IR 05000344/1999006

Insp Rept 50-344/99-06 on 990630-0701,21 & 0404-08.No Violations Noted.Major Areas Inspected:Organization,Mgt & Cost Controls & Decommissioning Performance & Status Review, Insp of Transportation Activities & Maint & Surveillance

ML20211Q376
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/09/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20211Q334	List: IR 05000344/1999006 ML20211Q328
References
50-344-99-06, NUDOCS 9909150054
Download: ML20211Q376 (15)

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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

Docket No.: 50-344 License No.: NPF-1 Report No.: 50-344/99-06 Licensee: Portland General Electric Company Facility: Trojan Nuclear Plant Location: 121 S. W. Salmon Street, TB-17 Portland, Oregon Dates: June 30-July 1, July 21, and August 4-8,1999 inspector: J. V. Everett, Senior Hs.'Ith Physics inspector, Region IV Approved By: D. Blair Spitzberg, Ph.D., Chief Fuel Cycle & Decommissioning Branch Division of Nuclear Materials Safety Attachment: SupplementalInformation

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EXECUTIVE SUMMARY Trojan Nuclear Plant NRC Inspection Report 50-344/99-06 The activities completed during this inspection represented a major milestone for the Trojan l site. The 2,040,000 pound reactor vessel package, containing 1.5 million curies of radioactivity l

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was safely delivered to the U. S. Ecology site in Hanford, Washington, for burial. With the removal of the reactor vessel,99 percent of the remaining radioactivity was removed from the site; excluding the spent fuel still in storage in the spent fuel pool. The reactor vessel shipment was conducted safely and without incident, representative of the major amount of time and effort that had been directed toward this project by the licensee and their contractor l Dismantlement work at the site continued to progress. Radiological controls and safety requirements being implemented continued to be effective in controlling work activitie Environmental monitoring of the site confirmed that radiological conditions were consistent with

,revious years. The spent fuel was being stored safety in the spent fuel pool. Water level and ,

i temperature were being maintained for the spent fuel pool within technical specification I Oraanization. Manaaement and Cost Controls and Decommissionina Performance and Status Review l

• Facility dismantlement activities were actively underway at Trojan. Radiological controls, fire loading and safe work practices were observed to be properly implemented during tours of the facility. The training program and employee concem program were -

effectively being implemented to maintain personnel training current and to provide an i opportunity for employees to express concems related to safety issues (Section 1). !

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l Inspection of Transportation Activities l * The Trojan reactor vessel was successfully delivered to Hanford, Washington, for burial l

at the U. S. Ecology site on August 8,1999. The 2,040,000 pound reactor vessel was shipped up the Columbia River on a specially built barge. The 36-hour trip involved passing through four locks and dams during the 270 mile trip. Dose rates on the barl e, in easily accessible areas, were less than 1 mR/hr during the trip (Section 2).

Maintenance and Surveillance

• The licensee had established documentation in a design basis document and a procedure describing their implementation of the maintenance rule requirements in 10 CFR 50.65. The program had been applied to the spent fuel pool structures,

' systems and components (Section 3).

Soent Fuel Pool Safety .

• The licensee had maintained the spent fuel pool water level and temperature within the required technical specification limits. Inspection of the spent fuel pool walls on the

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1-3-lower levels indicated no unusual structural conditions. The modular cooling system i

was operating and providing adequate cooling capability for the spent fuel pool (section 4).

Inspection of Final Sur_vqys f

• The licensee tvM sub.iiitted a license termination plan to the NRC on August 5,199 The license termination p%n is required by 10 CFR 50.82 to be submitted at least 2 years prior to license termination (Section 5).

Radwaste. Effluents and Environmental Proarams

• The licensee submitted the required annual environmental reports to the Nf, summarizing the radiological conditions around the Trojan site. Radiologicatie,s%

measured in the environment around the site for 1998 were consistent with conn a reported the previous year (Section 6).

