IR 05000344/1996008
| ML20147E054 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 02/13/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20147E040 | List: |
| References | |
| 50-344-96-08, 50-344-96-8, 72-0017-96-02, 72-17-96-2, NUDOCS 9702180177 | |
| Download: ML20147E054 (15) | |
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ENCLOSURE l
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket Nos.:
50-344;72-17 i
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License No.:
NPF-1 Renort No.:
50-344/96-08;72-17/96-02 Licensee:
Portland General Electric Company
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Facility:
Trojan Nuclear Plant l
Location:
121 S. W. Salmon Street, TB-17
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Portland, Oregon Dates:
November 4-7,1996 Inspectors:
J. Vincent Everett, Health Physicist i
Michael T. Masnik, Ph. D., Project Manager i
Approved By:
D. Blair Spitzberg, Ph. D., Chief Nuclear Materials Licensing Branch l
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Attachment:
Supplemental Information i
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9702180177 970213
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PDR ADOCK 05000344 O
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-2-EXECUTIVE SUMMARY Trojan Nuclear Plant NRC Inspection Report 50-344/96-08;72-17/96-02 This inspection included aspects of the licensee's decommissioning activities related to the ongoing efforts to decontaminate the Trojan Nuclear Facility and place the spent fuelin storage at an on-site Independent Spent Fuel Storage Installation (ISFSI). Work is progressing on the decontamination of the facility. The four large reactor coolant pumps had been removed and were being packaged for shipment to Hanford for burial. Plans to establish an ISFSI continued to progress. The location selected by the licensee for the ISFSI had been determined by the NRC as acceptable.
A challenging scenario was developed for the 1996 exercise. Several off-site
support organizations participated in responding to the simulated events. All exercise objectives were successfully demonstrated except for coordination and preparation of news releases with offsite organizations. (Section 1).
Revisions to the emergency plan and notification procedures were reviewed during
this inspection and >und acceptable (Section 1).
The licensee conducted a final survey of the northeast corner of the industrial
security area where the ISFSI will be located. This survey was determined by the NRC to meet the requirements of 10 CFR 50.82. The surveyed area may be released from the 10 CFR Part 50 license for use as an ISFSIlicensed under 10 CFR Part 72 (Section 2).
A plant walkdown of the offgas treatment and ventilation system and the liquid
radwaste treatment and retention system were completed to verify operability and to ensure system components had not been taken out of service or dismantled (Section 3).
Radwaste being stored in the condensate demineralizer building was verified as
being properly posted. Radiation levels were below 0.5 mR/hr outside the roped off areas (Section 3).
A review was completed of the Offsite Dose Calculation Manual (ODCM),
Radiological Environmente' Mitoring Grogram,1995 Radiological Environmental Monitoring Report, and the environmental sampling and analysis program. All programs were found to comply with the Trojan Technical Specifications (Section 4).
Health physics practices related to the decommissioning work continued to be
effective in minimizing radiation problems and preventing contamination spread in the f acility (Section 5).
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-3-Inspection followup was completed for three violations and one inspection followup
item, in addition, completion of the corrective actions related to the June 6,1996 Notice of Violation and Civil Penalty were reviewed (Section 6).
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The local public document room at the Bradford Price Miller Library, Portland State
University, Portland, Oregon, was visited to confirm the availability of Trojan information. The local public document room was found to be in acceptable condition (Section 7).
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-4-Report Details Summary of Plant Status Work on decontaminating selected areas of the Trojan facility were progressing on schedule with few radiologically related problems. Work activities appeared to be safely conducted with good controls being implemented on contaminated materials. Fire loading in areas toured during this inspection was found to be minimal. Selected radwaste systems were verified as operable through a walkdown of the systems. The control room operator who conducted the walkdown demonstrated a comprehensive knowledge of the systems and their function.
Activities related to the Independent Spent Fuel Storage Installation 0@SI) were progressing. The final survey of the location where the ISFSI will be built was completed.
The NRC confirmatory survey verified the adequacy of the licensee's survey. The NRC, subsequent to this inspection, determined that the release of the surveyed area from the 10 CFR Part 50 license and transfer to the 10 CFR Part 72 ISFSIlicense would be acceptable. This was communicated to PGE by letter dated November 26,1996.
