IR 05000320/2008008
| ML082240237 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 08/11/2008 |
| From: | Lorson R K Decommissioning Branch I |
| To: | Hagan J J GPU Nuclear |
| References | |
| IR-08-008 | |
| Download: ML082240237 (11) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PA 19406-1415
August 11, 2008
Joseph President and Chief Nuclear Officer GPU Nuclear, Inc.
76 South Main Street Akron, OH 44308
SUBJECT: THREE MILE ISLAND STATION UNIT 2 - SAFSTOR INSPECTION REPORT 05000320/2008008
Dear Mr. Hagan:
On July 3, 2008, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Three Mile Island Station, Unit 2. The enclosed inspection report documents the inspection results, which were discussed on June 5, 2008, with Mr. D. Petro and other members of your staff and the Exelon/AmerGen staff. In addition, on July 3, 2008, Mr. Miller and Mr. Curry of the AmerGen staff were contacted via telephone and a final exit was conducted.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.
On August 1, 2008, a report of this inspection was issued (ML082140299), however, the report was incorrectly directed to the Unit 1 distribution list due to an administrative error. This report replaces the report issued on August 1, 2008.
In accordance with 10 CFR Part 2.390 of the NRC's "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 NRC's document system (ADAMS). ADAMS is accessible from the NRC Web Site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,/RA/
Raymond K. Lorson, Chief Decommissioning Branch Division of Nuclear Materials Safety
Enclosure:
Inspection Report No. 05000320/2008008
w/Attachment:
Supplemental Information
cc w/encl: J. Rinckel, Vice President, GPU Nuclear Oversight D. Petro, Responsible Engineer, TMI-2, GPU Nuclear, Inc.
G. Gillespie, Responsible Engineer, TMI-2, GPU Nuclear, Inc.
cc: J. Rinckel, Vice President, GPU Nuclear Oversight D. Petro, Responsible Engineer, TMI-2, GPU Nuclear, Inc.
G. Gillespie, Responsible Engineer, TMI-2, GPU Nuclear, Inc.
C. Pardee, Chief Nuclear Officer (CNO) and Senior Vice President, Exelon C. Crane, Executive Vice President and Chief Operating Officer, Exelon W. Noll, Site Vice President - TMI Unit 1, AmerGen T. Dougherty, Plant Manager - TMI, Unit 1, AmerGen Manager, Regulatory Assurance - TMI, Unit 1, AmerGen Senior Vice President - Nuclear Services, AmerGen Senior Vice President - Mid-Atlantic Operations, AmerGen Senior Vice President - Operations Support, AmerGen Vice President - Licensing and Regulatory Affairs, AmerGen Director, Licensing - AmerGen Manager, Licensing - TMI, AmerGen J. Fewell, Esq., Associate General Counsel, Exelon Correspondence Control Desk - AmerGen Chairman, Board of County Commissioners of Dauphin County Chairman, Board of Supervisors of Londonderry Township R. Janati, Director, Bureau of Radiation Protection, State of PA D. Allard, Director, PA DEP J. Johnsrud, National Energy Committee E. Epstein, TMI-Alert (TMIA)
J. Powers, Director, PA Office of Homeland Security R. French, Director, PA Emergency Management Agency
SUMMARY OF FINDINGS
IR 05000320/2008-008; 06/03/2008 - 07/03/2008; GPU Nuclear, Inc.; Three Mile Island, Unit 2;
Other Activities - SAFSTOR Inspection
The inspection was performed by one region-based inspector and one project manager from headquarters. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Manual Chapter (MC) 2561, "Decommissioning Power Reactor Inspection Program."
A. NRC-Identified and Self-Revealing Findings
None
B. Licensee-Identified Violations
None ii
J. Hagan
1
REPORT DETAILS
Summary of Plant Status
The Three Mile Island Station, Unit 2 (TMI-2) has been permanently shutdown since March 1979 and has been in Post-Defueling Monitored Storage (PDMS) since December 1993. Final decommissioning is expected to begin following the permanent shutdown of Three Mile Island, Unit
OTHER ACTIVITIES
4OA5 Other Activities
.1 Corrective Action Program
a. Inspection Scope
The inspector reviewed the licensee's program for identifying, resolving, and preventing issues that could impact safety or the quality of decommissioning activities. The inspector reviewed the procedures describing the corrective action program (CAP) and reviewed two assignment reports (ARs). The ARs were reviewed to evaluate the licensee's effectiveness at identifying issues that could impact the safe storage of radioactive material and implementing appropriate corrective actions. The inspector discussed with cognizant personnel the tracking, current status, and closure of the
selected ARs.
b. Findings
No findings of significance were identified.