• A new liquid radwaste system was being installed to allow for dismantlement of the existing system (Section 6).

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-4-Report Details Summary of Facility Statn The Trojan site has been undergoing active decommissioning and dismahtlement over the past several years. Completion of decommissioning and termination of the Part 50 license is scheduled for the end of 2002. A significant portion of the decomrr.issioning effort was completed with the removal of the reactor vessel frorr 1.ae site during this inspection. The Trojan reactor vessel was shipped by barge to the (L S. Ecology burial site at Haniord, j Wasliington. The reactor vessel shipment was the first shipment in the United States of an intact commercial reactor vessel containing the activated intemals. The disposal of the Trojan teactor vessel and internals as a single package was estimated to save approximately 67 person-rem of dose and over 40 radioactive shipments, compared to the other disposal attemative The removal of the reactor vessel from the Trojan site resulted in 99 percent of the remaining radioactive material being removed from the site; excluding the spent fuel which will require special storage until a federal repository is availabl Umiessieir.g activities at the site continued to progress safely. Tours of work areas found workers complying with radiological ard safety requirements. Radwaste storage areas were properly posted. Environmental monitoring programs for 1998 indicated that radiological conditions around the site have remained consistent with conditions reported the previous yea The condition of the spent fuel pool continues to be good. Water clarity was excellent cmd water level and temperature'were being maintained within technical specification Organization, Management and Cost Controls (36801) and Dreommissioning Performance and Status Review (71801) .soection Scope Plant tours were performed to observe work in progress. Work areas were evaluated for fire loading, radiological controls and safe working conditions. Implementation of the training program and employee concem program were reviewe .2 Observation and Findinas Tours of the fuel building, auxiliary building and adjacent areas outside the reactor building were completed. A considerable amount of material had been removed from the auxiliary and fuel buildings. Many areas were ready for dacontamination of concrete walls and floors. Radiological postings were observed fe areas that required radiation work permits for entry or were contaminated. Protective clothing was available near the contaminated area entry points. No fire hazards were obse:ved and housekeeping was adequat .

-5-The ventilation system for the auxiliary building was confirmed to be operating in accordance with Operating Instruction (01).10-1 " Heating, Ventilation and Air Conditioning Reactor, Auxiliary, Fuel and Radwaste Processing Buildings."

Procedure Ol 10-1, Caution 5.1 required one more auxiliary building exhaust fan to be operating than the number of auxiliary building supply fans. Three exhaust fans and l one supply fan were verified as operating with a flow rate of 87,000 cubic feet / minut l Numerous outside areas were being used for storage of radwaste containers. These areas were properly posted as radiation areas. A survey was conducted by the NRC inspector at the edge of the roped boundary of each radwaste storage area. Dose rates I were typically background. The highest reading measured was 1 mR/h All employees and contractors working within the industrial area and the radiologically controlled area were required to complete training. An employee processing schedule designating required training was developed for each employee based on their job category and assigned work tasks. The training program was described in Procedure PSP 22-1, " General Employee Training," Revision 2. General employee training was divided into two levels. Category A provided for access to the industrial aree end buildings. Category B provided for industrial area access plus access to the protected area and radiologically controlled area. Category A training included fitness-for duty, I safety, quality assurance, emergency planning, security, fire prdoction, chemicEl safety, reporting safety concems and worker responsibilities. Category B training included all topics taught in category A training plus required training specified in 10 CFR 19.12

" Instructions to Workers." This included site specific radiation protection, how to reduce l exposures, protective devices, applicable sections of NRC regulations and how to use -

protective clothing. Category B training required the individual to be whole body counte Training was considered satisfactorily completed if the individual scored 80 percent on a test. Failure to successfully complete the test required remedial training and additional testing. For Category B training, the individual was also required to demonstrate the -

ability to dress out in protective clothing and to remove tho protective clothing using proper techniques for leaving a contaminated area of the plant. Retraining was required annually and was successfully demonstrated by taking an exam. A computerized system was used to track the training status of workers. The NRC inspector randomly selected a number of individuals who had access to the protected area and radiologically controlled areas to verify that training was current. Workers selected included both licensee employees and contractors. All persons were found to be .'

