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=Text= | =Text= | ||
{{#Wiki_filter:Inspection | {{#Wiki_filter:Inspection N Docket N License N Licensee: | ||
Address: U.S. NUCLEAR REGULATORY COMMISSION | Address: | ||
U.S. NUCLEAR REGULATORY COMMISSION | |||
= | ==REGION I== | ||
GPU Nuclear, | INSPECTION REPORT 05000320/2011008 05000320 DPR-73 GPU Nuclear, In White Pond Drive Akron, OH 44320 Locations Inspected: | ||
Three Mile Island Station, Unit 2 Middletown, PA 17057-0791 Inspection Dates: | |||
Inspectors: | |||
Approved By: | |||
July 25-28, 2011 Laurie A. Kauffman Health Physicist Decommissioning Branch Division of Nuclear Materials Safety Kathy Modes Senior Health Physicist Decommissioning Branch Division of Nuclear Materials Safety Judith A. Joustra, Chief Decommissioning Branch Division of Nuclear Materials Safety Document Name: G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx | |||
=EXECUTIVE SUMMARY= | |||
GPU Nuclear, Inc. | |||
The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561, "Decommissioning Power Reactor Inspection Program." The inspection included a review of operations and management oversight, maintenance, corrective action program implementation, and plant support activities while in Post Defueling Monitored Storage (PDMS) status. Within the scope of this inspection, no safety concerns or violations were identified. | NRC Inspection Report No. 05000320/2011008 A routine announced safety inspection was conducted on July 25-28, 2011, at the Three Mile Island Station, Unit 2 (TMI-2) by two Region I inspectors. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561, "Decommissioning Power Reactor Inspection Program." The inspection included a review of operations and management oversight, maintenance, corrective action program implementation, and plant support activities while in Post Defueling Monitored Storage (PDMS) status. Within the scope of this inspection, no safety concerns or violations were identified. The conclusions from each inspection area are presented below. | ||
Organization, Management & Cost Control The licensee has process controls, and an organization to effectively implement license requirements. | |||
& Cost Control The licensee has process controls, and an organization to effectively implement license requirements. | |||
Safety Reviews, Design Changes, and Modifications The licensee implemented a safety review program to maintain decommissioning safety and the facility configuration as described in their licensing basis | Safety Reviews, Design Changes, and Modifications The licensee implemented a safety review program to maintain decommissioning safety and the facility configuration as described in their licensing basis. | ||
Action reports were properly prioritized and corrective actions were tracked in accordance with approved procedures. | Self-Assessment, Auditing, and Corrective Action Programs The licensee's self-assessment, auditing, and corrective action programs were effective at identifying, resolving, and preventing problems. Action reports were properly prioritized and corrective actions were tracked in accordance with approved procedures. | ||
Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors (PSRs) There has been no dismantlement or decommissioning activities performed since the previous inspection. | Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors (PSRs) | ||
There has been no dismantlement or decommissioning activities performed since the previous inspection. | |||
Maintenance and Surveillance The licensee effectively implemented the preventive maintenance and surveillance program and associated procedures. | Maintenance and Surveillance The licensee effectively implemented the preventive maintenance and surveillance program and associated procedures. | ||
Occupational Radiation Exposure The licensee effectively implemented the occupational exposure control program associated with the TMI-2 PDMS activities. | Occupational Radiation Exposure The licensee effectively implemented the occupational exposure control program associated with the TMI-2 PDMS activities. The licensee maintained occupational radiation exposures as low as reasonably achievable (ALARA). | ||
Effluent and Environmental Monitoring The licensee effectively implemented and maintained the radioactive effluent controls program and the radiological environmental monitoring program. | |||
ii Inspection Report No. 05000320/2011008 G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOS.docx | |||
=REPORT DETAILS= | =REPORT DETAILS= | ||
Ventilation and rainwater systems continue to be monitored. | 1.0 | ||
. Background Information In December 1993, TMI-2 received a license from the NRC to enter Post Defueling Monitored Storage (PDMS). TMI-2 today is in long-term monitored storage. No further use of the nuclear part of the plant is anticipated. Ventilation and rainwater systems continue to be monitored. | |||
Equipment necessary to keep the plant in safe long-term storage continued to be maintained. | Equipment necessary to keep the plant in safe long-term storage continued to be maintained. | ||
| Line 54: | Line 60: | ||
The licensee plans to actively decommission TMI-2 in parallel with the decommissioning of the Three Mile Island, Unit 1 (TMI-1) after unit has been permanently shutdown. | The licensee plans to actively decommission TMI-2 in parallel with the decommissioning of the Three Mile Island, Unit 1 (TMI-1) after unit has been permanently shutdown. | ||
2.0 Organization, Management | 2.0 Organization, Management & Cost Controls | ||
& Cost Controls | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
(Inspection Procedures (lP) 36801) The inspectors evaluated any recent organization, management and staffing changes with respect to the PDMS Quality Assurance (QA) program outlined in the PDMS QA Plan. The inspectors reviewed Action Reports, interviewed Employee Concerns Program personnel, and reviewed Company Nuclear Review Board meeting minutes. | (Inspection Procedures (lP) 36801) | ||
The inspectors evaluated any recent organization, management and staffing changes with respect to the PDMS Quality Assurance (QA) program outlined in the PDMS QA Plan. The inspectors reviewed Action Reports, interviewed Employee Concerns Program personnel, and reviewed Company Nuclear Review Board meeting minutes. | |||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
In early 2010, Exelon appointed a new PDMS Manager and PDMS Senior Specialist who have over 20 years of experience working at TMI. The inspectors determined that these individuals were cognizant of the TMI-2 process controls and license requirements. | In early 2010, Exelon appointed a new PDMS Manager and PDMS Senior Specialist who have over 20 years of experience working at TMI. The inspectors determined that these individuals were cognizant of the TMI-2 process controls and license requirements. With a change in personnel, the licensee continued to maintain important records and history of the plant needed to support future decommissioning of TMI-2. | ||
Action Report No. 01100971, "TMI-2 FENOC and EXELON Employee Concerns Program (ECP) Enhancements" describes the licensee's continued commitment to safety culture. ECP personnel provided details about the licensee commitment to maintain a high level of awareness to safety. The Company Nuclear Review Board (CNRB) meeting minutes demonstrated that the CNRB was attentive to the ECP. | |||
Personnel from electrical, radiation protection, operations, radioactive waste, chemistry, security, maintenance, housekeeping, and quality assurance enter TMI-2 through the course of their normal work duties. Even though the facility is in a PDMS status, there are adequate resources available to ensure the licensee is meeting their licensing basis. | |||
====c. Conclusions==== | ====c. Conclusions==== | ||
The licensee has process controls, and an organization to effectively implement license requirements. | The licensee has process controls, and an organization to effectively implement license requirements. No findings of safety significance were identified. | ||
No | Inspection Report No. 05000320/2011008 G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx | ||
