IR 07200001/1986001
| ML20203E257 | |
| Person / Time | |
|---|---|
| Site: | 07200001, 07001308 |
| Issue date: | 07/18/1986 |
| From: | France G, Greger L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20203E234 | List: |
| References | |
| 72-0001-86-01, 72-1-86-1, NUDOCS 8607240118 | |
| Download: ML20203E257 (12) | |
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U.S. NUCLEAR REGULATORY COMISSION
REGION III
Report No. 72-001/86001(DRSS)
Docket No.72-001 License No. SNM-2500 Licensee: General Electric Company 175 Curtner Avenue San Jose, CA 95125 Facility Name: Morris Operation Inspection At: Morris Operation, Morris, Illinois
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Inspection Conducted: November 19, 1985 through July 15, 1986 b 15 Principal Inspector: G. M. France, III . $lNb ate
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Approved By: L. R. Greger, Chief 7-/8'86 Facilities Radiation Protection Section Date Inspection Summary Inspection on November 19, 1985 throuch July 15, 1986 (Report No. 72-001/86001(DRSS))
Areas Inspected: Routine, unannouncec inspection of fuel shipping activities; fuel storage activities; and radiation protection and radwaste programs, including organization, ALARA, internal surveys, notifications, and reports; criticality safety; solid radwaste and transportation activities; environmental protection program; maintenance surveillance activities; and emergency preparednes Results: For the areas inspected, no violations or deviations were identifie PDR ADOCK 07001308
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DETAILS 1. Persons Contacted R. L. Carlson, Specialist, Nuclear Materials Safeguards
- G. Damm, Senior Engineer, Licensing and Radiological Safety T. E. Ingels, Manager, Quality Assurance and Safeguards J. E. McGrath, Supervisor, Plant Safety S. P. Schmid, Specialist, Field Services T. E. Tehan, Senior Engineer, Field Services
- Denotes those present at the exit meeting on June 12, 1986.
The inspector also contacted other licensee personnel and other personnel associated with the spent fuel shipments, including: operators, safety technicians, instrument maintenance specialists, State of Illinois Office of Waste Transportation inspectors, officials of Burlington Northern Railroad Company, and Burns Security personne . General The inspection of onsite activities, which began at 2:30 p.m. on June 2, 1986, was conducted to examine routine operations of spent fuel storage activitie The inspectors performed independent surveys on seven out of the nine shipments of spent fuel received from the Nebraska Public Power District Cooper Station since November 1985. Also, a representative of USNRC Safeguards and Materials Programs Branch / Division of Inspection Programs observed receipt of a spent fuel shipment and met with the Plant Manager and selected members of his staf . Licensee Actions on Previous Inspection Findings The licensee is currently updating emergency preparedness procedures to effect changes where necessary. An inspector concern about emergency brigade operations was previously discussed in Inspection Report No. 72-001/85002. This item remains open pending licensee action (0 pen Item 72-001/86001-01).