currently trained. The name of a headquarters NRC inspector, who was known to be overdue for annual retraining, was provided to the training specialist. The computer ,

identified the individual as not being currently trained. The individual's access to the i protected area and radiologically controlled areas was identified in the system as being denied. The NRC inspector's dosimeter had been removed from the dosimetry rack at ;

the entrance to the radiologically controlled area and the access computer displayed a message that the individual was denied access when his badge number was entered into the syste ...

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The employee concern program being implemented at Trojan was discussed with the licensee's employee concem program coordinator. One employee concern had been received during 1999. The licensee had conducted an investigation of the concern and provi1ed the individual with the results of the evaluation. The NRC inspector randomly )

selected a number of individuals during tours of the facility and discussed working !

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conditions at the site and their willingness to present safety concerns to managemen All licensee employees interviewed felt that management was interested in hearing safety concems and took the concems seriously. In general, the same attitude was expressed by contract personnel. However, one contract person had worked at job sites other than those under an NRC license where he had witnessed situations in which concems were identified to management but were not resolved. This contractor felt !

more comfortable identifying concems to management through co-workers who were licensee employees. Severallicensee employees provided specific examples of information provided to management that had been identified by contractors. The licensee's employees were willing to forward these concems through their chain-of-command for resolution. Overall, there appeared to be a good attitude by the workers toward presenting safety concems to managemen ] Conclusion I

Facility dismantiement activities were actively underway at Trojan. Radiological l controls, fire loading and safe work practices were observed to be properly implemented during tours of the facility. The training program and employee concern program were effectively being implemented to maintain personnel training current and to provide an opportunity for employees to express concems related to safety issue Inspection of Transportation Activities (86740)

Insoection Scooe

- On August 8,1999, the Trojan reactor vessel completed its journey to the U. S. Ecology ;

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burial site at Hanford, Washington. Two NRC inspectors accompanied the shipment up the Columbia River to support the safe transport of the reactor vessel. A third inspector followed the shipment by automobil .2 - Observations and Findina On August 8,1999, the Trojan reactor vessel was successfully delivered to the U. Ecology site on the Hanford Reservation near Richland, Washington, for burial. The shipment of the 1,000 ton Westinghouse reactor vessel took approximately 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to travel the 270 mile joumey up the Columbia River. A specially built 240 foot long barge and two tug boats were used to transport the reactor vessel up the Columbia River and j i through four sets of locks operated by the Army Corp of Engineers. The U. S. Coast !

Guard provided escort for the reactor vessel shipmen ;:

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The application to remove and ship the reactor vessel as an intact package was

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submitted to the NRC on March 31,1997. On July 16,1999, the NRC approved the shipment. Ten major contractors were involved with the reactor vessel removal and shipment project providing support for heavy lifts, land transportation, water transportation, vehicle inspections, package tie-down design, barge design, traffic contros ard cccurity. Fourteen federal, state and local agencies provided regulatory oversight and support during the transportation activitie ;

The project had to overcome several significant technical obstacles for approval. The l reactor vessel and intemals had to receive special approval from the State of Washington for disposal in a shallow land burial site. In order to achieve this, a detailed exposure pathway analysis was completed. The transpcrt package had to receive special NRC and DOT approval since it could not undergo actual drop testing to meet package specification requirements. Finally, the shipment had to be approved by the Coast Guard for transport up the Columbia Rive The licensee had developed a comprehensive safety plan for the reactor vessel shipment. The safety plan described responsibilities, required permits and inspections, packaging requirements, notifications, radiological controls, physical protection and contingency actions. Contingency actions included plans for bad weather, abnormal ,

radiological conditions, fire, tug problems, and sinking of the barge. The licensee had I developed a detailed recovery plan for the unlikely situation of the barge sinking. This planning effort was documented in the environmental report for the reactor vessel package, Appendix E-1 " Contingency Plan for Package Recovery." The technical