Three major projects were being planned by the licensee. The first was the Spent Fuel Pool Debris Project. This project involved the characterization, processing and packaging of spent fuel pellets from damaged fuel, welding dross from previous core barrel modifications, other nonfuel bearing components, and organic (plastic) filter material. The material will be processed in a steam reformer system using 1100 degree Fahrenheit steam, then sealed in specially designed fuel debris canisters.
The second major project underway at Trojan was the Reactor Vessel Removal Project.
The licensee has proposed to the NRC an option of removing the reactor pressure vessel as
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one unit as opposed to segmenting the vesselinto pieces for burial. The licensee believes i
that this approach will reduce both cost and personnel exposure. The NRC is currently evaluating the licensee's proposal.
The third major project underway at Trojan is the licensing of the ISFSt. By letter dated March 29,1996, PGE submitted an application to the NRC for the review and approval of a site specific license for an ISFSI at Trojan. This review is currently underway. Trojan plans to start construction of the ISFSI this year with actual movement of fuel at the end of 1997 or early 1998, i
Emergency Preparedness (82701)
1.1 Inspection Scone The emergency preparedness program at Trojan has been significantly reduced from the level of planning and preparedness required for an operational reactor. This inspection reviewed the changes to the program since the last inspection and
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5-evaluated the recent annual exercise, including the self-assessment conducted of the exercise and the identified deficiencies.
1.2 Observations and Findinas
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The 1996 annual exercise for Trojan was conducted on September 18,1996. The exercise included the Trojan on-site emergency response organization and off-site participation by the U. S. Coast Guard, Rainer Rural Fire Protection District, St. John Medical Center, and Professional Communications Services. The Oregon Department of Energy, Oregon Health, and Washington Emergency Management
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Division each had representatives present to observe portions of the exercise.
The scenario selected for this exercise was challenging and innovative. With the Trojan facility in active decommissioning, selection of a realistic exercise scenario was difficult with only a limited number of possible scenarios involving equipment f ailures. The reactor spent fuel assemblies in the spent fuel pool were the primary source term onsite. Calculations in Section 6.3.2 of the Safety Analysis Report concluded that fuel 310 s vars old would not experience boiling in the spent fuel pool for 88 hours0.00102 days <br />0.0244 hours <br />1.455026e-4 weeks <br />3.3484e-5 months <br /> if spent fuel pool cooling was lost. The boil off rate would not exceed 3.7 gallons / day, which would allow 22.5 days to re-establish make-up water before the water level dropped to a level 10 feet above the core. Therefore, a scenario involving failure of the spent fuel pool cooling systems would not create the level of urgency desired for an annual exercise scenario. A scenario resulting in sudden damage to the fuel or catastrophic loss of the water in the pool was needed for a challenging scenario.
Trojan developed an accident scenario that accomplished the desired results. The scenario was challenging for both the health physics organization and the security organization. The Coast Guard assisted Trojan with security support along the Columbia River shoreline. Medical response by the Rainier Rural Fire District ambulance and St. John Medical Center was required for simulated injuries received by a Trojan employee, which included contamination and a broken leg.
Of the 29 exercise objectives identified for the licensee and the hospital, only one objective was not met. This objective involved the ability to prepare news releases and coordinate the news releases with off-site agencies. This objective was not met due to the unavailability of a licensee's public relations person to participate in the exercise. The licensee has since trained additional personnel to function as the Media Representative and will demonstrate this objective in the 1997 exercise.
A number of improvement items were identitied during this exercise including self contained breathing apparatus (SCBA) training and qualifications, operator response to radiation alarms, public address system announcements, and communications with the Coast Guard and Rainier Fire Department. Several very good suggestions
for improvement were made by the participants and incorporated into the
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emergency planning action item tracking list. Review of the resolution of these
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-6-i action items will be incorporated into a future inspection and will be tracked as NRC Followup item 50 344/9608-01.
l The licensee's quality assurance department performed an evaluation of the
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exercise. This evaluation was documented as'AP 731," Annual Audit of Emergency l
Planning Program," dated October 3,1996. The evaluation identified a number of I
good observations concerning the exercise including the coordination between operations and security to locate the insider and security's actions to deactivate the insider's badge to prevent further access back into the protected area.