The inspector noted that the priority for addressing ARs and implementing corrective actions was adequate and based upon safety significance. The threshold for identifying issues entered into the CAP was adequate. Responsible personnel were knowledgeable of the status of corrective actions and established measures to monitor completion of corrective actions. No adverse trends or safety concerns were identified.
2 Enclosure
.2 Maintenance and Surveillance
a. Inspection Scope
The inspector reviewed the licensee's preventive maintenance (PM) and surveillance test program for structures, systems, and components (SSCs) important for maintaining the safe storage of radioactive material. The inspector reviewed selected surveillance tests (STs) including the high efficiency particulate air (HEPA) filter Di-Octyl Phthalate (DOP) tests for the reactor building breather, reactor building purge, fuel handling building, auxiliary building, and service building; the ventilation heater; the containment isolation airlocks; and the quarterly containment isolation valves. The inspector toured plant areas and discussed aspects of the STs with individuals cognizant of the performance of the above systems and components.
b. Findings
No findings of significance were identified.
The inspector verified that the maintenance for selected systems and components had been conducted in accordance with established procedures and met the requirements of the associated technical specifications (TS). The inspector noted that the individuals performing the annual STs were knowledgeable of motors, pumps, valves, HEPA filter DOP tests, and implemented good industrial and radiological safety practices during the ST.
.3 Occupational Radiation Safety and Effluent Monitoring (83750 and 84750)
a. Inspection Scope
The inspector reviewed implementation of the occupational exposure control program associated with the TMI-2 PDMS activities and the implementation of primary containment isolation requirements, TS 3/4.1, Containment Systems. The inspection consisted of interviews with responsible individuals, and review of the as low as reasonably achievable (ALARA) plan, and of the post-job review for the reactor building entry. The inspector reviewed the controls for high radiation areas (HRA), locked high radiation areas (LHRA) and very high radiation areas (VHRA), and conducted field observations of radiological postings and signs, and the annual reactor building entry ST. The reactor building ST included activities such as: conducting radiological surveys including obtaining grab air samples, smears and area dose rates at locations identified in the radiological survey procedure. The ST also included performing a visual inspection to assess the material condition of the containment interior, including checking for rust, cracks, and water intrusion. The inspector observed the licensee implement access controls to the VHRA.
The inspector evaluated aspects of the radioactive effluent monitoring program. The inspector reviewed the radioactive liquid and gaseous effluent release permits and data from June 2007 through April 2008. The inspector also reviewed the sampling and the analysis procedures.
3 Enclosure
b. Findings
No findings of significance were identified.
The inspector noted that the radiation workers were knowledgeable of the tasks and demonstrated a questioning attitude during the job. The radiation protection team maintained control of the locked high radiation area key in accordance with the procedure. The associated radiation work permit was commensurate with the radiological significance of the task and included the appropriate exposure control measures for the safe implementation of the activity.
The LHRAs and VHRAs were appropriately posted for dose rates and radioactive material. Radiological postings were readily visible, well-maintained, and reflected radiological conditions. The ALARA report contained a summary of the estimated doses, a comparison of the estimated doses to the actual doses, and a detailed evaluation of the entry.
The licensee conducted the effluent control program according to the Offsite Dose Calculation Manual and the implementing procedures.
4OA6 Meetings, including Exit
Exit Meeting Summary
On June 5, 2008, the inspector presented the preliminary inspection results to Mr. Petro, and members of the GPU Nuclear, Inc. and the AmerGen staff. The inspector confirmed that proprietary information was not provided or examined during the inspection. In addition, on July 3, 2008, the licensee was contacted via telephone and a final summary exit was conducted.
J. Hagan Attachment 1A-1
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
GPU Nuclear, Inc. (Three Mile Island, Unit 2) and Exelon/AmerGen (Three Mile Island, Unit 1) Personnel
- D. Atherholt, Regulatory Assurance Manager, Exelon
- E. A. Curry, PDMS Supervisor, AmerGen
- G. Darling, Regulatory Assurance Specialist, AmerGen
- D. Divittore, Radiation Protection Manager, Exelon
- D. Ethridge, Radiation Protection Manager (Acting), AmerGen
- G. Gillespie, TMI-2 Engineer, GPU Nuclear, Inc.