- feasibility of recovering the reactor vessel after an accident was confirmed in the .

contingency plan and included the deep water recovery effort that would be required at the deepest location of the trip, which was 191 feet in Lake Umatilla above the John Day Dam. Marine salvage contractors had been identified in the contingency plan capable of providing the necessary. equipment and resources to perform the recovery effor The reactor vessel, filled with low density concrete,' weighed 2,040,000 pounds and consisted of over 1.5 million curies of radioactive material. The predominant gamma i emitting isotope was Co-60. The radioactivity was the result of neutron activation of the !

reactor vessel and intemals during operations. In addition, the intemal surfaces were I contaminated with approximately 155 curies of radioactive material. Low density ,

concrete had been injected into the reactor vessel to fix the intemal loose I contamination. Severalinches of shielding were added to key areas of the reactor i I

vessel to reduce dose rates below regulatory limits for shipment. Extemal surfaces were found to be free of contamination based on smear surveys taken by the license The reactor vessel was painted and shrink wrapped in plasti The reactor vessel was properly labeled as radioactive material, Class C stable. The ,

reactor vessel was packaged as exclusive use, Type B, as exempted by DOT-E-12147 and shipped as a highway route controlled quantity. The NRC inspector observed the radiological surveys conducted of the reactor vessel, including those cenducted by the State of Washington health physics personnel. The highest reading measured by the licenses was 175 mR/hr near the nozzles close to the top side of the vessel. The

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-8- i reading at the vertical plane of the side of the transporter was 3 mR/hr at 2 meters. The radiological limits for shipments in 49 CFR 173.441 are 200 mR/hr contact and 10 mR/hr at 2 meters from the vertical plane of the transporte On August 7,1999, during the transport up the Columbia River, a radiological survey was performed by the NRC inspector on the barge and the tug boats to confirm the radiological conditions. Radiation levels inside the cab of the tug boat were measured at background levels. On the barge, most accessible areas measured background level The highest measured reading was 0.7 mR/hr near the edge of the transporter. Pencil !

dosimetry, with a rar.ge of 0-200 mR, was provided by the licensee to all persons on the j

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tug boats. The pencil dosimeter wom by the NRC inspector was checked periodically and at the end of the trip. No measurable radiation was recorded on the dosimete .3 Conclusion The Trojan reactor vessel was successfully delivered to Hanford, Washington, for burial at the U. S. Ecology site on August 8,1999. The 2,040,000 pound reactor vessel was i shipped up the Columbia River on a specially built barge. The 36-hour trip involved I passing through four locks and dams during the 270 mile trip. Dose rates on the barge, in easily accessible areas, were less than 1 mR/hr during the tri .

l 3~ Maintenance & Surveillance (62801) j Insoection Scooe The licensee's implementation of the mainter,ance rule in 10 CFR 50.65 was reviewed to determine if the licensee had established a program for those structures, systems ;

and components that were covered by the maintenance rul .2 Observation and Findinos The licensee had established a program to implement 10 CFR 50.65 requirements in Design Basis Document #36, Appendix A entitled "10 CFR 50.65 Maintenance Rule,"

and Procedure TPP 14-23 " Maintenance Rule implementation," Revision O. The licensee had incorporated into their program the recommendations of the industry guidance document NUMARC 93-01 " Industry Guidelines for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants." The maintenance rule program was applied to the spent fuel pool. ' A maintenance rule administrator was assigned by the licensee to ensure implementation of the maintenance rule at the site. A three member panel consisting of the engineering manager, operations manager and maintenance manager reviewed and approved any changes to structures, systems and components (SSC) that were covered by the maintenance rule implementatio Procedure TPP 14-23 established two categories related to performance of the SSC The first category identified SSCs with unacceptable performance or condition. When placed in this category, the SSC was subject to goal setting and monitoring to return the L