3.0 Safety Reviews, Design Changes, and Modifications | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
(lP 37801) The inspectors reviewed a random sample of PDMS procedures to verify the licensee implements a safety review program that effectively maintains decommissioning safety and the facility configuration as described in their licensing basis. | (lP 37801) | ||
The inspectors reviewed a random sample of PDMS procedures to verify the licensee implements a safety review program that effectively maintains decommissioning safety and the facility configuration as described in their licensing basis. | |||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
The licensee updated their PDMS procedures to reflect current plant configuration and administrative processes, and to make some editorial changes. The typical categories of procedures that were changed were administrative, ventilation, electrical distribution, radioactive waste processing, fire protection, compressed air, and Technical Specification surveillance. | The licensee updated their PDMS procedures to reflect current plant configuration and administrative processes, and to make some editorial changes. The typical categories of procedures that were changed were administrative, ventilation, electrical distribution, radioactive waste processing, fire protection, compressed air, and Technical Specification surveillance. Due to the non-operating and defueled status of TMI-2 during PDMS, there are no structures, systems, or components (SSC) that are required to meet the safety-related criteria. Therefore, there are no SSC classified as safety-related at TMI-2. All procedure changes and facility modifications at TMI-2 are made using the Exelon 10 CFR 50.59 Review Process, which provides a screening process to determine if the change requires a written evaluation. | ||
Due to the non-operating and defueled status of TMI-2 during PDMS, there are no structures, systems, or components (SSC) that are required to meet the safety-related criteria. | |||
Therefore, there are no SSC classified as safety-related at TMI-2. All procedure changes and facility modifications at TMI-2 are made using the Exelon 10 CFR 50.59 Review Process, which provides a screening process to determine if the change requires a written evaluation. | |||
====c. Conclusions==== | ====c. Conclusions==== | ||
| Line 88: | Line 93: | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
(lP 40801) The inspectors reviewed the licensee's program for identifying, resolving, and preventing issues that could impact safety or the quality of future decommissioning activities. | (lP 40801) | ||
The inspectors reviewed the licensee's program for identifying, resolving, and preventing issues that could impact safety or the quality of future decommissioning activities. The inspectors reviewed the procedures describing the corrective action program and reviewed several issue reports (IRs), action reports (ARs), and the associated corrective actions. The inspectors discussed with cognizant personnel the tracking, current status, and closure of the selected IRs and ARs. The inspectors reviewed the August 2010 Nuclear Oversight (NOS) audit report and the April 2011 Fleet Oversight Audit Report (TMI-C-11-04-28). | |||
The inspectors reviewed the procedures describing the corrective action program and reviewed several issue reports (IRs), action reports (ARs) , and the associated corrective actions. The inspectors discussed with cognizant personnel the tracking, current status, and closure of the selected IRs and ARs. The inspectors reviewed the August 2010 Nuclear Oversight (NOS) audit report and the April 2011 Fleet Oversight Audit Report (TMI-C-11-04-28). | |||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
The inspectors noted that there were approximately 178 ARs generated for TMI-2 and only 26 remained open at the time of the inspection. | The inspectors noted that there were approximately 178 ARs generated for TMI-2 and only 26 remained open at the time of the inspection. There were 61 ARs dealing with administrative issues, 17 that needed procedure changes, and 100 work orders generated. ARs were generated to address revision of plant procedures, effectiveness of fire brigades, lack of sample flow for the weekly tritium check, roof leaks, a radiation monitor out-of-service, and cork seam pump problems. The inspectors noted that there Inspection Report No. 05000320/2011008 G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx | ||
There were 61 ARs dealing with administrative issues, 17 that needed procedure changes, and 100 work orders generated. | |||
ARs were generated to address revision of plant procedures, effectiveness of fire brigades, lack of sample flow for the weekly tritium check, roof leaks, a radiation monitor out-of-service, and cork seam pump problems. | |||
The inspectors noted that there | |||
has been a good questioning attitude among licensee staff and a desire for continuous improvement. | |||
The licensee also conducted a review of all of their internal procedures associated with TMI-2. The licensee reviewed procedures for radiation protection, emergency preparedness, security, maintenance, environmental, chemistry, and operations. | The Nuclear Oversight audit conducted last year (July 26 - August 13, 2010) was very detailed and comprehensive. The licensee also conducted a review of all of their internal procedures associated with TMI-2. The licensee reviewed procedures for radiation protection, emergency preparedness, security, maintenance, environmental, chemistry, and operations. Procedures were up-to-date and adequate for PDMS. | ||
Another ongoing effort is an initiative by Emergency Preparedness to ensure that personnel working in TMI-2 will be able to hear personnel announcements in the event of an emergency. | |||
====c. Conclusions==== | ====c. Conclusions==== | ||
The licensee's self-assessment, auditing, and corrective action programs were effective at identifying, resolving, and preventing problems. | The licensee's self-assessment, auditing, and corrective action programs were effective at identifying, resolving, and preventing problems. ARs were properly prioritized and corrective actions were tracked in accordance with approved procedures. No findings of safety significance were identified. | ||
ARs were properly prioritized and corrective actions were tracked in accordance with approved procedures. | |||
No findings of safety significance were identified. | |||
5.0 Decommissioning Performance and Status Review | 5.0 Decommissioning Performance and Status Review | ||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
(IP 71801) The inspectors reviewed the licensee's current decommissioning status with respect to the TMI-2 PDMS QA Plan. | (IP 71801) | ||
The inspectors reviewed the licensee's current decommissioning status with respect to the TMI-2 PDMS QA Plan. | |||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
The total special nuclear material inventory is less than 1,086 kilograms. | The total special nuclear material inventory is less than 1,086 kilograms. The three locations with the highest activities are: the reactor vessel with approximately 925 kilograms, the reactor coolant bleed tank room with 3.5 kilograms, and the "A" spent fuel pool with 3.8 kilograms of special nuclear material. | ||
The three locations with the highest activities are: the reactor vessel with approximately 925 kilograms, the reactor coolant bleed tank room with 3.5 kilograms, and the "A" spent fuel pool with 3.8 kilograms of special nuclear material | |||
Since TMI-1 's license was recently renewed for an additional 20 years of operation, the licensee is in discussions with the NRC staff to extend the expiration date of the TMI-2 NRC license. The TMI-2 license currently expires in 2014. | The licensee plans to actively decommission TMI-2 in parallel with the decommissioning of TMI-1 after that unit has been permanently shutdown. Since TMI-1 's license was recently renewed for an additional 20 years of operation, the licensee is in discussions with the NRC staff to extend the expiration date of the TMI-2 NRC license. The TMI-2 license currently expires in 2014. | ||