4. Management Organization and Controls The inspector reviewed the licensee's management organization and controls for radiation protection and operations, including changes in the organizational structure, procedure revising and updating, and utilization of audit systems, Organization Radiation protection staff stability continues to be excellen The Plant Safety Supervisor and four Safety Technicians provide coverage in industrial safety, industrial hygiene, fire prevention,
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first aid, and radiation protection programs. On a routine basis, technicians provide coverage during the day and afternoon or evening shifts, and upon request all shifts are covered by radiation protection personnel, b. Procedure Revising and Updating The inspector reviewed the licensee's quality assurance program and confirmed that radiation protection procedures and operating procedures pertaining to onsite activities are periodically reviewed by the Plant Manager, the Licensing and Radiological Safety Senior Engineer and other members of the Plant Safety Comittee. Recent reviews and approvals of Standard Operating Procedures conducted by the Plant Safety Comittee include:
- SOP-16-110, Revision 6, Sealed Source Inventory and Leak Check
- SOP-16-100, Revision 3, Effluent Water Analysis Compliance Test
- SOP-16-96, Revision 5, Criticality Detector Operability Compliance Test
- S0P-16-97, Revision 3, Criticality Alarms Operability Compliance Test FCN-977, Revision 0, LAW Vault Evaporator Structure
- The inspector noted that these procedures correctly reflect requirements identified by license conditions and NRC regulation c. Reviews and Audits An inhouse audit revealed that the licensee is exempt from the State of Illinois Chemical Safety Act (ICSA) because the licensee does not discharge hazardous waste to a public owned treatment work A review of other audits identified the following recomendations:
Corporate Audit - recomended a review of the emergency procedure manua This was previously recomended in Inspection Report No. 72-001/8500 Insurance Audit - recomended automatic sprinklers for warehouse "A" (MAERP Reinsurance to protect against a fire in the combustible Association) materials. The inspector toured this facility and determined that the only radioactive material present was low level contamination fixed on equipment previously used in operation Inhouse Audit - USEPA/ State of Illinois Resource Conservation and Recovery Act (RCRA). Apparently, the licensee does not engage in a production activity that would create waste volumes or quantities of oil or hazardous waste or metal polishing waste reportable under the RCRA. The inspector also determined that the licensee does not generate radioactive contaminated waste oi . Safety Committee The inspector examined minutes of the monthly meetings held by the Plant Safety Committee, interviewed several members of the committee, and reviewed the committee file on incidents pertaining to safet An operation alert is issued by the Operations Supervisor to describe any incident that occurrs during production that may have safety significance. These incidents are reviewed and evaluated by the Plant Safety Committee for recommended action to prevent recurrence. Those reviewed recently included:
- Sewage Waste Maintenance - An employee was struck (head and
. back) by a handle while placing a float in position in the sewage waste pond. Employee was treated with first aid, hospitalized, and release '
- IF-302 Head Gasket - Misalignment of the head seal caused the seal to fall off the cask. Apparently, the operator changed functions during critical phase of an individual tas The inspector noted that none of the incidents reviewed were associated with any radiological hazar No violations or deviations were identifie . Radiation Protection
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The inspector reviewed the licensee's internal and external exposure control programs including the required records, reports, and notification, and the licensee's program for maintaining occupational exposure ALAR Internal Exposure Control Whole body count results for licensee personnel were reviewe Results for each individual showed no significant detectable activit Although personnel were instructed to shower before submitting to the whole body count, an occasional recount was required for individuals showing external contaminatio Employee urinalysis results showed no significant detectable activity, External Exposure Vendor supplied film badge reports from November 1985 to date were reviewed. The annual exposure report for 1985 operations disclosed that 142 persons were badged during the year. An exposure table follows:
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- Four (4) persons received annual doses of 2 to 2.3 rem * Nine (9) persons received annual doses of 1 to 2 rem * Thirteen (13) persons received annual doses of 0.5 to 1 re * Thirty-eight (38) persons received annual doses of 0.01 to 0.5 re A total of 37 person-rem was reported for 1985. This was the decond highest person-rem exposure during plant operations. Higher exposure levels occurred from workers decontaminating the spent fuel casks and the basin filter system and sludge tank, and from replacing the low activity waste (LAW) vault evaporator. Because of manpower availability (M0 has 48 employees) staff members and operations personnel share exposure Although the total exposure for the operatin higher than most previous operating years, the licensee'g year wass practice o using various workers, time, distance, and shielding have helped reduce the exposure to any one worke c. Airborne Releases The inspector selectively reviewed licensee records of air sample analyses. Samples of airborne radioactive concentrations taken in the fuel basin area were less than 10 CFR 20 limits, d. ALARA Activities The inspector examined licensee records that documented licensee practices in reducing occupational exposure * The inspector observed the licensee removing bolts from an IF-300 cask with air driven torque-socket wrenches (reported in Inspection Report No. 72-001/85002). This application expends about a one-half hour effort by two workers that would usually require two hours with hand held wrenche * Chemical cleaning of the basin filter tubes reduced personnel exposure by 2.4 re * Chemical cleaning of the evaporator heat exchanger removed about 0.2 curies of radioactivit * Cask decontamination studies determined the radiation levels of fuel spacers after using selected methods of chemical cleanin Initial dose rates of 400-600 mR/hr were reduced to 80-100 mR/hr with chemical rinsing and 20-30 mR/hr after hand wipin * Decontamination efforts around the cask decon pad included:
fill in of cracks in the concrete after removing fixed contamination and removal of contaminated strippable pain . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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The inspector determined that the licensee tracks doses by individual tasks, work groups and individuals. A regulated work permit (RWP)
was used to show the minimum requirements for radiation safety. In addition, a beta /gama air monitor and an area radiation monitor were located at the decon pad. The extent of contaminated areas was confined to major equipment and the cask decon pad. Liquid waste
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generated during decontamination operations was piped to the low
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activity waste (LAW) vault for subseouent evaporation and containment.
