IR 05000344/1998003
| ML20237E589 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/25/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20237E581 | List: |
| References | |
| 50-344-98-03, 50-344-98-3, NUDOCS 9809010055 | |
| Download: ML20237E589 (13) | |
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ENCLOSURE 2 I
t U.S. NUCLEAR R3GULATORY COMMISSION l
'1EGION IV i
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Docket No.:
50-344 License No.:
Report No.:
50-344/98-03 Licensee:
Portland General Electric Company Facility:
Trojan Nuclear Plant
Location:
121 S. W. Salmon Street, TB 17 Portland, Oregon D 6.'s:
July 27-30,1998 Inspector:
J. V. Everett, Sr. Health Physics inspector Fuel Cycle / Decommissioning Branch Accompanied D. Blair Spitzberg, Ph.D., Chief By:
Fuel Cycle / Decommissioning Branch Approved By:
D. Blair Spitzberg, Ph.D., Chief Fuel Cycle / Decommissioning Branch Attachment:
Supplemental information
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9009010055 980825 PDR ADOCK 05000344 l
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2-EXECUTIVE SUMMARY Trojan Nuclear Plant NRC Inspection Report 50-344/98-03 Decommissioning and dismantlement of the Trojan facility was proceeding with no significant safety or radiological problems. Work observed during this inspection was being conducted safely and in compliance with health physics requirements. A significant amount of material had been removed from the containment building and the auxiliary / fuel building since the last inspection. Radiological exposures were being maintained at acceptable levels for the work underway. Shipments of radwaste from the site were occurring on a frequent basis representing the significant amount of dismantlement activity being completed.
The new modular spent fuel pool cooling and cleanup system was being tested. The system test should demonstrate that pool temperature will be maintained below technical specification limits, even during the hottest summer months. Testing included collecting data for conditions when the cooling system was not running at full capacity. Preliminary indications were that initial pool temperature increases would be approximately 10 F per day, should the cooling
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system fail. This would provide for several days to complete repairs on the system before pool
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temperatures would exceed Technical Specification limits.
Spent Fuel Pool Safety
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The spent fuel pool was being maintained in compliance with Technical Specifications
for water level and water temperature (Section 1).
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Testing of the new modular cooling and clean up system for the spent fuel pool was
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underway. Preliminary results indicated the pool temperature would reach a high of
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approximately 100*F during hot summer months. The Trojan Technical Specification limit for spent fuel pool temperature was 140 F (Section 1).
Occupational Radiation Exposure
- An occupational site dose to workers of 26 man-rem had been accumulated during the J
first two quarters of 1998. The highest dose received by any individual for the first half
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of the year was 493 millirem (Section 2).
Tours were conducted in the auxiliary / fuel building and containment. Health physics
controls and postings were adequate. Workers were observed cornplying with radiological requirements (Section 2).
Decommissioning Performance and Status Review During the tours of the auxiliary / fuel building and containment, no problems were a
observed related to housekeeping, fire loading, and OSHA compliance (Section 3).
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Planning for shipment of the reactor vessel and internals to Hanford, Washington, for
burial was continuing. The pathway analysis associated with the burial of the reactor vessel had been completed and was under review by the state of Washington. Public q
meetings were held at the Trojan facility and in Kelso, Washington, to discuss the I
technicalissues for shipment of the reactor vessel and provide an opportunity for public l
comment (Section 3).
l Organization. Manaaement. and Cost Controls l
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Medical response to an emergency at the Trojan facility involving contaminated and l
injured personnel would require ambulance service from the Rainier Fire Department l
and medical services from St. John Medical Center. Meetings were conducted with both
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organizations to verify arrangements were current for providing medical support to the l
l Trojan facility. Both agencies indicated that a strong working relationship existed with
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Trojan, including their participation in periodic training and drills (Section 4).
l Solid Radioactive Waste and Transoort q
l Selected radioactive waste shipping procedures were reviewed and determined to be
current. Implementation of the procedures was verified for three shipments of radwaste conducted during the week of this inspection. Characterization data being used for current radwaste shipments were appropriate for the type of radwaste being shipped l
(Section 5).
