ML082140299
| ML082140299 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 08/01/2008 |
| From: | Ray Lorson NRC Region 1 |
| To: | Pardee C AmerGen Energy Co, Exelon Generation Co, NRC Region 1 |
| References | |
| IR-08-008 | |
| Download: ML082140299 (11) | |
See also: IR 05000320/2008008
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
475 ALLENDALE ROAD
KING OF PRUSSIA, PA 19406-1415
August 1, 2008
Mr. Charles G. Pardee
Chief Nuclear Officer (CNO) and Senior Vice President
Exelon Generation Company, LLC
Chief Nuclear Officer (CNO)
AmerGen Energy Company, LLC
200 Exelon Way
Kennett Square, PA 19348
SUBJECT: THREE MILE ISLAND STATION UNIT 2 - SAFSTOR INSPECTION REPORT
Dear Mr. Pardee:
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. Dougherty and other
members of your staff. In addition, on July 3, 2008, Mr. Miller and Mr. Curry of your 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 Commissions rules and regulations, and with the conditions of your
license. The inspector reviewed selected procedures and records, observed activities, and
interviewed personnel.
In accordance with 10 CFR Part 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 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
Docket No. 50-320
License No. DPR-73
C. Pardee 2
Enclosure: Inspection Report No. 05000320/2008008
w/Attachment: Supplemental Information
cc w/encl:
C. Crane, Executive Vice President and Chief Operating Officer, Exelon Generation
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
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
August 1, 2008
Mr. Charles G. Pardee
Chief Nuclear Officer (CNO) and Senior Vice President
Exelon Generation Company, LLC
Chief Nuclear Officer (CNO)
AmerGen Energy Company, LLC
200 Exelon Way
Kennett Square, PA 19348
SUBJECT: THREE MILE ISLAND STATION UNIT 2 - SAFSTOR INSPECTION REPORT
Dear Mr. Pardee:
On July 03, 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. Dougherty and other
members of your staff. In addition, on July 03, 2008, Mr. Miller and Mr. Curry of your 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 Commissions rules and regulations, and with the conditions of your
license. The inspector reviewed selected procedures and records, observed activities, and
interviewed personnel.
In accordance with 10 CFR Part 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 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
Docket No. 50-320
License No. DPR-73
Distribution w/encl: S. Barber, DRP C. LaRegina, DRP, R. Nelson, NRR
S. Collins, RA A. Rosebrook, DRP OA H. Chernoff, NRR
M. Dapas, DRA D. Kern, DRP, Sr S. Williams, RI OEDO ROPreports@nrc.gov
D. Lew, DRP Resident Inspector P. Bamford, PM, NRR
J. Clifford, DRP J. Brand, DRP, G. Miller, NRR,
R. Bellamy, DRP Resident Inspector Backup
SUNSI Review Complete: LKauffman
DOCUMENT NAME: G:\D&LB\TMI-2\INSPECTIONREPORTS\TMI-2 IR05000320-2008008.doc
After declaring this document AAn Official Agency Record@ it will/will not be released to the Public.
To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure
"N" = No copy
OFFICE RI/DNMS RI/DNMS
NAME LKauffman RLorson
DATE 8/1/08 8/1/08
OFFICIAL RECORD COPY
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Docket No.: 50-320
License No.: DPR-73
Report No.: 05000320/2008008
Licensee: AmerGen Energy Company, LLC (AmerGen)
Facility: Three Mile Island Station, Unit 2
Location: P. O Box 480
Middletown, PA 17057-0191
Dates: June 3 - 5, 2008 (on-site)
June 27 - July 3, 2008 (in-office)
Inspectors: Laurie Kauffman, Health Physicist
Division of Nuclear Materials Safety
Kristina Banovac, Project Manager
Decommissioning and Uranium Recovery Licensing Directorate
Division of Waste Management and Environmental Protection
Office of Federal and State Materials and Environmental Management
Programs
Approved by: Raymond Lorson, Chief
Decommissioning Branch
Division of Nuclear Materials Safety
i Enclosure
SUMMARY OF FINDINGS
IR 05000320/2008-008; 06/03/2008 - 07/03/2008; AmerGen Energy Company, LLC; 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 NRCs 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 Enclosure
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 1.
4. OTHER ACTIVITIES
4OA5 Other Activities
.1 Corrective Action Program (40801)
a. Inspection Scope
The inspector reviewed the licensees 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
licensees 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.
Enclosure
2
.2 Maintenance and Surveillance (62801)
a. Inspection Scope
The inspector reviewed the licensees 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.
Enclosure
3
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.
Dougherty, and members of 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.
Enclosure
A-1
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee 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
T. Dogherty, Plant Manager Unit 1, Exelon
D. Ethridge, Radiation Protection Manager (Acting), AmerGen
G. Gillespie, TMI-2 Engineer, First Energy
D. Knaby, Radiation Engineer, Exelon
P. Handy, Radiation Engineer, Exelon
R. McDonald, Radiation Protection Supervisor, Exelon
D. Petro, TMI-2 Project Manager, First Energy
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
A-2
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-AA-401, ALARA Plan, Revision 9
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)
Control and Service Building Sump Transfer to IWTS (Release Permit WO803005)
Tendon Access Gallery Sump Transfer to IWTS (Release Permit WO804009)
Air Intake Tunnel Sump Transfer to IWTS (Release Permit WO804008)
Reactor Building Breather HEPA DOP test (WO R2071872)
Attachment
A-3
Reactor Building Purge HEPA DOP test (WO R2074772)
Fuel Handling Building HEPA DOP test (WO R2071842)
Auxiliary Building HEPA DOP test (WO R2078493)
Soiled Exhaust HEPA DOP test (WO R2105902)
LIST OF ACRONYMS
ADAMS Agencywide Documents Access and Management System
ALARA as low as reasonably achievable
AR action report
CFR Code of Federal Regulations
CAP corrective action program
DOP Di-Octyl Phthalate
HEPA high efficiency particulate air
LHRA locked high radiation area
MC manual chapter
NRC Nuclear Regulatory Commission
PARS Publicly Available Records System
PDMS Post-Defueling Monitored Storage
PM preventive maintenance
RCA radiologically controlled area
SSC structure, systems and components
ST surveillance test
TMI-2 Three Mile Island Station, Unit 2
TS technical specification
VHRA very high radiation area
WO work order
Attachment