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SSC to acceptable performance. Trojan had no SSCs in this category. The second j category included SSCs that had shown acceptable performance or condition and were i included in the preventive maintenance program. Procedure TPP 14-23, Attachment 1, provided a list of SSCs that were incorporated into the licensee's maintenance rule program. All items on the list related to the spent fuel pool and support system Examples of listed items included the spent fuel racks, spent fuel pool structure, modular spent fuel pool cooling system, portable pumps for providing spent fuel pool makeup from the Columbia River, and boric acid batching tan On a monthly basis, printouts of the corrective maintenance work orders for the SSCs were forwarded to the maintenance rule administrator for review to determine if any l SSC should be moved into the unacceptable performance category. Annually, the I maintenance rule administrator was required to perform a review of corrective I maintenance work orders and corrective action requests initiated for SSCs. This evaluation was to include industry wide operating experience. On a 6-month basis, a walkdown was required of the control room, fuel building and auxiliary building by an individual from engineering to observe the general condition of the building .3 Conclusion The licensee had established documentation in a design basis document and a procedure describing their implementation of the maintenance rule requirements in 10 CFR 50.65. The program had been applied to the spent fuel pool structures, systems and component Spent Fuel Pool Safety (60801) Inspection Scope Compliance with technical specifications related to spent fuel pool water temperature and water level were reviewed. The structural condition of the spent fuel pool wall and the adequacy of the modular cooling system to maintain cooling of the spent fuel pool were evaluate .2 Obsentation and Findinas Technical Specification 3.1.1 required the spent fuel pool water level to be maintained at least 23 feet over the top of the irradiated fuel assemblies. Data for the period of January through July 20,1999, were reviewed. The water level was maintained above 23.5 feet throughout this perio Technical Specification 3.1.3 required the spent fuel pool water temperature to be maintained at or below 140*F. For the period January through July 20,1999, the water temperature had been maintained between 100*F and 130*F.

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-10-The condition of the spent fuel pool was observed. Water clarity was very good. A visual inspection of the spent fuel pool walls on the lower levels indicated no unusual structural conditions. Numerous pipes that had been part of the old cooling system were observed to be cut and capped. No leaks were observed. The modular cooling system was operating and was providing adequate cooling capability for the spent fuel poo .3 Conclusion The licensee had maintained the spent fuel pool water level and temperature within the required technical specification limits. Inspection of the spent fuel pool walls on the lower levels indicated no unusual structural conditions. The modular cooling system was operating and providing adequate cooling capability for the spent fuel poo Inspection of Final Survey (83801)

l Inspection Scooe The licensee had submitted a license termination plan to the NRC for review. The license termination plan is required by 10 CFR 50.82(a)(9)(i) to be submitted to the NRC at least 2 years prior to license terminatio .2 Observation and Findinas On March 10,1999, the licensee submitted a license termination plan to the NRC for review. On April 29,1999, the NRC informed the licensee by letter that the license termination plan that had been submitted did not include sufficient infonnation to allow the NRC staff to perform a detailed review. Subsequent telephone conversations with the licensee resulted in a resubmittal of the license termination plan on August 5,199 The resubmitted license termination plan has been accepted for NRC revie The Trojan licensee termination plan used the methodology established in the )'

Multi-Agency Radiation Survey and Site Investigation Manual (MARSSIM). MARSSIM provided detailed guidance for planning, implementing, and evaluating environmental and facility radiological surveys conducted to demonstrate compliance with the NRC

- radiological release criteria established in 10 CFR Subpart E " Radiological Criteria for License Termination." MARSSIM was developed as a multi-agency effort involving the NRC, Environmental Protection Agency, Department of Defense, and Department of Energ The licensee had established a work area in the general administration building for analyzing data using a computerized system. Data was being collected for several areas around the plant that may be affected by the shine that could occur from the independent Spent Fuel Storage Installation (ISFSI) that will become operational in the near futur i