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Report Details
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Summary of Plant Status A significant amount of radioactive material had been removed from the Trojan facility. During l
the first 7 months of 1998,122 radwaste shipments had been completed. This rate of removal
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of material from the site was expected to continue for the rest of the year. In the reactor
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building, dismantlement was scheduled to be completed by the end of the year, except for equipment needed to support removal of the reactor vessel. Work was progressing on preparing the reactor vessel for removal. In the auxiliary building, considerable work had been completed on the removal of tanks, piping, and cables. Planning had been started on the final survey program. This major effort will require extensive surveys of plant areas to confirm that residual radiation levels have been mitigated to below license termination limits specified in Subpart E to 1CCFR Part 20,
Spent Fuel Pool Safety (60801,86700)
1.1 Inspection Scope Spent fuel pool compliance was inspected for Technical Specification 3.1.1, related to spent fuel pool water level and Technical Specification 3.1.3, related to spent fuel pool l
temperature. Results of the July tests for the new modular spent fuel pool cooling and clean up system were reviewed.
l 1.2 Observation and Findinas l
l Technical Specification 3.1.1 required the spent fuel pool water level to be maintained at
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or above 23 feet over the spent fuel. Records were reviewed for June and July 1998.
Water level had been maintained above 24 feet.
Technical Specification 3.1.3 required the spent fuel pool water temperature to be maintained at or below 140 F. Records for June and July 1998 were reviewed. Water temperature was maintained between 70 F and 110 F. A test of the new modular spent fuel pool system was conducted during July. The spent fuel pool was allowed to heat up over a 4-day period with no active cooling. The spent fuel pool heat-up rate was
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approximately 10 F/ day. Maximum temperature reached was 110 F before the fans for the modular cooling system were turned on. The pool temperature decreased to approximately 100 F. Based on these tests, the pool temperature is expected to be 25'F to 30*F above the average ambient daily temperature (average between daily high and daily low) with both fans operating. With only one fan operable, the difference between pool temperature and average ambient temperature was estimated to be approximately 50*F.
i Surveillance Requirement 3.1.3.1 required the temperature of the spent fuel pool to be determined using a NationalInstitute of Standards Technology (NIST) traceab!e l
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l instrument. The licensee used a resistance temperature detector (RTD) placed approximately 3 feet below the water level of the spent fuel pool to measure the pool temperature. The RTD was calibrated against a platinum resistance thermometer system (PRTS) which was traceable to an NIST standard. The licensee maintained paperwork for the PRTS confirming traceability. The certificate for the PRTS was provided by the John Fluke Manufacturing Company and documented a testing date of November 18,1993.
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The new modular cooling system had intake and outlet points on a different side of the
spent fuel pool than the current system. The new system's inlet and outlet points were i
located closer to the RTD. Because the spent fuel pool will be operating at a higher i
I temperature and much closer to the Technical Specification limit, confirmation of the adequacy of the location of the RTD to measure a representative spent fuel pool temperature is necessary. The licensee planned to conduct several temperature readings <at various locations in the pool to verify that the location of the RTD still provided a representative reading of the spent fuel pool temperature. This will be tracked as an inspection follow-up item (50-344/9803-01).
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NRC Information Notice 97-14, " Assessment of Spent Fuel Pool Cooling" was discussed with the licensee concerning the review of this information notice to determine applicability to the new system. Several of the issueo discussed in the information notice were found to be included in the safety evaluation for the new system. However, the safety evaluation did not indicate that a comprehensive review of all relevant information notices and bulletins had been completed. A comprehensive review was initiated by the licensee. A review of relevant information notices and bulletins again.st the new system will be tracked as an inspection follow-up item (50-344/9803-02).
1.3 Conclusion The spent fuel pool was being maintained in compliance with Technical Specifications for water level and water temperature.
Testing of the new modular cooling and clean up system for the spent fuel pool was
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underway. Preliminary results indicated the pool temperature would reach a high of approximately 100 F during hot summer months. The Trojan Technical Specification limit for pool temperature was 140*F.