In addition to the review of the 1996 exercise, revision 4 changes made to the emergency plan, dated October 1996, were reviewed during this inspection. These changes included assignments to the fire brigade, addition of an agreement letter with the contract communications service that provided off-site notifications during an emergency, and editorial changes. All changes were found to be acceptable.
Emergency Plan implementing Procedure No. 2 entitled, " Notifications," was issued as Revision 3 on December 20,1995. This procedure change incorporated the use i
of Professional Communications Services (24-hour service) for making state and
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local notifications during emergencies. The procedure used by Professional Communications Services was reviewed and found to be comprehensive. Required calls were lister' for the state and counties with both a primary and secondary phone number 0vided.
1.3 Conclusion A challenging scenario was developed for the 1996 exercise. Several off-site support organizations participated in responding to the simulated events. All exercise objectives were successfully demonstrated except for coordination and preparation of news releases with offsite organizations.
Revisions to the emergency plan and notification procedures were reviewed during this inspection and found acceptable.
Independent Spent Fuel Storage installation (83890)
2.1 Insoection Scope Trojan had completed all activities associated with the final survey of the area selected for their Independent Spent Fuel Storage Installation (ISFSI). The NRC,
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subsequent to this inspection, determined that the release of this area from the 10 CFR Part 50 license and transfer to the 10 CFR Part 72 license would be acceptable.
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2.2 Observations and Findinas
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The activities associated with the final survey of the proposed ISFSI site, on the northeast corner of the industrial security area, had been reviewed during NRC Inspection 50-344/96-07:72-17/96-01 dated September 10,1996. The NRC, with the assistance of the Oak Ridge institute for Science and Education (ORISE),
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conducted an evaluation of the survey activities, while in progress, and provided preliminary comments to the licensee concerning the adequacy of the final survey program. The final survey was completed by the licensee on October 17,1996.
On October 23,1996, the NRC issued a letter to the licensee concerning the final survey plan for the Trojan ISFSI. This letter informed the licensee that the NRC had
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completed their review of the licensee's Final Survey Plan which had been submitted to the NRC on April 9,1996. A number of comments concerning the Final Survey Plan were issued to Trojan. On October 30,1996, the licensee submitted to the NRC the Final Survey Report. This report incorporated the results of the wvey completed by PGE and resolution of the NRC comments on the Final Survey.>Ian. On November 26,1996, the NRC issued a letter to the licensee
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approving the Final Survey Report, stating that the requirements of 10 CFR 50.82 had been met, and PGE's plan to transfe. the surveyed area from the 10 CFR
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Part 50 license to an ISFSIlicensed under 10 CFR Part 72 was acceptable.
i The licensee was developing an integrated schedule of activities associated with the
ISFSI. This schedule was forwarded to the NRC on December 4,1996. From this
schedule, the NRC will determine the activities that will be incorporated into future
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inspections for the ISFSt.
2.3 Conclusion
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The licensee conducted a final survey of the northeast corner of the industrial security area where the ISFSI will be located. This survey was determined by the NRC to meet the requirements of 10 CFR 50.82. The surveyed area may be released from the 10 CFR Pa.t 50 license for use as an ISFSIlicensed under 10 CFR Part 72.
3 Radwaste (84750/86750)
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3.1 Insoection Scoce
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l Many systems at Trojan have been shutdown and are awaiting decontamination or removal. Systems still required to be maintained operational for the purpose of controlling liquid radwaste and airborne contamination were reviewed as part of this inspection to verify that decommissioning activities had not reduced the effectiveness of these systems to perform their required function.
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3.2 Observation and Findinas T;ds inspection reviewed the operationai status of several key systems which provide control for liquid and airborne radioactive material. The systems reviewed were:
Offgas treatment and ventilation system
- Vent collection system
- Containment ventilation system
- Fuel and auxiliary building ventilation system l
Liquid Waste Treatment System
- Clean radioactive waste treatment system
- Dirty radioactive waste treatment system A walkdown of the systems listed above was completed to verify that the systems were energized and operational; components of these systems, as described in section 5.2 of the Defueled Safety Analysis Report, had not been removed or modified during facility decommissioning; High Efficiency Particulate Air (HEPA)
filters were stillin place; and monitoring and alarm systems were operational.