====c. Conclusions==== | ====c. Conclusions==== | ||
There has been no dismantlement or decommissioning activities performed since the previous inspection. | There has been no dismantlement or decommissioning activities performed since the previous inspection. No findings of safety significance were identified. | ||
No | Inspection Report No. 05000320/2011008 G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOS.docx | ||
6.0 Maintenance and Surveillance at PSRs | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
(lP 62801) The inspectors reviewed the licensee's preventive maintenance (PM) and surveillance test (ST) program for structures, systems, and components important for maintaining the safe storage of radioactive material and the implementation of primary containment isolation requirements, TS 3/4.1, Containment Systems. Specifically, the inspectors evaluated the licensee's implementation of the maintenance program associated with the containment isolation. | (lP 62801) | ||
The inspectors reviewed the licensee's preventive maintenance (PM) and surveillance test (ST) program for structures, systems, and components important for maintaining the safe storage of radioactive material and the implementation of primary containment isolation requirements, TS 3/4.1, Containment Systems. Specifically, the inspectors evaluated the licensee's implementation of the maintenance program associated with the containment isolation. The inspectors toured the containment isolation system and the reactor building atmospheric breather system. The inspectors observed the licensee perform select STs associated with the cork seam and ventilation system. The inspectors reviewed selected STs, toured plant areas, and discussed aspects of the STs with individuals cognizant of the performance of the above systems and components. | |||
The inspectors toured the containment isolation system and the reactor building atmospheric breather system. The inspectors observed the licensee perform select STs associated with the cork seam and ventilation system. The inspectors reviewed selected STs, toured plant areas, and discussed aspects of the STs with individuals cognizant of the performance of the above systems and components. | |||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
| Line 145: | Line 135: | ||
During a tour of TMI-2, the inspectors observed new fire protection equipment (including acquisition of fire extinguishers and the installation of a fire resistance wire known as Protectowire thermal detection systems) throughout the plant and noted that housekeeping has eliminated combustibles. | During a tour of TMI-2, the inspectors observed new fire protection equipment (including acquisition of fire extinguishers and the installation of a fire resistance wire known as Protectowire thermal detection systems) throughout the plant and noted that housekeeping has eliminated combustibles. | ||
Operations personnel demonstrated how they conduct their containment isolation surveillance. | Operations personnel demonstrated how they conduct their containment isolation surveillance. The inspectors verified the containment isolation valves were properly tagged and locked. There are approximately 200 containment isolation valves, 15 containment isolation flanges, three pipe caps, and two personnel hatches that make up the containment isolation system. Every five years on an annual staggered test basis, the licensee visually inspected the bolted or welded blind flanges which form a containment isolation boundary and the equipment hatch for signs of degradation and/or leakage. The licensee monitored the four open Reactor Breather isolation valves for releases. | ||
The inspectors verified the containment isolation valves were properly tagged and locked. There are approximately 200 containment isolation valves, 15 containment isolation flanges, three pipe caps, and two personnel hatches that make up the containment isolation system. Every five years on an annual staggered test basis, the licensee visually inspected the bolted or welded blind flanges which form a containment isolation boundary and the equipment hatch for signs of degradation and/or leakage. The licensee monitored the four open Reactor Breather isolation valves for releases. | |||
On two separate occasions during the inspection, Operations personnel demonstrated how they remove water from a cork seam and how they record the pressure difference for the filters associated with the Auxiliary and Fuel Handling*buildings exhaust heating and ventilation system. In each case, licensee personnel used the correct procedure, followed the procedure, documented their measurements, and successfully demonstrated their ability to perform the task correctly. | On two separate occasions during the inspection, Operations personnel demonstrated how they remove water from a cork seam and how they record the pressure difference for the filters associated with the Auxiliary and Fuel Handling*buildings exhaust heating and ventilation system. In each case, licensee personnel used the correct procedure, followed the procedure, documented their measurements, and successfully demonstrated their ability to perform the task correctly. | ||
====c. Conclusions==== | ====c. Conclusions==== | ||
The licensee effectively implemented the preventive maintenance and surveillance program and associated procedures. | The licensee effectively implemented the preventive maintenance and surveillance program and associated procedures. No findings of safety significance were identified. | ||
No | Inspection Report No. 05000320/2011008 G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011008.docx | ||
7.0 Occupational Radiation Exposure | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
(IP 83750) The inspectors evaluated the implementation of the occupational exposure control program associated with the TMI-2 PDMS activities. | (IP 83750) | ||
The inspectors evaluated the implementation of the occupational exposure control program associated with the TMI-2 PDMS activities. The inspectors reviewed occupational exposure reports for calendar year 2010 and the most current data for 2011. The inspectors reviewed the key control process for locked high and very high radiation areas with Radiation Protection personnel. The inspection consisted of interviews with responsible individuals and observations of radiological postings and signs in radiologically controlled areas. | |||
The inspectors reviewed occupational exposure reports for calendar year 2010 and the most current data for 2011. The inspectors reviewed the key control process for locked high and very high radiation areas with Radiation Protection personnel. | |||
The inspection consisted of interviews with responsible individuals and observations of radiological postings and signs in radiologically controlled areas. | |||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
In calendar year 2010, the collective exposure was 364 mrem. As of June 30, 2011, the collective exposure was 267 mrem. The largest contribution was obtained in April, during the annual reactor building containment entry. In 2010, this entry accounted for 266 of the 364 mrem exposure. | In calendar year 2010, the collective exposure was 364 mrem. As of June 30, 2011, the collective exposure was 267 mrem. The largest contribution was obtained in April, during the annual reactor building containment entry. In 2010, this entry accounted for 266 of the 364 mrem exposure. In 2011, the collective exposure for this entry was 181 mrem. The licensee informed the inspectors that they are reconsidering an annual entry based on ALARA and that the data obtained from the previous entries has shown little change or degradation of the integrity of the reactor building. | ||
In 2011, the collective exposure for this entry was 181 mrem. The licensee informed the inspectors that they are reconsidering an annual entry based on ALARA and that the data obtained from the previous entries has shown little change or degradation of the integrity of the reactor building | |||