Occupational Radiation Exposure (83750)
2.1 Insoection Scope Occupational exposures for site personnel were reviewed for the first two quarters of 1998. Plant tours were conducted to observe contamination controls in work areas and posting of radiation areas.
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2.2 Observation and Findina A review was conducted of the personnel exposures for the first two quarters of 1998.
Forty-three radiation work permits were active with 434 personnel badged onsite. The total accumulated site dose was 26 man-rem. For the first half of the year, twenty-six individuals had received over 250 millirem, with the highest dose of 493 millirem received by a contractor working on dismantlement activities.
During plant tours of the auxiliary / fuel building and containment, radiological controls and postings were observed to be adequate. Workers were observed complying with health physics requirements. Contaminated areas were posted and protective clothing I
was readily available. Step-off pads and receptacles for contaminated clothing were property positioned at exit points from contaminated areas.
2.3 Conclusion i
An occupational site dose to workers of 26 man-rem had been accumulated during the
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first two quarters of 1998. The highest dose received by any individual for the first half of the year was 493 millirem.
Tours were conducted in the auxiliary / fuel building and containment. Health physics controls and postings were adequate. Workers were observed complying with radiological requirements.
Decommissioning Performance and Status Review (71801)
3.1 Insoection Scope The progress of dismantlement activities was reviewed. The inspector accompanied an auxiliary operator performing daily routines in the auxiliary / fuel building. A tour of containment was conducted with the licensee to review activities related to removal of l
the reactor vessel. During the tours, housekeeping, fire loading, and OSHA compliance were observed.
Two meetings were attended concerning the reactor vessel removal project and shipment of the reactor vessel to Hanforo, Washington, for burial.
l 3.2 Observation and Findinas Activities related to the dismantlement of the Trojan facility were progressing. Work appeared to be consistent with schedules. In the auxiliary / fuel building, approximately 85 percent of the equipment in the east and west horizontal pipe chase had been removed. Various holdup tanks, filters, piping for the boron injection tanl: room, volume control tanks, and equipment from the radiological sample lab had been removed. In containment, equipment removal was on schedule for completion by the end of 1998, except for equipment needed to support removal of the reactor vessel. The alternate l
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-7-containment access control point had been installed and was being used by workers to provide easier access to containment.
A tour of the plant was conducted to observe work underway. The tour of the auxiliary / fuel building included accompanying an auxiliary operator performing daily routines. The auxiliary operator implemented Attachment 1," Auxiliary Operator Rounds Sheet," of Procedure OG 13-100," Auxiliary Operator Rounds," Revision 23. The attachment to the procedure provided a detailed list of areas and equipment to be checked and provided the acceptable ranges for instrument readings. The auxiliary operator was knowledgeable of plant areas and was aware of the current operational status of various systems. The auxiliary operator performed safety tagging of equipment and verification of proper readings on instruments and correct settings on valves. A tour of containment was also conducted with the licensee to observe progress of work and review the process planned for removal of the reactor vessel. During the tours of the auxiliary / fuel building and containment, no accumulation of waste material or material that presented a fire hazard was observed. Designated storage locations were established for material awaiting removal from the area. Work was being conducted safely, No occupational safety concerns were observed.
The licensee was continuing the effort to obtain NRC approval to ship the reactor vessel and internals to Hanferd, Washington, for burial. The construction of the barge for shipment had been completed. A pathway analysis for burial of the reactor vessel had been completed and sent to U. S. Ecology, which forwarded the analysis to the state of Washington for review. The state of Washington was actively reviewing the analysis.
- Two public meetings were held on July 30,1998, to discuss the licensee's plans to ship the reactor vessel and internals to Hanford, Washington. The first meeting, held at the Trojan site, provided an opportunity for the licensee's technical staff and the NRC to discuss the technical issues related to the shipment and the recently issued NRC request for additionalinformation. The second meeting was held in Kelto, Wash;ngton, to provide an opportunity to discuss the planned shipment with members of the public and receive public input. Two members of the public provided comments.
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. Conclusion Tours were conducted of the auxiliary / fuel building and containment. No problems were I
observed related to housekeeping, fire loading, and OSHA compliance.