1 Personnel exposure levels were kept to a minimum by judiciously assigning tasks on a time share basis to both management and
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production personnel.
I Surveys and Contamination Controls
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The inspector reviewed the licensee's program for radiological
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surveys to verify compliance with the regulations and with license requirements.
4 The licensee maintains G-M pancake probe friskers at three points of egress from the operations area. Each egress station is also equipped with hand and foot monitors which appear to be relatively inefficient for levels of gamma radioactivity below 0.5 uC The j licensee uses a 8 uCi Cs-137 gamma source to check instrument i response. The licensee has conducted an inhouse evaluation of the The hand inspector anddetermined foot monitors that and has pancake the G-M decided monitors to order set rep about (lacement C/M above background) appear adequate for workers to perform personal monitoring. Posted procedures provide the operations personnel detailed instructions on how to survey with the G-M pancake probe prior to exiting the area. However, for most i personnel who pass through the hand and foot monitors, contamination l 1evels would have to exceed 0.5 uCi in order to be consistently detected. In response to inspector concerns, the licensee agreed to
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the following:
- Determine the minimum level of detection for each instrument used for personnel monitoring at the point of egress.
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- Continue the ongoing program to obtain more efficient portal /
) hand and foot monitors.
! * Increase surveillance on persons exiting the three locations by using safety technicians equipped with G-M pancake detectors at
- the exit * Maintain records of safety technician exit surveys for l
Region III review during a future inspection.
Appropriate documentation of the licensee's contamination control
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program will be reviewed during a future inspection. (0 pen Item No, 72-001/86001-01).
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. Respiratory Protection The inspector reviewed the licensee's respiratory program and determined that the program was being administered in compliance i with the following regulations and standards:
- Title 10 CFR, Part 20.103(c)
- OSHA 1910.134 The licensee incorporates OSHA /NRC requirements in providing personnel respiratory trainin This program includes a qualitative test performed in an isoamyl acetate atmosphere with the worker wearing MSA Welsh full face mask No violations or deviations were identified.
4 Operations Review The inspector toured the facility and reviewed the status of operations.
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- Fuel Storage Activities The inspector reviewed the licensee's fuel storage activities including current and proposed fuel receipts and shipments. From November 19, 1985 through July 15, 1986, Region III USNRC inspectors
- performed onsite inspections on 7 of 9 spent fuel shipments from Nebraska Public Power District's Cooper Station. Spent fuel
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, shipments from Northern State Power's Monticello Nuclear Generating i Station are scheduled to resume during the latter part of 198 The major activity completed since the last inspection (72-001/85002) was the fabrication and installation of the i replacement evaporator, Housekeeping The inspector determined that housekeeping efforts were adequate i'
and that the potential for accumulating fissile materials in unauthorized locations or exposing the public to unnecessary levels of radiation was minimized because of the implementation of planned, approved standard operating procedures (50P).
! Safety Analysis Report Update and Inaccordancewiththerequirementof10CFR72.50(b)(1),(2)Idated (3) the licensee shall submit an annual update to the Consol Safety Analysis Report (CSAR) to include:
- new or revised information relating to applicable site evaluation factors (72.50(b)(1));
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- description and inalysis of changes in the structures, systems, and components of the ISFSI, with emphasis upon aerformance requirements, the bases upon which requirements lave been established and evaluations showing that safety functions will be accomplished (72.50(b)(2));
e an analysis of the significance of any changes to codes, standards or regulations which the licensee has committed to meeting the design or operation of the ISFSI (72.50(b)(3)).