The licensee | On April 20, 2011, 15 individuals entered the reactor building containment, which is posted as Grave Danger Very High Radiation Area. The ALARA post-job review noted that they received 0.171 person-rem. This was slightly more than the 0.149 person-rem estimated, but within the regulatory dose limits. The licensee showed the inspectors the photographs that were taken during the last reactor containment entry in April 2011, which clearly demonstrated the continued use of shielding and appropriate labeling of radiological control areas. | ||
This will be accomplished by September 2011. | The licensee used a check form to verify that all locked high and very high radiation areas keys were maintained and secured. The licensee maintained strict control of the Very High Radiation Area keys and the Locked High Radiation Area keys. Radiation Protection personnel informed the inspectors that they vigorously challenge the latching mechanism in order to ensure that the actual locked conditions exist. Radiation Protection personnel also verified that there were effective barriers in place to prevent unauthorized entry into these areas as well as proper postings. The licensee is currently replacing their caution radiation postings with newly acquired postings. This will be accomplished by September 2011. | ||
====c. Conclusions==== | ====c. Conclusions==== | ||
The licensee effectively implemented the occupational exposure control program associated with the TMI-2 PDMS activities. | The licensee effectively implemented the occupational exposure control program associated with the TMI-2 PDMS activities. The licensee maintained occupational radiation exposures ALARA. No findings of safety significance were identified. | ||
Inspection Report No. 05000320/2011008 G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx | |||
8.0 Effluent and Environmental Monitoring | |||
====a. Inspection Scope==== | ====a. Inspection Scope==== | ||
(lP 84750) The inspectors reviewed the radioactive effluent control program and the site radiological environmental monitoring program. The evaluation included a review of the annual radioactive effluent release report for 2010, the annual radiological environmental operating report for 2010, and the associated analytical results for each. | (lP 84750) | ||
The inspectors reviewed the radioactive effluent control program and the site radiological environmental monitoring program. The evaluation included a review of the annual radioactive effluent release report for 2010, the annual radiological environmental operating report for 2010, and the associated analytical results for each. | |||
====b. Observations and Findings==== | ====b. Observations and Findings==== | ||
The licensee analyzed liquid and gaseous effluent releases, as well as fish, sediment, and cow milk samples to compile their radiological environmental monitoring and operating reports. The Off-Site Dose Calculation Manual used to arrive at their conclusion was revised on December 14, 2010 as part of the licensee's initiative to maintain up-to-date procedures using the latest guidance available. | The licensee analyzed liquid and gaseous effluent releases, as well as fish, sediment, and cow milk samples to compile their radiological environmental monitoring and operating reports. The Off-Site Dose Calculation Manual used to arrive at their conclusion was revised on December 14, 2010 as part of the licensee's initiative to maintain up-to-date procedures using the latest guidance available. The licensee's annual effluent and environmental monitoring reports demonstrated that all calculated doses were well below regulatory dose criteria of 10 CFR 50, Appendix I. | ||
The licensee's annual effluent and environmental monitoring reports demonstrated that all calculated doses were well below regulatory dose criteria of 10 CFR 50, Appendix I. | |||
====c. Conclusions==== | ====c. Conclusions==== | ||
| Line 197: | Line 175: | ||
===Exit Meeting Summary=== | ===Exit Meeting Summary=== | ||
On July 28, 2011, the inspectors presented the inspection results to Mr. Michael Casey, Responsible Engineer, FirstEnergy/GPU Nuclear and other members of your organization, and members of the Exelon management and staff. The inspectors confirmed that proprietary information was not removed from the site. | On July 28, 2011, the inspectors presented the inspection results to Mr. Michael Casey, Responsible Engineer, FirstEnergy/GPU Nuclear and other members of your organization, and members of the Exelon management and staff. The inspectors confirmed that proprietary information was not removed from the site. | ||
Inspection Report No. 05000320/2011008 G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOS.docx | |||
PARTIAL LIST OF PERSONS CONTACTED LICENSEE STATE NRC R. Libra M. Ford J. Francis Boyd M. Casey B. Carn J. Flora D. Knaby R. Freeman L. Weber D.Neff K. Oster D. Windle T. Haaf J. Grove M. Fitzwater E. Schmeichel T. Van Wynn T. Geyer K. Pedersen D. Dykman D. Werkheiser J. Buckley Plant Manager PDMS Manager PDMS Sr. Specialist FENOC engineer/Senior Consultant Radiation Protection Radiation Protection Radiation Protection Chemistry Environmental chemist Emergency Preparedness Operations Operations Operations Regulatory Assurance Regulatory Assurance NOS Lead /Acting Manager Training Employee Concerns Program Site Representative Employee Concerns Investigator with Exelon Corporate Commonwealth of Pennsylvania Senior Resident Inspector NRC HO, Project Manager for TMI-2 | |||
=SUPPLEMENTAL | =SUPPLEMENTAL INFORMATION= | ||
INFORMATION= | |||
None. INSPECTION | None. | ||
PROCEDURES | INSPECTION PROCEDURES USED | ||
36801 Organization, Management, and Cost Controls at Permanently Shutdown Reactors | |||
Shutdown Reactors 37801 Safety Reviews, Design Changes, and Modifications | 37801 Safety Reviews, Design Changes, and Modifications at PSRs | ||
at PSRs 40801 Self Assessment | 40801 Self Assessment and Corrective Action at PSRs | ||
and Corrective | 2801 Maintenance and Surveillance at PSRs | ||
Action at PSRs | 71801 Decommissioning Performance and Status Reviews at PSRs | ||
and Surveillance | 83750 Occupational Radiation Exposure | ||
at PSRs 71801 Decommissioning | 84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring | ||
Performance | Inspection Report No. 05000320/2011008 | ||
and Status Reviews at PSRs 83750 Occupational | G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx | ||
Radiation | |||
Waste Treatment | |||
and Effluent and Environmental | |||
Monitoring | |||
Inspection | |||
Report No. 05000320/2011008 | |||
G:\WordDocs\Current\lnsp | |||
Report\RDPR-73 | |||
2011 OOB.docx | |||
ITEMS OPEN. CLOSED. AND DISCUSSED | ITEMS OPEN. CLOSED. AND DISCUSSED | ||
Opened, Closed and Discussed | Opened, Closed and Discussed - None. | ||
-None. LIST OF DOCUMENTS | LIST OF DOCUMENTS REVIEWED | ||
Electric Insurance Limited Property Loss Control Comprehensive Evaluation Report April 2011 | |||
Limited Property Loss Control Comprehensive | TMI Unit 2 collective exposure for 2010 and 2011 | ||
Evaluation | ALARA Post-Job Review for Unit -2 Reactor Bldg Annual PDMS Survey and Unit-2 | ||
Report April 2011 TMI Unit 2 collective | Management Inspection dated April 26, 2011 | ||
exposure for 2010 and 2011 ALARA Post-Job Review for Unit -2 Reactor Bldg Annual PDMS Survey and Unit-2 Management | Biennial 10 CFR 50.59 and PDMS SAR Report dated February 15, 2010 | ||
Inspection | Technical Specifications for PDMS - Amendment 63 for License 50-320 issued May 1,2009 | ||
dated April 26, 2011 Biennial 10 CFR 50.59 and PDMS SAR Report dated February 15, 2010 Technical | Locked High Radiation Area Control Check Form dated December 19, 2009 | ||
Specifications | Fleet Oversight Audit Report: TMI-C-11-04-28 dated April 2011 | ||
for PDMS -Amendment | Releasing Radioactive Gaseous Effluents - TMI-2 Reactor Building - Radiological Controls | ||
for License 50-320 issued May 1,2009 Locked High Radiation | Procedure 661 0-ADM-4250.14 Revision 5 effective dated April 14, 2010 | ||
Area Control Check Form dated December 19, 2009 Fleet Oversight | Combined 2010 Annual Radioactive Effluent Release Report dated April 27, 2010 | ||