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The licensee had submitted a license termination plan to the NRC on August 5,199 l The license termination plan is required by 10 CFP. 50.82 to be submitted at least 2 years prior to license terminatio Radwaste, Effluents and Environmental Programs (84750)

i Insoection Scope The licensee's annual environmental reports were reviewed. These reports provided information on radiological conditions around the site and radioactive. shipments for offsite burial. The status of the dismantlement of the radwaste system was reviewe ] Observation and Findinas k I

The annual radiological environmental report for 1998 was submitted to the NRC on l'

April 21,1999. The annual report is required to be sulemitted to the NRC by May 15 of each year in accordance with Technical Specification 5.8.12. The annual report included the required information specified in the technical specification including interpretations of the data and trends. The environmental samples collected at Trojan )

were analyzed by an outside analytical laboratory. Fifteen sampling locations were identified around the site. Samples taken included air, well water, drinking water and soil. Thermoluminescent dosimeters (TLD) were also placed at 12 of the locations. All but one sample collected were found to have similar radiological levels as have been measured over the past several years, representing normal background levels. _The one elevated sample was the TLD at Location #15 on the industrial area fence. Elevated levels could be attributed to the nearby refueling water storage tank and radioactive material stored nearby. Average ambient TLD readings for background radiation levels were 0.08 mR/ day. At location #15, the 1998 reading was 0.14 mR/ day. The 1997 reading for this same location had been 0.16 mR/ da The operational ecological monitoring program annual report for 1998 was submitted to the NRC on April 8,1999. Submittal of the report is required by the Trojan license, Appendix B " Environmental Protection Plan," Section 5.4.1. The report included the required information specified in the environmental protection plan. No issues related to radiological safety were identified. One environmental protection plan non-compliance was reported. involving the digging of test pits for sampling without conducting an

- environmental evaluation. Corrective actions were implemented to prevent recurrenc The radioactive effluent release report for 1998 was submitted to the NRC on April 29,1999. The report is required by Technical Specification 5.8.1.3 and provided information related to effluent and waste disposal and offsite radiation doses. There were 24 liquid discharges from the Trojan site during 1998. A total of 3 x 10' liters of diluted water was released from the site containing 1.3 x 10' liters of waste water. Total actmty released, excluding tritium, was approximately 0.17 curies with Co-60, Cs-137 o< l

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-12-and Sr-90 being the primary isotopes released. For tritium, a total of approximately 8 curies was released . The limits for liquid releases of radioactive material are specified in 10 CFR 20, Appendix B, Table 2, Column 2, and in the licensee's offsite dose calculation manual, Section 3.2. Section 3.2.1.2 of the offsite dose calculation manuallimited doses to a member of the public from offsite releases to less than 1.5 mrem whole body and 2.5 mrem to any organ. If the quarterly release of liquid effluents exceeded 2.5 curies, excluding tritium and dissolved gases, then verification that the dose rates would not exceed the 1.5 mrem whole body and 2.5 mrem to any organ were required. The licensee's releases were well below the 2.5 curie limit.- In addition, Section 3.2.1.3 of the offsite dose calculation manual required that the liquid radwaste treatment system be maintained and used to reduce liquid wastes discharged from the site to below 1.25 curies, excluding tritium and dissolved gases. The licensee was also below this limit. For tritium, the release limit in 10 CFR 20, Appendix B, Table 2, Column 2 was 3 x 10 '8 microcuries/ml. Releases for the first quarter of 1998 were 4.26 x 10 4microcuries/ml. The first quarter had the highest concentrations for the year. These releases represented 5 percent of the 10 CFR 20 limi There were 148 shipments of radwaste from Trojan in 1998. All shipments were sent to Hanford, Washington, for burial. A total of approximately 1940 cubic meters of solid waste was shipped offsite. This represented 493 curies of activity. This compared to 355 curies shipped for burial in 1996 and 24 curies in 1997, i

For 1999,43 shipments of radwaste had been made as of the end of July. All were shipped to Hanford, Washingto .

