Design Report, 33-9018465-003, Revision 003, 1/8/10; ATTACHMENT 7,
A-11
Attachment OWNERS REVIEW FORM FOR DESIGN/STRESS REPORT, 1/9/10
Action and Condition Reports IR-1287166: Exelon AR, Unexpected Degradation in EOTSGs CR-2011-8212: AREVA EOTSG Tube-to-Tube Wear Root Cause Report, 6/13/13
A-12
Attachment LIST OF ACRONYMS
Alternate Current ADAMS
Agencywide Documents Access and Management System ALARA
As Low As Reasonably Achievable ASME
American Society of Mechanical Engineers CFR
Code of Federal Regulations CR
Condition Report DHRS Decay Heat Removal System DRP
Division of Reactor Projects DRS
Division of Reactor Safety DRWS Decay River Water System EDG
Emergency Diesel Generator EPIP
Emergency Plan Implementing Procedures GL
[NRC] Generic Letter HXs
Heat Exchangers ICCS Intermediate Closed Cooling System IP
[NRC] Inspection Procedure IR
Issue Report IST
In-Service Testing NEI
Nuclear Energy Institute NRC
Nuclear Regulatory Commission NSIR
Office of Nuclear Security and Incident Response NSRWS
Nuclear Service River Water System ODCM Offsite Dose Calculation Manual PARS
Publicly Available Records SSC
Structure, System, or Component TMI
Three Mile Island Unit 1 TS
Technical Specifications UFSAR
Updated Final Safety Analysis Report UT
Ultrasonic Testing WECST
Waste Evaporator Condensate Storage Tank WGDT
Waste Gas Decay Tank