Charcoal filters had been removed from all ventilation systems. Charcoal filters had been used during plant operations to remove radioiodine from airborne effluents.
These filters were no longer required af ter plant shutdown due to the rodioactive decay of the radioiodine.
The offgas treatment and ventilation system consisted of the vent collectio'1 system, containment ventilation system, and the fuel and auxiliary building ventilation systems. The vent collection system discharged potentially radioactive gaseous effluents from various liquid waste collection tanks and sumps. The system provided a means of maintaining negative pressure on tank vapor spaces during volumetric changes in tank contents. A process radiation monitoring system (PRM-5) automatically stopped the exhaust fans and initiate an alarm in the control room if abnormal radiation levels were detected. A walkdown of the vent collection system verified operation of the exhaust fans, HEPA filter, and PRM-5 radiation monitoring system.
The containment ventilation system provided ventilation for the containment building. This system removed potentially contaminated gases from the containment building. The system consisted of a containment purge supply system and a containment purge exhaust system. The fans, HEPA filters, and radioactive monitoring system (PRM-1) for both the supply and exhaust systems were verified as operational by conducting a walkdown of the systems.
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The fuel and auxiliary building ventilation system provided ventilation for the fuel f
and auxiliary building and maintained a negative atmosphere in spaces subject to airborne radioactive contamination. This systene also exhausted air taken from the spent fuel pool area. The system walkdown verified the operations of the supply fans, exhaust f ans, HEPA filters, auxiliary building vent exhaust monitoring system (PRM-2A, PRM-2C, PRM-2D), and the spent fuel pool discharge monitoring system j
(PRM-3).
The liquid waste treatment and retention systems collect, store, process, monitor, and discharge plant liquid effluents that may contain radioactive material. Two liquid radwaste systems were operational at Trojan. These were the clean i
radioactive waste treatment system and the dirty radioactive waste treatment system. The clean radioactive waste treatment system collected liquids from various equipment drains, leak offs, and flush water. The dirty radioactive waste treatment system collected liquids from the floor drains and equipment drains in the containment building, fuel building, and auxiliary building. The system walkdowns included the clean waste receiver tanks, treated waste tanks, dirty waste drain tank, system pumps, sump pumps, clean waste bag filters, system demineralizers, and the effluent monitoring system (PRM-9). All systems were found operational.
Two liquid radwaste system demineralizers were used to process both clean and dirty radioactive waste. Spent resins were periodically removed and shipped to Hanford for burial as radioactive waste. Spent resins were typically shipped by the licensee every other year. Based on currently projected activities, only one or two more spent resin shipments are expected prior to license termination. Each shipment involved up to three canisters. Each canister was shipped on a separate trailer. The shipping papers for the July 22,1996, shipment of dewatered resins were reviewed. The resins were taken from several systems including systems that j
were in operation prior to plant shutdown. Shipping papers and measured dose j
rates on the shipment were found to be in compliance with 49 CFR requirements, l
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Resins still on site included the spent fuel pool resins and liquid radwaste resins.
The liquid radwaste resins were from both the clean radioactive waste treatment system and the dirty radioactive waste treatment system and included resins used to collect liquids from decommissioning operations, floor drains, and dewatering of systems prior to decontamination.
The condensate demineralizer building was being used for storage of radwaste prior to shipment off site. This building was west of the turbine building within the industrial security area (old protected area). A tour of the facility was conducted.
Radiation areas were appropriately identified, roped off, and posted. Radiation levels outside the posted area were well below 0.5 mR\\hr.
A brief review of recent activities related to the radwaste shipping program was completed, including discussions with the radwaste engineer concerning future shipments. Verification that up-to-date copics of the required shipping regulations
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-10-and licensing documents was completed including review of U. S. Ecology license, 16-19204-1, Rev.11, dated November 1993 (currently under NRC review for renewal), Washington State License WN1019-2, Amendment 20 which expires May 31,1997, and confirmation that current copies of Department of Transportation (DOT) and NRC reguletions were maintained by the radwaste engineer.
3.3 Conclusion
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i A plant walkdown of the offgas treatment and ventilation system and the liquid radwaste treatment and retention system was completed to verify operability and to
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ensure system components had not been taken out of service or dismantled.
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Radwaste being stored in the condensate demineralizer building was verified as being properly posted. Radiation levels were below 0.5 mR/hr outside the roped off areas.