Audit Report: TMI-C-11-04-28 | Various surveillance tests from April 22, 2010 - July 27, 2011 such as: | ||
dated April 2011 Releasing | RMS Calibrations - Surveillance Test Procedure No. 2303-4.15E dated: 7/23/10,8/3/10, | ||
Radioactive | 9/2/10,1/15/11,3/10111,5/11/11, and 6/4111 | ||
Gaseous Effluents | Actual surveillance test conducted on 5/11/2011 for Flow Alarm Check of TMI-2 | ||
-TMI-2 Reactor Building -Radiological | Atmospheric RMS monitors procedure 2303-4.15E revision 5, dated 11/11/10 | ||
Actual surveillance test conducted on 614/11 for PDMS RMS (Victoreen) Functional test | |||
661 0-ADM-4250.14 | procedure no. 2303-4.15A Revision 12, dated 10105/10 | ||
Revision 5 effective | Actual surveillance test conducted on 3/10/11 for Flow and Vacuum Calibrations for TMI | ||
dated April 14, 2010 Combined 2010 Annual Radioactive | Atmospheric Effluent Radiation Monitors Procedure No. 1302-3.40, Revision 4 | ||
Effluent Release Report dated April 27, 2010 Various surveillance | Actual surveillance test conducted on 7/23/10, 8/3/10, 9/2/10 and 1/15/11 for Calibration | ||
tests from April 22, 2010 -July 27, 2011 such as: RMS Calibrations | of TMI-2 RMS Particulate Channels Procedure No. MA-2TM-2662-201 Revision 0 | ||
-Surveillance | Actual surveillance test conducted on 6/2/10 for Reactor Building Purge Exhaust Filter | ||
Test Procedure | InspectlDOP test; Surveillance test procedure No. 2303-11.14 Revision 5, dated | ||
No. 2303-4.15E | 11/01/02 | ||
dated: 7/23/10,8/3/10, 9/2/10,1/15/11,3/10111,5/11/11, and 6/4111 Actual surveillance | Test conducted on 5/18/2010 and 4/18/11 for Reactor Building Breather Filter Analysis | ||
test conducted | Inspection Report No. 05000320/2011008 | ||
on 5/11/2011 | G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx | ||
for Flow Alarm Check of TMI-2 Atmospheric | Surveillance test Procedure No. 2301-4.70, Revision 8, dated 3/27/09 | ||
RMS monitors procedure | Test conducted on 4/20/11 for Reactor Building Survey Surveillance test procedure No. | ||
2303-4.15E | 2301-4.3 Revision 5 | ||
revision 5, dated 11/11/10 Actual surveillance | Test conducted on 4/19/11 for reactor Building Purge Exhaust Filter Operations Check | ||
test conducted | procedure no. 2303-5.10 Revision 6, dated 9/24/02 | ||
on 614/11 for PDMS RMS (Victoreen) | Tests conducted 6/7110, 1216/10, and 6113/11 for Aux bldg Ventilation Air Cleanup | ||
Functional | Operational Check procedure no. OP-2TM-2829-201 Revision 0 | ||
Test conducted 6/13/11 for Fuel Handling Bldg Air Cleanup Operational Check | |||
no. 2303-4.15A | procedure no. 2303-5.9 Revision 10 | ||
Revision 12, dated 10105/10 Actual surveillance | Test conducted on 4/30/11 for Operability Check of the TMI-2 Equipment Hatch | ||
test conducted | Personnel Airlock Doors, procedure No. 2303-11.20A Revision 5 dated 10/13/08 | ||
on 3/10/11 for Flow and Vacuum Calibrations | Test conducted on 4/30/11 for Operability Check of the TMI-2 Ante Room Personnel | ||
for TMI Atmospheric | Airlock Doors, procedure No. 2303-11.20B Revision 5 dated 10/13/08 | ||
Effluent Radiation | Test conducted on 7/10/10 for Ventilation Filter DOP & Halide Testing, Procedure | ||
Monitors Procedure | No. U-36 Revision 14A | ||
No. 1302-3.40, Revision 4 Actual surveillance | Test conducted on 7/10/10 for TMI-2 Soiled Exhaust Filter Train Efficiency Test, | ||
test conducted | procedure No. 2303-11.57, Revision 0 dated 9/19/02 | ||
on 7/23/10, 8/3/10, 9/2/10 and 1/15/11 for Calibration | Tests conducted on 6/14/10 and 6/13/11 for TMI-2 Soiled Exhaust Filter Train | ||
of TMI-2 RMS Particulate | Operational Check, procedure No. 2303-5.11, Revision 0 dated 9/12/02 | ||
Channels Procedure | Test conducted on 1/18/11 for TMI-2 Auxiliary and Fuel Handling Building POMS | ||
No. MA-2TM-2662-201 | Radiological Surveys, procedure No. 2301-4.2, Revision 8, dated 5/12/04 | ||
Revision 0 Actual surveillance | Test conducted on 7/21/10 for POMS - Remote Area Inspection Procedure | ||
test conducted | No. 20PS-S020, Revision 2, dated 7/27/04 | ||
on 6/2/10 for Reactor Building Purge Exhaust Filter InspectlDOP | POMS TMI-2 Daily Checks Procedure No. 2301-1 Revision 21 dated 1/15/11,2/14/11, | ||
test; Surveillance | 3/15/11, 4/15/11, 6/15/11, and 7/13/11 | ||
test procedure | TMI-2 vent sampling weekly and monthly composite reports dated 12/31/10, 2112111, | ||
No. 2303-11.14 | 5/14/11, and 7/9111 TMI-2 Vent Sampling Procedure No. 2301-4.7 Revision 18, dated | ||
Revision 5, dated 11/01/02 Test conducted | 10/11/06 | ||
on 5/18/2010 | Tests conducted on 7/21/10,10113/10,1/19/11, and 4/20/11 for Verification ofTMI-2 | ||
and 4/18/11 for Reactor Building Breather Filter Analysis | Containment Isolation, procedure No. OP-2TM-2244-201, Revision 0 | ||
Report No. 05000320/2011008 | Issue Report Nos. 01088266 and 01088266 | ||
G:\WordDocs\Current\lnsp | Inspection Report No. 05000320/2011008 | ||
Report\RDPR-73 | G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx | ||
2011 OOB.docx | Action Reports Nos. | ||
Surveillance | AR 01062052 | ||
test Procedure | AR 01121145 | ||
No. 2301-4.70, Revision 8, dated 3/27/09 Test conducted | AR 01111195 | ||
on 4/20/11 for Reactor Building Survey Surveillance | AR 01100971 | ||
test procedure | AR 01101025 | ||
No. 2301-4.3 Revision 5 Test conducted | AR 01177620 | ||
on 4/19/11 for reactor Building Purge Exhaust Filter Operations | AR 01101009 | ||
AR 01080691 | |||
no. 2303-5.10 | AR 01210935 | ||
Revision 6, dated 9/24/02 Tests conducted | AR 01101015 | ||
6/7110, 1216/10, and 6113/11 for Aux bldg Ventilation | AR 01092576 | ||
Air Cleanup Operational | AR 01244013 | ||
Check procedure | LIST OF ACRONYMS USED | ||
no. OP-2TM-2829-201 | ALARA | ||
Revision 0 Test conducted | AR | ||
6/13/11 for Fuel Handling Bldg Air Cleanup Operational | CNRB | ||
DOP | |||
no. 2303-5.9 Revision 10 Test conducted | ECP | ||
on 4/30/11 for Operability | FENOC | ||
Check of the TMI-2 Equipment | GPUN | ||
IMC | |||
Airlock Doors, procedure | IP | ||
No. 2303-11.20A | IR | ||
Revision 5 dated 10/13/08 Test conducted | NOS | ||
on 4/30/11 for Operability | NRC | ||
Check of the TMI-2 Ante Room Personnel | NRCHQ | ||
Airlock Doors, procedure | PDMS | ||
No. 2303-11.20B | PDMS Plan | ||
Revision 5 dated 10/13/08 Test conducted | PM | ||
on 7/10/10 for Ventilation | PSR | ||
Filter DOP & Halide Testing, Procedure | QA | ||
No. U-36 Revision 14A Test conducted | RMS | ||
on 7/10/10 for TMI-2 Soiled Exhaust Filter Train Efficiency | SAR | ||
Test, procedure | SSC | ||
No. 2303-11.57, Revision 0 dated 9/19/02 Tests conducted | ST | ||
on 6/14/10 and 6/13/11 for TMI-2 Soiled Exhaust Filter Train Operational | TMI | ||
Check, procedure | TMI-1 | ||
No. 2303-5.11, Revision 0 dated 9/12/02 Test conducted | TMI-2 | ||
on 1/18/11 for TMI-2 Auxiliary | TS | ||
and Fuel Handling Building POMS Radiological | as low as reasonably achievable | ||
Surveys, procedure | action report | ||
No. 2301-4.2, Revision 8, dated 5/12/04 Test conducted | Company Nuclear Review Board | ||
on 7/21/10 for POMS -Remote Area Inspection | dioctyl phthalate | ||
Procedure | employee concerns program | ||
No. 20PS-S020, Revision 2, dated 7/27/04 POMS TMI-2 Daily Checks Procedure | FirstEnergy Nuclear Operating Company | ||
No. 2301-1 Revision 21 dated 1/15/11,2/14/11, 3/15/11, 4/15/11, 6/15/11, and 7/13/11 TMI-2 vent sampling weekly and monthly composite | GPU Nuclear, Inc. | ||
reports dated 12/31/10, 2112111, 5/14/11, and 7/9111 TMI-2 Vent Sampling Procedure | Inspection Manual Chapter | ||
No. 2301-4.7 Revision 18, dated 10/11/06 Tests conducted | Inspection Procedure | ||
on 7/21/10,10113/10,1/19/11, and 4/20/11 for Verification | issue report | ||
ofTMI-2 Containment | Nuclear Oversight | ||
Isolation, procedure | Nuclear Regulatory Commission | ||
No. OP-2TM-2244-201, Revision 0 Issue Report Nos. 01088266 and 01088266 | Nuclear Regulatory Commission headquarters | ||
Report No. 05000320/2011008 | Post-Defueling Monitored Storage | ||
G:\WordDocs\Current\lnsp | PDMS Quality Assurance (QA) Plan | ||
Report\RDPR-73 | preventive maintenance | ||
2011 OOB.docx | Permanently Shutdown Reactor | ||