- D. Knaby, Radiation Engineer, Exelon
- P. Handy, Radiation Engineer, Exelon
- R. McDonald, Radiation Protection Supervisor, Exelon
- D. Petro, Responsible Engineer, TMI-2, GPU Nuclear, Inc.
- D. Smith, PDMS Manager, AmerGen
- R. Taylor, Radiation Engineer, Exelon
- L. Weber, Environmental Chemist, Exelon
- L. Weir, Manager, Nuclear Oversight, Exelon
- H. Yeldell, Work Management Director, Exelon
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened and Closed
None
LIST OF DOCUMENTS REVIEWED
Post-Defueling Monitored Storage Safety Analysis Report (PDMS SAR) for
- TMI-2, Update 7, dated, August 22, 2007.
- GPU Nuclear Post-Defueling Monitored Storage Quality Assurance Plan (PDMS QA Plan) for Three Mile Island Unit 2, Revision 11, dated May 15, 2008
- Possession Only License No.
- DPR-73 License Amendment No. 62 and Technical Specifications
- Action Reports (ARs)
- AR Number
- 00688884
- AR Number
- 00675139
- Attachment Work Orders
- WO R2088079, Unit 2 Reactor Building Entry, May 31, 2007
- WO R2121543, Unit 2 Reactor Building Entry, June 3, 2008
- WO 2114837 and
- WO 212708, Unit 2 Vent Monthly Composite
- WO R2113692, Unit 2 Vent Weekly Composite
- WO R2116589, Auxiliary and Fuel Handling Building Surveys 2008
- WO R2104191, Reactor Building Breather Sample Filters
- WO R2087558, Reactor Building (Containment) Radiological Surveys
Procedures
- 2104-1A, Reactor Building Entry, Revision 005
- 2104-1B,
- TMI-2 Reactor Building Purge, Revision 012
- 2104-1C,
- TMI-2 Reactor Building Breather Shutdown, Revision 007
- 2104-1F, Reactor Building Air Sampling Operations, Revision 007
- 2104-40C,
- TMI-2 Turbine Building Sump Transfer to IWTS, Revision 1
- 2104-40D,
- TMI-2 Control Building Area Sump Transfer to IWTS, Revision 0
- 2104-40E,
- TMI-2 Control and Service Building Sump Transfer to IWTS, Revision 0
- 2104-40F,
- TMI-2 Tendon Access Gallery Sump Transfer to IWTS, Revision 2
- 2104-40G,
- TMI-2 Air Intake Tunnel Sump Transfer to IWTS, Revision 1
- 2107-2, Operation of
- TMI-2 Reactor Building Lighting, Revision 005
- 2301-4.2 Auxiliary and Fuel Handling Building PDMS Radiological Surveys, Revision 8
- 2301-4.3
- TMI-2 Reactor Building (Containment) PDMS Radiological Surveys, Revision 005
- 2301-4.7,
- TMI-2 Vent Sampling, Revision 18
- 2301-4.7D, Sampling and Analysis of the Reactor Building Breather System, Revision 007
- 2301-9.10,
- TMI-2 Containment Isolation Verification, Revision 13
- 2303-5.10, Reactor Building Purge Exhaust Filter Ops Check, Revision 006
- 2303-11.25, Containment Isolation Air Locks, Revision 006
- 6610-ADM-4250.14, Releasing Radioactive Gaseous Effluents -
- TMI-2 Reactor Building Purges, Revision 004
- 2OPS-S021, PDMS - Ventilation Heater Verification, Revision 1
- MA-AA-796-024, Scaffold Installation, Inspection and Removal, Revision 007
- RP-AA-460, Controls for High and Very High Radiation Areas, Revision 11
- RP-TM-220-1002, Special Bioassay Program for Transuranic Areas of
- TMI-2, Revision 1
Documents
- Unit 2 Vent Sample Analysis for Weekly Composites December 2007 to May 2008
- Unit 2 Vent Sample Analysis for Monthly Composites July 2007 to January 2008
- Containment Isolation Verifications July 2007 to June 2008
- Auxiliary and Fuel Handling Building Surveys Reactor Building Breather Sample Filters Reactor Building (Containment) Radiological Surveys Turbine Building Sump Transfer to IWTS (Release Permit WO710028)
- Attachment Reactor Building Purge HEPA DOP test (WO R2074772) Fuel Handling Building HEPA DOP test (WO R2071842)
LIST OF ACRONYMS
VHRA very high radiation area