The licensee informed DFMS and Region III that no new information was obtained, activities conducted, or changes to the structure, systems and components of the Morris Operation made during the report period that require revision of the CSA No violations or deviations were identifie . Criticality Safety The inspector examined the licensee's nuclear safety records and confirmed that the licensee maintains a detailed description of the physical, thermal, and radiological characteristics of spent fuel received from the Nebraska Cooper Station (NCS). The inspector noted that the licensee received a fuel bundle acceptability list from the shipper (NCS), performed specific criticality safety analysis to extend thewater/fuelratioforthetypebundlearray,andsubmittedtheanalysis to NMSS for review and approva The Commission approved the licensee s safety analysis and issued the following statement as part of an amendment to the Morris Operation's Material License No. SNM-2500:
" Based on the staff's review of the applicant's calculated results and conservative W/F linear extrapolation, plot is found acceptabl theWp/F Correction Factorroposed extensio Use of the Graph with the proposed extended range is to allow General Electric an independent check of rod lattice k-infinity for fuel designs not presently covered, such as the GE BWR 8 x 8 R fuel bundl However, this change to the graph does not change the actual k-infinity limits set for fuel acceptability at the General Electric Morris Operation in Appendix A of SNM-2500. Thus, there is no change in the criticality safety margins associated with this amendment for the General Electric Morris Operation."
The licensee performed an off-shift criticality evacuation drill and determined that criticality alarms were heard by all personnel and that evacuation routes were properly use However, during an annual test of the criticality alarm system located in the basin area, the alarm could not be heard clearly. Repairs were made and the system was restored to an acceptable performance leve No violations or deviations were identifie . _ _
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. Maintenance Surveillance The inspector examined the licensee's maintenance operations to determine if records pertinent *to safety are maintained en Morris Operations system Items such as radioactive sources and instrument calibrations requiring scheduled service at some predetermined frequency are being placed on a compute In response to inspector concerns about systems mintained for nuclear criticality safety alarms, the licensee noted that a standby criticality monitor was availabl In compliance with the Appendix A Technical Specifications of License No. SNM-2500, the licensee perforn.ed required measurements of stack effluent air and basin water quality at the specified frequencie No violations or deviations were identifie . Training The inspector reviewed the licensee's provisions for training and periodic retraining of employees related to employee work assignments with radioactive material The inspector verified that production workers received annual training for "A" certification and that administrative workers participated in training sessions required for "B" certification. The inspector noted that the written exam for "A" certification was significantly more difficult than the examination required for "B" certification. In other training activities, two operations technicians were assigned full time for two weeks to the supercompactor project to gain familiarity with the unit. The licensee also noted that special.ized training for operations technicians was accomplished in the following areas:
- neutralization techniques in maintaining the waste steam from the demineralizer;
- instructions for all shifts in operating the LAW vault evaporator / heat exchanger; and
- annual respiratory training requirement No violations or deviations were identifie . Environmental Monitoring The inspector reviewed the licensee's environmental monitoring program, the annual environment report, and specific requirements of Materials License No. SNM-2500. The average stack release concentration of
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Cobalt-60 during 1985 was about 64 percent less than the previous year, and the Cesium-137 concentration was about 59 percent less than the previous yea Appendix B, Technical Specifications for Environmental Protection License No. SNM-2500, Table 8-1, Morris Operation Radiological Monitoring Program, requires the licensee to sample milk from three collection sites (Davidson, Dorin, and Mather farms) for iodine-131 content. However, according to the annual environmental report, milk samples were collected from the Clow, Birros, and Trotter farms instead. The discrepancy in sampling locations was discussed during the exit meeting and will be reviewed further during a future inspection. (Unresolved Item No. 72-001/86001-02).