Action Reports Nos. AR 01062052 AR 01121145 AR 01111195 AR 01100971 AR 01101025 AR 01177620 AR 01101009 AR 01080691 AR 01210935 AR 01101015 AR 01092576 AR 01244013 LIST OF ACRONYMS USED ALARA AR CNRB DOP ECP FENOC GPUN IMC IP | quality assurance | ||
IR NOS NRC NRCHQ PDMS PDMS Plan PM PSR QA RMS SAR SSC ST TMI | |||
TMI-1 TMI-2 TS as low as reasonably | |||
achievable | |||
action report Company Nuclear Review Board dioctyl phthalate | |||
employee concerns program FirstEnergy | |||
Nuclear Operating | |||
Manual Chapter Inspection | |||
Procedure | |||
issue report Nuclear Oversight | |||
Nuclear Regulatory | |||
Commission | |||
Nuclear Regulatory | |||
Commission | |||
headquarters | |||
Post-Defueling | |||
Monitored | |||
maintenance | |||
Permanently | |||
Shutdown Reactor quality assurance | |||
radiation monitoring system | radiation monitoring system | ||
Safety Analysis Report structures, systems, or components | Safety Analysis Report | ||
surveillance | structures, systems, or components | ||
surveillance test | |||
specification | Three Mile Island Station | ||
Inspection | Three Mile Island Station, Unit 1 | ||
Report No. 05000320/2011008 | Three Mile Island Station, Unit 2 | ||
G:\WordDocs\Current\lnsp | technical specification | ||
Report\RDPR-73 | Inspection Report No. 05000320/2011008 | ||
2011 OOB.docx | G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx | ||
}} | }} | ||
Latest revision as of 02:23, 13 January 2025
| ML112370120 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/25/2011 |
| From: | Division of Nuclear Materials Safety I |
| To: | |
| References | |
| IR-11-008 | |
| Download: ML112370120 (12) | |
Text
Inspection N Docket N License N Licensee:
Address:
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
INSPECTION REPORT 05000320/2011008 05000320 DPR-73 GPU Nuclear, In White Pond Drive Akron, OH 44320 Locations Inspected:
Three Mile Island Station, Unit 2 Middletown, PA 17057-0791 Inspection Dates:
Inspectors:
Approved By:
July 25-28, 2011 Laurie A. Kauffman Health Physicist Decommissioning Branch Division of Nuclear Materials Safety Kathy Modes Senior Health Physicist Decommissioning Branch Division of Nuclear Materials Safety Judith A. Joustra, Chief Decommissioning Branch Division of Nuclear Materials Safety Document Name: G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx
EXECUTIVE SUMMARY
GPU Nuclear, Inc.
NRC Inspection Report No. 05000320/2011008 A routine announced safety inspection was conducted on July 25-28, 2011, at the Three Mile Island Station, Unit 2 (TMI-2) by two Region I inspectors. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561, "Decommissioning Power Reactor Inspection Program." The inspection included a review of operations and management oversight, maintenance, corrective action program implementation, and plant support activities while in Post Defueling Monitored Storage (PDMS) status. Within the scope of this inspection, no safety concerns or violations were identified. The conclusions from each inspection area are presented below.
Organization, Management & Cost Control The licensee has process controls, and an organization to effectively implement license requirements.
Safety Reviews, Design Changes, and Modifications The licensee implemented a safety review program to maintain decommissioning safety and the facility configuration as described in their licensing basis.
Self-Assessment, Auditing, and Corrective Action Programs The licensee's self-assessment, auditing, and corrective action programs were effective at identifying, resolving, and preventing problems. Action reports were properly prioritized and corrective actions were tracked in accordance with approved procedures.
Decommissioning Performance and Status Reviews at Permanently Shutdown Reactors (PSRs)
There has been no dismantlement or decommissioning activities performed since the previous inspection.
Maintenance and Surveillance The licensee effectively implemented the preventive maintenance and surveillance program and associated procedures.
Occupational Radiation Exposure The licensee effectively implemented the occupational exposure control program associated with the TMI-2 PDMS activities. The licensee maintained occupational radiation exposures as low as reasonably achievable (ALARA).
Effluent and Environmental Monitoring The licensee effectively implemented and maintained the radioactive effluent controls program and the radiological environmental monitoring program.
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REPORT DETAILS
1.0
. Background Information In December 1993, TMI-2 received a license from the NRC to enter Post Defueling Monitored Storage (PDMS). TMI-2 today is in long-term monitored storage. No further use of the nuclear part of the plant is anticipated. Ventilation and rainwater systems continue to be monitored.
Equipment necessary to keep the plant in safe long-term storage continued to be maintained.
The licensee plans to actively decommission TMI-2 in parallel with the decommissioning of the Three Mile Island, Unit 1 (TMI-1) after unit has been permanently shutdown.
2.0 Organization, Management & Cost Controls
a. Inspection Scope
(Inspection Procedures (lP) 36801)
The inspectors evaluated any recent organization, management and staffing changes with respect to the PDMS Quality Assurance (QA) program outlined in the PDMS QA Plan. The inspectors reviewed Action Reports, interviewed Employee Concerns Program personnel, and reviewed Company Nuclear Review Board meeting minutes.
b. Observations and Findings
In early 2010, Exelon appointed a new PDMS Manager and PDMS Senior Specialist who have over 20 years of experience working at TMI. The inspectors determined that these individuals were cognizant of the TMI-2 process controls and license requirements. With a change in personnel, the licensee continued to maintain important records and history of the plant needed to support future decommissioning of TMI-2.
Action Report No. 01100971, "TMI-2 FENOC and EXELON Employee Concerns Program (ECP) Enhancements" describes the licensee's continued commitment to safety culture. ECP personnel provided details about the licensee commitment to maintain a high level of awareness to safety. The Company Nuclear Review Board (CNRB) meeting minutes demonstrated that the CNRB was attentive to the ECP.
Personnel from electrical, radiation protection, operations, radioactive waste, chemistry, security, maintenance, housekeeping, and quality assurance enter TMI-2 through the course of their normal work duties. Even though the facility is in a PDMS status, there are adequate resources available to ensure the licensee is meeting their licensing basis.
c. Conclusions
The licensee has process controls, and an organization to effectively implement license requirements. No findings of safety significance were identified.
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3.0 Safety Reviews, Design Changes, and Modifications
a. Inspection Scope
(lP 37801)
The inspectors reviewed a random sample of PDMS procedures to verify the licensee implements a safety review program that effectively maintains decommissioning safety and the facility configuration as described in their licensing basis.
b. Observations and Findings
The licensee updated their PDMS procedures to reflect current plant configuration and administrative processes, and to make some editorial changes. The typical categories of procedures that were changed were administrative, ventilation, electrical distribution, radioactive waste processing, fire protection, compressed air, and Technical Specification surveillance. Due to the non-operating and defueled status of TMI-2 during PDMS, there are no structures, systems, or components (SSC) that are required to meet the safety-related criteria. Therefore, there are no SSC classified as safety-related at TMI-2. All procedure changes and facility modifications at TMI-2 are made using the Exelon 10 CFR 50.59 Review Process, which provides a screening process to determine if the change requires a written evaluation.
c. Conclusions
The licensee implemented a safety review program to maintain decommissioning safety and the facility configuration as described in their licensing basis. No findings of safety significance were identified.