A new liquid radwasta system was being installed to allow for dismantlement of the existing system. In the existing system, liquids were directed through floor drains to the dirty waste tank, we.re filtered, and subsequently stored in the two treated waste monitoring tanks. These tanks held 15,000 gallons and were 16 percent and 60 percent filled at the time of this inspection. The new system consisted of two plastic poly tanks located on the 45' elevation of the fuel building. Each tank held 1,500 gallons. Liquids would be collected in the first tank, then filtered and sent to the second tank. The liquids in the second tank would be recirculated, sampled and discharge .3 Conclusion The licensee submitted the required annual environmental reports to the NRC summarizing the radiological conditions around the Trojan site. Radiological levels measured in the environment around the site for 1998 were consistent with conditions

. reported the previous yea A new liquid radwaste system was being installed to allow for dismantlement of the existing syste .

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-13-7 Onsite Follow-up of Written Reports of Nonroutine Events (92700)

On July 12,1999, the licensee provided written notification to the NRC that an earthquake had occurred approximately 81 miles north-northwest of the Trojan site on July 2,1999. The University of Washington in Seattle measured the earthquake at on the Coda Magor.ude scale, which is essentially the same as the Richter scale. No after shocks were reported. Seismic monitors in the Seattle-Tacoma area measured the highest ground motion as 0.01g. The earthquake was felt at Trojan as a very mild movement. Seismic monitors at Trojan did not measure any ground motio Inspections conducted by the licensee found no effects on facilities from the earthquak Exit Meeting The inspector presented the inspection results to members of licensee management at an interim exit at the conclusion of the onsite inspection on July 21,1999. A telephonic exit was conducted on September 2,1999, with the final results of the inspection involving the transportation activities associated with the delivery of the reactor vessel to Hanford, Washington. The licensee acw:wledged the findings presented. The licensee did not identify as proprietary any information provided to, or reviewed by, the inspecto .

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ATTACHMENT PARTIAL LIST OF PERSONS CONTACTED Licensee A. Bowman, Radiation Protection Supervisor C. Brown, Training Specialist B. Clark, Engineering Supervisor

. L. Dusek, Nuclear Regulatory. Affairs Manager T. Meek, Radiation Protection Manager J. Mehelich, Engineering Manager -

M. Murdock, Radwaste Specialist P. Peterson, Decommissioning B. Wallace, Project Engineer, Decommissioning State Aaencies

' A. Bless, Resident inspector, Oregon Office of Energy E. Fordham, Health Physicist, Washington Department of Health R. Paris, Manager, Radiation Protection Services, Oregon Department of Human Resources E. Wright, Oregon Department of Human Resources Foss Maritime T. Alfred, Deckhand M. Davis, Deckhand D. Howard, Tugboat Captain J. McCoy, Tugboat Captain P. Mosher, Tugboat Captain D. Mulligan, Tugboat Captain L. Slecht, Deckhand D. Toolkes, Deckhand Others S. Gowen, U. S. Ecology, In INSPECTION PROCEDURES USED 36801 Organization, Management and Cost Controls 60801 Spent Fuel Pool Safety 62801 Maintenance and Surveillance 71801 Decommissioning Performance and Status Review 83801- Ir.spection of Final Surveys 84750; Radwaste, Effluents and Environmental Programs 86740 Inspection of Transportation Activities 92700 Onsite Follow-up of Written Reports of Nonroutine Events

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2-ITEMS OPENED, CLOSED, AND DISCUSSED Opened None  ;

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LIST OF ACRONYMS CFR Code of Federal Regulations {

PGE Portland General Electric Company 1 Multi-Agency Radiation Survey and Site Investigation Manual I MARSSIM .

SAR Safety Analysis Report SSC Structures, Systems and Components T. Technical Specification ,

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