No violations or deviations were identifie . Transportation The inspectors reviewed the transportation activities to determine whether the licensee is maintaining an adequate program to assure radiological safety in the receipt, packaging, and delivery of licensed e radioactive material Three inspectors reviewed the licensee's program for receipt and shipment of radioactive materials. The review included inspection of seven of nine incoming rail shipments of spent reactor fuel from Nebraska Public Power District's Cooper Station during the months of November 1985 through the 15th of July 1986. The inspectors noted that minor contamination levels exceeding the NRC contamination reporting level of 22,000 dpm/100cm2 were discovered on the external surface of one spent fuel cask and two empty casks. In each instance the application of smear efficiency techniques demonstrated that the DOT contamination limit was not exceeded. The 9th rail shipment from Cooper Station was temporarily delayed, because the regulatory limit of 1000 mrem on the external surface of the cask initially was nct me The regulatory limit for external radiation at two meters from the cask was also exceeded. The Cooper Station licensee repackaged the fuel bundles and with regulatory concurrence added temporary shielding inside the cask cage area (near the cask closure head)
to reduce the radiation levels externall The inspector performed independent measurements on the shipment upon its arrival at G. E. Morris and determined that external radiation levels were within regulatory limit The licensee shipped 54 packages of compacted contaminated waste (plastic, paper and wood) to the Barnwell, S.C., disposal site. The amount of radioactivity in the shipment totaled nearly 800 mci, with Cobalt-60 (400 mci) being the major isotope. The inspectors concluded that the licensee demonstrated a performance level that assured radiological safety in the handling and transport of licensed radioactive materia No violations or deviations were identifie I
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12. Emergency Preparedness The inspector verified that emergency equipment including fire extinguishers, respiratory protection devices and radiation survey instruments are checked on a periodic basi Currently, the licensee is maintaining licensed activities with a staff of 48 person There have been no personnel changes that affect the staffing of the emergency fire brigad MAERP Reinsurance Association conducted an onsite inspection and recommended that the licensee add automatic sprinklers in warehouse "A" to reduce the potential of a serious fire. The licensee continues to use the Operation Shift Supervisor as the emergency coordinator. Emergency procedures are discussed in monthly safety meetings and respiratory protection training is extended to the Plant Manager, Operations Staff, and all personnel involved in fuel storage and handling operation During a tour of the facility the inspector noted that portable fire extirguishers were accessible and ready for immediate use in emergency situations. Passageways in storage areas had clear access to points of egress and housekeeping appeared adequate for emergency evacuatio The licensee noted that oft-site health services have been upgrade The Morris, Illinois, hospital has instituted a trauma section which can provide service for M0 personnel during emergencies that don't involve radioactivit During a previous inspection (72-001/85002) the inspector recommended an l early review of the emergency preparedness procedures in order to effect l changes where neede This project is still ongoing and will be reviewed during the next inspection (0 pen Item No. 72-001/86001-03).
No violations or deviations were identifie . Radioactive Waste Management The inspectors reviewed the licensee's records to determine whether the licensee is complying with regulations and license requirements related to the release and disposal of liquid and solid radioactive wast Solid Wastes Records of waste shipments disclosed that 54 drums of waste containing 800 mci were shipped. Shipping papers, survey records, and certifications were reviewed; no problems were identified. The licensee continues to demonstrate waste volume reduction techniques using the supercompacto A demonstrated rate of compaction resulted in the reduction of 40 drums of solid waste (capacity equal to 7.5 cu.ft. per drum) into 8 drums with a capacity of 11.6 cu.f per drum. This represented more than a 3 to 1 reduction rati . - Liquid Waste As described in the licensee's SAR, liquid radioactive waste is collected and accumulated in the low activity waste (LAW) vaul Materials such as spent resins are flushed from the basin water filter system. The licensee recently replaced the system evaporator which is used to concentrate (control) the liquid level of the vault. Demisting and venting is accomplished through the building ventilation system. Evaporation is another technique the licensee uses in waste volume reduction. No liquid effluents are discharged from the site. Sanitary wastes from M0 are routed to treatment facilities and settling lagoon No violations or deviations were identifie . Exit Meeting The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the onsite inspection on June 12, 1986. The inspector summarized the scope and findings of the inspectio In response to inspector concerns the licensee agreed to continue reviewing the emergency preparedness procedures and publish appropriate change The licensee stated that evaluation of monitoring instrumentation used exits will continue. Unannounced surveillance of personnel exiting the premises will also increase. Results will be recorded and held for future Region III inspection The licensee agreed to resolve the discrepancy in milk sampling location During the course of the inspection and the exit meeting, the licensee did not identify any documents or inspector statements and references to specific process as proprietary.
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