4.0 Self-Assessment, Auditing, and Corrective Action
a. Inspection Scope
(lP 40801)
The inspectors reviewed the licensee's program for identifying, resolving, and preventing issues that could impact safety or the quality of future decommissioning activities. The inspectors reviewed the procedures describing the corrective action program and reviewed several issue reports (IRs), action reports (ARs), and the associated corrective actions. The inspectors discussed with cognizant personnel the tracking, current status, and closure of the selected IRs and ARs. The inspectors reviewed the August 2010 Nuclear Oversight (NOS) audit report and the April 2011 Fleet Oversight Audit Report (TMI-C-11-04-28).
b. Observations and Findings
The inspectors noted that there were approximately 178 ARs generated for TMI-2 and only 26 remained open at the time of the inspection. There were 61 ARs dealing with administrative issues, 17 that needed procedure changes, and 100 work orders generated. ARs were generated to address revision of plant procedures, effectiveness of fire brigades, lack of sample flow for the weekly tritium check, roof leaks, a radiation monitor out-of-service, and cork seam pump problems. The inspectors noted that there Inspection Report No. 05000320/2011008 G:\\WordDocs\\Current\\lnsp Report\\RDPR-73 2011 OOB.docx
has been a good questioning attitude among licensee staff and a desire for continuous improvement.
The Nuclear Oversight audit conducted last year (July 26 - August 13, 2010) was very detailed and comprehensive. The licensee also conducted a review of all of their internal procedures associated with TMI-2. The licensee reviewed procedures for radiation protection, emergency preparedness, security, maintenance, environmental, chemistry, and operations. Procedures were up-to-date and adequate for PDMS.
Another ongoing effort is an initiative by Emergency Preparedness to ensure that personnel working in TMI-2 will be able to hear personnel announcements in the event of an emergency.
c. Conclusions
The licensee's self-assessment, auditing, and corrective action programs were effective at identifying, resolving, and preventing problems. ARs were properly prioritized and corrective actions were tracked in accordance with approved procedures. No findings of safety significance were identified.
5.0 Decommissioning Performance and Status Review
a. Inspection Scope
(IP 71801)
The inspectors reviewed the licensee's current decommissioning status with respect to the TMI-2 PDMS QA Plan.
b. Observations and Findings
The total special nuclear material inventory is less than 1,086 kilograms. The three locations with the highest activities are: the reactor vessel with approximately 925 kilograms, the reactor coolant bleed tank room with 3.5 kilograms, and the "A" spent fuel pool with 3.8 kilograms of special nuclear material.
The licensee plans to actively decommission TMI-2 in parallel with the decommissioning of TMI-1 after that unit has been permanently shutdown. Since TMI-1 's license was recently renewed for an additional 20 years of operation, the licensee is in discussions with the NRC staff to extend the expiration date of the TMI-2 NRC license. The TMI-2 license currently expires in 2014.
c. Conclusions
There has been no dismantlement or decommissioning activities performed since the previous inspection. No findings of safety significance were identified.
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6.0 Maintenance and Surveillance at PSRs
a. Inspection Scope
(lP 62801)
The inspectors reviewed the licensee's preventive maintenance (PM) and surveillance test (ST) program for structures, systems, and components important for maintaining the safe storage of radioactive material and the implementation of primary containment isolation requirements, TS 3/4.1, Containment Systems. Specifically, the inspectors evaluated the licensee's implementation of the maintenance program associated with the containment isolation. The inspectors toured the containment isolation system and the reactor building atmospheric breather system. The inspectors observed the licensee perform select STs associated with the cork seam and ventilation system. The inspectors reviewed selected STs, toured plant areas, and discussed aspects of the STs with individuals cognizant of the performance of the above systems and components.
b. Observations and Findings
The inspectors determined that the licensee increased their attention to fire protection.
During a tour of TMI-2, the inspectors observed new fire protection equipment (including acquisition of fire extinguishers and the installation of a fire resistance wire known as Protectowire thermal detection systems) throughout the plant and noted that housekeeping has eliminated combustibles.
Operations personnel demonstrated how they conduct their containment isolation surveillance. The inspectors verified the containment isolation valves were properly tagged and locked. There are approximately 200 containment isolation valves, 15 containment isolation flanges, three pipe caps, and two personnel hatches that make up the containment isolation system. Every five years on an annual staggered test basis, the licensee visually inspected the bolted or welded blind flanges which form a containment isolation boundary and the equipment hatch for signs of degradation and/or leakage. The licensee monitored the four open Reactor Breather isolation valves for releases.
On two separate occasions during the inspection, Operations personnel demonstrated how they remove water from a cork seam and how they record the pressure difference for the filters associated with the Auxiliary and Fuel Handling*buildings exhaust heating and ventilation system. In each case, licensee personnel used the correct procedure, followed the procedure, documented their measurements, and successfully demonstrated their ability to perform the task correctly.
c. Conclusions
The licensee effectively implemented the preventive maintenance and surveillance program and associated procedures. No findings of safety significance were identified.
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7.0 Occupational Radiation Exposure
a. Inspection Scope
(IP 83750)
The inspectors evaluated the implementation of the occupational exposure control program associated with the TMI-2 PDMS activities. The inspectors reviewed occupational exposure reports for calendar year 2010 and the most current data for 2011. The inspectors reviewed the key control process for locked high and very high radiation areas with Radiation Protection personnel. The inspection consisted of interviews with responsible individuals and observations of radiological postings and signs in radiologically controlled areas.
b. Observations and Findings
In calendar year 2010, the collective exposure was 364 mrem. As of June 30, 2011, the collective exposure was 267 mrem. The largest contribution was obtained in April, during the annual reactor building containment entry. In 2010, this entry accounted for 266 of the 364 mrem exposure. In 2011, the collective exposure for this entry was 181 mrem. The licensee informed the inspectors that they are reconsidering an annual entry based on ALARA and that the data obtained from the previous entries has shown little change or degradation of the integrity of the reactor building.
On April 20, 2011, 15 individuals entered the reactor building containment, which is posted as Grave Danger Very High Radiation Area. The ALARA post-job review noted that they received 0.171 person-rem. This was slightly more than the 0.149 person-rem estimated, but within the regulatory dose limits. The licensee showed the inspectors the photographs that were taken during the last reactor containment entry in April 2011, which clearly demonstrated the continued use of shielding and appropriate labeling of radiological control areas.
The licensee used a check form to verify that all locked high and very high radiation areas keys were maintained and secured. The licensee maintained strict control of the Very High Radiation Area keys and the Locked High Radiation Area keys. Radiation Protection personnel informed the inspectors that they vigorously challenge the latching mechanism in order to ensure that the actual locked conditions exist. Radiation Protection personnel also verified that there were effective barriers in place to prevent unauthorized entry into these areas as well as proper postings. The licensee is currently replacing their caution radiation postings with newly acquired postings. This will be accomplished by September 2011.
c. Conclusions
The licensee effectively implemented the occupational exposure control program associated with the TMI-2 PDMS activities. The licensee maintained occupational radiation exposures ALARA. No findings of safety significance were identified.
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8.0 Effluent and Environmental Monitoring
a. Inspection Scope
(lP 84750)
The inspectors reviewed the radioactive effluent control program and the site radiological environmental monitoring program. The evaluation included a review of the annual radioactive effluent release report for 2010, the annual radiological environmental operating report for 2010, and the associated analytical results for each.
b. Observations and Findings
The licensee analyzed liquid and gaseous effluent releases, as well as fish, sediment, and cow milk samples to compile their radiological environmental monitoring and operating reports. The Off-Site Dose Calculation Manual used to arrive at their conclusion was revised on December 14, 2010 as part of the licensee's initiative to maintain up-to-date procedures using the latest guidance available. The licensee's annual effluent and environmental monitoring reports demonstrated that all calculated doses were well below regulatory dose criteria of 10 CFR 50, Appendix I.
c. Conclusions
The licensee effectively implemented and maintained the radioactive effluent controls program and the radiological environmental monitoring program. No findings of safety significance were identified.
Exit Meeting Summary
On July 28, 2011, the inspectors presented the inspection results to Mr. Michael Casey, Responsible Engineer, FirstEnergy/GPU Nuclear and other members of your organization, and members of the Exelon management and staff. The inspectors confirmed that proprietary information was not removed from the site.