Radiological Environmental Monitoring (80721/84750)
4.1 inspection Scope The radiological environmental monitoring program, required by Technical Specification 5.7.2.5, provides for representative measurements of radioactivity in i
the highest potential exposure pathways and verification of the accuracy of the effluent monitoring program and modeling of environmentai exposure pathways.
The Offsite Dose Calculation Manual (ODCM), procedures, and records were reviewed to verify implementation of the requirements for monitoring, sampling, analysis, and reporting of the radionuclides in the environment. The Radiolot,ical Environmental Monitoring Program and the 1995 Radiological Environmental Monitoring Annual Report were included in this review.
4.2 Observations and Findinas Amendments 12 and 13 to the ODCM were reviewed as part of this inspection.
Amendment 12 administratively moved a requirement to a different section of the ODCM. The requirement remained the same. Amendment 13 encompassed three licensing document change requests (LDCRs94-034,95-031 and 95-050). LDCR 94-034 corrected minor typographical errors in table values and a sample location map. LDCR 95-031 deleted the requirement from the ODCM to perform an annual land use census. LDCR 95-050 was an administrative change renumbering the sections in Section 6 of the ODCM.
i Amendments 12 and 13 to the ODCM were consistent with the change requirements in the Permanently Defueled Technical Specifications (PDTS).
Changes to the ODCM were made in accordance with licensee procedures and complied with PDTS Section 5.7.2.3.2, " Licensee Initiated Changes to the ODCM."
Sufficient information to support the changes was provided. The changes
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-11-maintained the levels of radioactive effluent control required by 10 CFR 20.1302 and 40 CFR 190, and had appropriate approvals. Changes in the ODCM over the previous year were reflected in the Trojan Radiological Environmental Monitoring Report as required by PDTS 5.7.2.3.2 c.
The Trojan Radiological Environmental Monitoring Program requires the licensee to sample ambient radiation levels, well and drinking water, shoreline soil, and air particulates. Procedure TPP 20-4, " Radiological Environmental Monitoring Program," Revision 1, dated September 21,1995, was reviewed. Procedure TPP 20-4 provided a general overview of the radiological monitoring program. Individual radiation protection procedures for Thermoluminescent Dosimetry (TLD) field placement, collection and processing radiological environmental air samples, radiological environmental well water sampling, radiological environmental shoreline soil sampling, and composite water sampling from the Trojan plant environs were examined. The licensee maintained a complete and current set of contractor analytical procedures that were used by the contractor for the analysis of the Trojan site samples. All procedures were determined to be comprehensive, current, and properly approved.
Ambient radiation levels were measured with TLDs at 11 locations. TLDs at 7 locations were examined and found to be deployed according to approved procedures. Both particulate air sampling locations were visited. The air samplers were checked for operation and calibration. One of the two surface water sampling locations was visited and the automatic drawing of a sample was observed. All sampling or monitoring was done according to approved procedures.
The 1995 Radiological Environmental Monitoring Report was reviewed, and the results discussed with the licensee. The only anomalous radiation levels were elevated radiation levels from TLD locations 3 and 15 within the Trojan site boundary on the north and east sides of the industrial area boundary. The average ambient gamma radiation level around the Trojan site was approximately 0.08 mR/ day. Higher than average readings were measured at locations 3 and 15 during the first and fourth quarters of 1995. Location 3 averaged 0.28 mR/ day, and location 15 averaged 0.21 mR/ day for the first quarter of 1995. During the 4th raarter, location 3 averaged 0.23 mR/ day, and location 15 averaged 0.23 mR/ day.
The elevated levels were due to the increased amount of radioactive materials being packaged and shipped off site for burial, including the four steam generators and the pressurizer, which were stored in an outside area near TLDs 3 and 15 during the large component removal program. Measurements of gamma emitting radionuclides in quarterly composites of air particulate filters resulted in no detectable activity.
Gamma emitting radionuclides were not detected in well water samples during 1995. Gross beta activity and tritium and gamma emitters from drinking water samples were consistent with previous measurements, and no radioactivity attributable to the Trojan Plant was detected. None of the shoreline soil samples showed detectable levels of gamma emitter.
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-12-All environmental samples collected by the licensee's personnel at the Trojan site were forwarded to their contract laboratory, Thermo NUtech, which conducted the analysis of the samples. Cognizant PGE personnel were in telephone contact with the contractor on approximately a monthly basis. The licensee received and reviewed both contract laboratory monthly quality control reports as well as the results of the contract laboratories participation in the U.S. Environmental Protection Agency interlaboratory comparison program. The licensee audited the contractor on February 26-27,1996, to evaluate the quality related activities implemented by Thermo NUtech to ensure compliance with the requirements imposed by the licensee's Quality Assurance program. Environmental samples were followed through the receiving, log-in process, and analysis. Three deficiencies in the program were identified. The licensee documented the deficiencies in ar audit report transmitted to the contractor by letter dated March 20,1996. All deficiencies have been corrected by the contractor. The licensee's audit of the contractor was determined to be comprehensive.
Meteorological data was not reported by the licensee for the Trojan site. There were no requirement for the collection of meteorological data at the permanently shutdown and defueled Trojan Plant.
4.3 Conclusion A review was completed of the Offsite Dose Calculation Manual, Radiological Environmental Monitoring Program,1995 Radiological Environmental Monitoring Report, and the environmental sampling and analysis program. All programs were found to comply with the Trojan Technical Specifications.
Health Physics (83100)
5.1 Inspection Scope Activities associated with the ongoing decontamination effort at Trojan were reviewed to verify that health physics practices were being effectively implemented.
Since the potential for spread of contamination would be expected to increase during the decommissioning process, a review of contamination control practices was completed to verify that new areas of the plant were not becoming contaminated. Proper posting of areas was also verified.
5.2 Observations and Findinas Active decontamination of plant areas was continuing. Health physics staffing currently included eight full-time licensee rad:ation protection technicians and seven temporary technicians. Discussions with several of the technicians indicated a strong commitment toward implementing their health physics responsibilities and confidence in management's continued support for the health physics program.
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-13-Actual work in progress was briefly observed. Protective clothing and radiation monitoring equipment were easily accessib'e near the work areas. Personnel observed in the contamination areas were properly dressed in protective clothing.
Health physics contamination controls, including step-off pads, ropes, and postings were correctly established. Radiation monitoring equipment was calibrated, and appropriate beta-gamma survey equipment was being utilized for the work in progress.
Contamination controls continued to be effective in preventing contamination of new areas. Nineteen contamination incidents were documented in 1996 involving
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only minor levels of radioactive material that were easily cleaned up. There was clearly progress being achieved toward the dismantling and decommissioning of the facility. Recently the four reactor coolant pumps had been removed and were being prepared for shipment to Hanford for burial. Plans were to complete the shipments by the end of 1996.
5.3 Conclusion Health physics practices related to the decommissioning work continued to be effective in minimizing radiation problems and preventing contamination spread in the facility.
Inspection Followup (92701/92702)
6.1 Insoection Scope Four open items were reviewed as part of this inspection. Three were NRC violations. One was an inspection Followup Item. In addition, the corrective actions related to the civil penalty issued in June 1996 was reviewed.
6.2 Observations and Findinas a.
(Closed) Violation 50-344/96002-01: 49 CFR Shipping Papers. The Trojan radwaste procedures did not include the requirement to ensure that 95 percent of the radioisotopes, as calculated by the formula provided in 49 CFR 173.433(f),
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were being listed on the shipping papers for radioactive waste shipments. The NRC issued a Notice of Violation on May 22,1996.
Trojan reviewed and revised their radwaste procedures to incorporate this requirement. Trojan also contracted for a review by an outside consultant of Radwaste Procedures RP 300, RP 302, RP 303, and RP 310 to verify that the NRC and DOT regulations were fully incorporated into the licensee's procedures.
Procedure revisions were completed on June 13,1996. The PGE individuals assigned responsibility for radwaste shipments attended training presented by U. S. Ecology on September 24-27,1996. The training was entitled, " Packaging and Transportation of Radwaste Material."
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(Closed) Violation 50-344/96003-01: Failure to follow written plant procedures.