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PARTIAL LIST OF PERSONS CONTACTED LICENSEE STATE NRC R. Libra M. Ford J. Francis Boyd M. Casey B. Carn J. Flora D. Knaby R. Freeman L. Weber D.Neff K. Oster D. Windle T. Haaf J. Grove M. Fitzwater E. Schmeichel T. Van Wynn T. Geyer K. Pedersen D. Dykman D. Werkheiser J. Buckley Plant Manager PDMS Manager PDMS Sr. Specialist FENOC engineer/Senior Consultant Radiation Protection Radiation Protection Radiation Protection Chemistry Environmental chemist Emergency Preparedness Operations Operations Operations Regulatory Assurance Regulatory Assurance NOS Lead /Acting Manager Training Employee Concerns Program Site Representative Employee Concerns Investigator with Exelon Corporate Commonwealth of Pennsylvania Senior Resident Inspector NRC HO, Project Manager for TMI-2
SUPPLEMENTAL INFORMATION
None.
INSPECTION PROCEDURES USED
36801 Organization, Management, and Cost Controls at Permanently Shutdown Reactors
37801 Safety Reviews, Design Changes, and Modifications at PSRs
40801 Self Assessment and Corrective Action at PSRs
2801 Maintenance and Surveillance at PSRs
71801 Decommissioning Performance and Status Reviews at PSRs
83750 Occupational Radiation Exposure
84750 Radioactive Waste Treatment and Effluent and Environmental Monitoring
Inspection Report No. 05000320/2011008
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ITEMS OPEN. CLOSED. AND DISCUSSED
Opened, Closed and Discussed - None.
LIST OF DOCUMENTS REVIEWED
Electric Insurance Limited Property Loss Control Comprehensive Evaluation Report April 2011
TMI Unit 2 collective exposure for 2010 and 2011
ALARA Post-Job Review for Unit -2 Reactor Bldg Annual PDMS Survey and Unit-2
Management Inspection dated April 26, 2011
Biennial 10 CFR 50.59 and PDMS SAR Report dated February 15, 2010
Technical Specifications for PDMS - Amendment 63 for License 50-320 issued May 1,2009
Locked High Radiation Area Control Check Form dated December 19, 2009
Fleet Oversight Audit Report: TMI-C-11-04-28 dated April 2011
Releasing Radioactive Gaseous Effluents - TMI-2 Reactor Building - Radiological Controls
Procedure 661 0-ADM-4250.14 Revision 5 effective dated April 14, 2010
Combined 2010 Annual Radioactive Effluent Release Report dated April 27, 2010
Various surveillance tests from April 22, 2010 - July 27, 2011 such as:
RMS Calibrations - Surveillance Test Procedure No. 2303-4.15E dated: 7/23/10,8/3/10,
9/2/10,1/15/11,3/10111,5/11/11, and 6/4111
Actual surveillance test conducted on 5/11/2011 for Flow Alarm Check of TMI-2
Atmospheric RMS monitors procedure 2303-4.15E revision 5, dated 11/11/10
Actual surveillance test conducted on 614/11 for PDMS RMS (Victoreen) Functional test
procedure no. 2303-4.15A Revision 12, dated 10105/10
Actual surveillance test conducted on 3/10/11 for Flow and Vacuum Calibrations for TMI
Atmospheric Effluent Radiation Monitors Procedure No. 1302-3.40, Revision 4
Actual surveillance test conducted on 7/23/10, 8/3/10, 9/2/10 and 1/15/11 for Calibration
of TMI-2 RMS Particulate Channels Procedure No. MA-2TM-2662-201 Revision 0
Actual surveillance test conducted on 6/2/10 for Reactor Building Purge Exhaust Filter
InspectlDOP test; Surveillance test procedure No. 2303-11.14 Revision 5, dated
11/01/02
Test conducted on 5/18/2010 and 4/18/11 for Reactor Building Breather Filter Analysis
Inspection Report No. 05000320/2011008
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Surveillance test Procedure No. 2301-4.70, Revision 8, dated 3/27/09
Test conducted on 4/20/11 for Reactor Building Survey Surveillance test procedure No.
2301-4.3 Revision 5
Test conducted on 4/19/11 for reactor Building Purge Exhaust Filter Operations Check
procedure no. 2303-5.10 Revision 6, dated 9/24/02
Tests conducted 6/7110, 1216/10, and 6113/11 for Aux bldg Ventilation Air Cleanup
Operational Check procedure no. OP-2TM-2829-201 Revision 0
Test conducted 6/13/11 for Fuel Handling Bldg Air Cleanup Operational Check
procedure no. 2303-5.9 Revision 10
Test conducted on 4/30/11 for Operability Check of the TMI-2 Equipment Hatch
Personnel Airlock Doors, procedure No. 2303-11.20A Revision 5 dated 10/13/08
Test conducted on 4/30/11 for Operability Check of the TMI-2 Ante Room Personnel
Airlock Doors, procedure No. 2303-11.20B Revision 5 dated 10/13/08
Test conducted on 7/10/10 for Ventilation Filter DOP & Halide Testing, Procedure
No. U-36 Revision 14A
Test conducted on 7/10/10 for TMI-2 Soiled Exhaust Filter Train Efficiency Test,
procedure No. 2303-11.57, Revision 0 dated 9/19/02
Tests conducted on 6/14/10 and 6/13/11 for TMI-2 Soiled Exhaust Filter Train
Operational Check, procedure No. 2303-5.11, Revision 0 dated 9/12/02
Test conducted on 1/18/11 for TMI-2 Auxiliary and Fuel Handling Building POMS
Radiological Surveys, procedure No. 2301-4.2, Revision 8, dated 5/12/04
Test conducted on 7/21/10 for POMS - Remote Area Inspection Procedure
No. 20PS-S020, Revision 2, dated 7/27/04
POMS TMI-2 Daily Checks Procedure No. 2301-1 Revision 21 dated 1/15/11,2/14/11,
3/15/11, 4/15/11, 6/15/11, and 7/13/11
TMI-2 vent sampling weekly and monthly composite reports dated 12/31/10, 2112111,
5/14/11, and 7/9111 TMI-2 Vent Sampling Procedure No. 2301-4.7 Revision 18, dated
10/11/06
Tests conducted on 7/21/10,10113/10,1/19/11, and 4/20/11 for Verification ofTMI-2
Containment Isolation, procedure No. OP-2TM-2244-201, Revision 0
Issue Report Nos. 01088266 and 01088266
Inspection Report No. 05000320/2011008
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Action Reports Nos.
AR 01121145
AR 01100971
AR 01177620
AR 01080691
AR 01101015
AR 01244013
LIST OF ACRONYMS USED
CNRB
GPUN
IMC
IP
IR
NOS
NRC
NRCHQ
PDMS
PDMS Plan
PSR
TMI-1
TMI-2
TS
as low as reasonably achievable
action report
Company Nuclear Review Board
dioctyl phthalate
employee concerns program
FirstEnergy Nuclear Operating Company
GPU Nuclear, Inc.
Inspection Manual Chapter
Inspection Procedure
issue report
Nuclear Oversight
Nuclear Regulatory Commission
Nuclear Regulatory Commission headquarters
Post-Defueling Monitored Storage
PDMS Quality Assurance (QA) Plan
preventive maintenance
Permanently Shutdown Reactor
quality assurance
radiation monitoring system
Safety Analysis Report
structures, systems, or components
surveillance test
Three Mile Island Station
Three Mile Island Station, Unit 1
Three Mile Island Station, Unit 2
technical specification
Inspection Report No. 05000320/2011008
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