On March 20,1996, a PGE employee at the Trojan site performed an independent safety review of Safety Evaluation 96-019 of ter the employee's qualifications had elapsed on January 13,1996, approximately 2 months earlier and, therefore, did not satisfy the training requirements to conduct an independent safety review as required by Section 4.2.2 of Trojan Plant Procedure (TPP) 18-1. The NRC issued a Notice of Violation on June 18,1996.
In response to the violation, the licensee initiated a number of corrective actions.
The corrective actions included: (1) a review of the Safety Evaluation database to determine if any other safety evaluations had been performed by unqualified personnel, (2) a new monthly report that provides the expiration date for qualified individuals, (3) a revision to Procedure TPP 18-1 that requires each individual preparing or reviewing screenings and/or safety evaluations to document their training expiration date when they sign off on the document, and (4) an updated Trojan Training Department procedure, Plant Support Procedure (PSP) 22-16, effective September 30,1996, that formalizes control of the training database and the list of qualified reviewers.
Through a review of plant procedures, records, and discussions with individuals, the inspector determined that the above mentioned corrective actions had been implemented. Trojan also conducted a new review of Safety Evaluation 96-019 by a qualified reviewer and reapproved the safety evaluation.
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(Closed) Violation 50-344/96007-01: Technical Specification 5.10.3 Violation for Unauthorized Entry Into a Locked High Radiation Area. On July 25,1996, during NRC inspection 50-344/96-05,the licensee informed the inspector on site of a problem concerning entry into a high radiation area by an individual assigned safety watch during work in containment. The individual had climbed over a fence posted as a high radiation area in order to verify that no fires haa started in the posted area due to cutting operations overhead. No health physics technician coverage was obtained during the entry. On September 10,1996, the NRC issued a Notice of Violation concerning the unauthorized entry into a high radiation area.
The licenue's corrective action for this incident included stopping work in containment and meeting with all potentially effected personnel to reinforce compliance with radiation work permit requirements and posting of areas.
Additional training was conducted with contract personnel to reinforce entry requirements for high radiation areas. The individual involved with the incident was terminated. The corrective actions taken by the licensee appeared to be appropriate for the situation.
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(Closed) Followuo item 50-344/96007-02: Split Soil Samples. During inspection 96-07, on August 19-22,1996, the NRC directed personnel from ORISE to collect soil samples of the area being surveyed by PGE for the planned location of the ISFSt. Five soil samples were analyzed by the ORISE staff in their laboratories. The
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samples were analyzed using solid-state gamma spectrometry for fission products, activation products, U-235, and U-238. No indication of radioactive contamination was found.
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Corrective Actions for the June 6,1996. Notice of Violation and Civil Penalty.
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On June 6,1996, the NRC issued a Notice of Violation and a $50,000 civil penalty to the licensee concerning the submittal of inaccurate and incomplete information to the NRC end the apparent violation of 10 CFR 50.9. On July 3,1996, the licensee i
responded to the Notice of Violation and identified corrective actions which would
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be taken to avoid further violations. These actions included a training seminar for all employees concerning the requirements of 10 CFR 50.9 related to completeness and accuracy of information provided to the NRC, revision of the general employee
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training program to highlight the company and individual's responsibilities related to i
10 CFR 50.9, display of information related to 10 CFR 50.9 and 50.5 in areas
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where NRC Form 3 is displayed, and revision to the Trojan Plant Directive concerning correspondence to provide additional guidance with respect to
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responsibilities of the preparer and reviewer of the licensee's correspondence to the l
NRC. The corrective actions committed to by PGE had been completed. All badged
site personnel had completed the training except for a small number of personnel
ident"ied as exempt, which included cafeteria workers, office building maintenance per;onnel, NRC inspectors, and Oregon Department of Energy personnel, i
6.3 Conclusion i
inspection followup was completed for three violations and one inspection followup
item. In addition, completion of the corrective actions related to the June 6,1996 Notice of Violation and Civil Penalty were reviewed.
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Public Document Room On Friday November 8,1996, a visit was made to the local public document room on the 5th floor of the Bradford Price Miller Library, Portland State University, Portland, Oregon. The local public document room was found to be in an acceptable condition with the microfiche reader operational and the microfiche
i catalog up-to-date. The inspector spoke with the librarian responsible for maintaining the local public document room. A hard copy of licensee's application i
for an ISFSI will be provided to the local public document room to enhance access
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by members of the public on current Trojan licensing issues.
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