Planning for shipment of the reactor vessel and internals to Hanford, Washington, for burial was continuing. The pathway analysis associated with the burial of the reactor i,
vessel had been completed and was under review by the state of Washington. Public meetings were held at the Trojan facility and in Kelso, Washington, to discuss the technical issues related to shipment of the reactor vessel and provide an opportunity for public commen _
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Organization, Management, and Cost Controls (36801)
4.1 Inspection Scoce The Trojan emergency plan described provisions for handling medical emergencies which included support from the Rainier Fire Department for ambulance service and St. John Medical Center for medical treatment of contaminated and injured persons. A meeting with the two agencies was conducted to verify that arrangements were current for providing support to Trojan.
4.2 Observation and Findinos The Trojan emergency plan, Section 3.4 identified the Rainier Fire Department and St. John Medical Center as offsite support organizations for medical emergencies involving contamination or radiological exposure. Appendix A to the emergency plan included an agreement letter from St. John Medical Center dated September 15,1983.
The licensee annually reviewed and confirmed the agreement letter. The most recent correspondence with St. John Medical Center was dated June 30,1998. This correspondence consisted of a letter from the licensee to St. John Medical Center confirming the agreement between Portland General Electric and the hospital. The 1983 agreement letter was attached. St. John Medical Center initialed the agreement letter and returned it to the licensee.
A meeting was conducted with the St. John Medical Center coordinator to discuss the arrangements for receiving and treating a contaminated or radiologically injured person.
The coordinator indicated that the working arrangement with the licensee had been very good. The coordinator considered the hospital to be capable of responding to an injured person from Trojan. This was due to the many years of support provided by the licensee and the experience gained by the hospital staff from training and from drills on
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handling simulated contaminated and injured persons. The hospital staff conducted
training at least once a year which included discussions on radiological emergency response.
The hospital was undergoing renovation, which included a number of changes to the emergency room area. Several changes suggested by the licensee during past drills had been incorporated into the remodeling. This included considerations for movement of individuals into the facility and the type of flooring in those areas which would facilitate easy decontamination. The coordinator felt supplies provided by the licensee were adequate based on past drills. Survey instruments were included in the emergency
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inventory maintained at St. John Medical Center by the licensee. The last inventory had j
l been performed on May 12,1998. Inventories were conducted by the licensee
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l semiannually and after drills.
t The Rainier Fire Department provided fire and ambu!ance service to the Trojan site under a fire district agreement. This agreement was established March 29,1995, and provided for the Trojan site to be annexed into the Rainier Rural Fire Protection District.
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l A meeting was held with the Rainier Fire Department Chief to discuss the ambulance support provided to the licensee. Six members of the fire department were trained and l
badged for access to the Trojan site. All ambulance personnel were provided an l
opportunity for annual radiological training. This provided for expedient access of
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ambulance personnel to the site during an emergency. Radiological monitoring instrumentation was available at the Trojan site to be taken on the ambulance. The Rainier Fire Chief was satisfied with the arrangements and support being provided by the licensee and felt that the periodic medical emergency drills and fire drills being conducted with the licensee had prepared his organization to respond to an incident at the site.
4.3 Conclusion Medical response at an emergency at the Trojan facility involving contaminated and injured personnel would require ambulance service from the Rainier Fire Department and medical services from St. John Medical Center. Meetings were conducted with both l
organizations to verify arrangements were current for providing medical support to the Trojan facility. Both agencies indicated that a strong working relationship existed with
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Trojan, including their participation in periodic training and drills.
Solid Radwaste and Transportation (86750)
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5.1 Inspection Scope The licensee's program for shipping radioactive waste was reviewed. This included a review of three shipments being made by the licensee during the week of this inspection.
5.2 Observation and Findinas I.
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The licensee maintained eighteen procedures related to the packaging, storing, and
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shipping of radioactive material. These procedures were included in the RP 300 series procedures. The following RP 300 procedures were reviewed during this inspection:
l RP 300 Radioactive Material Shipment by Public Highway dated 6/13/96 RP 303 Shipment of Radioactive Waste dated 4/16/97 RP 310 Determination of Radioactive Material Shipping and Waste q
. Classification dated 4/16/97 RP 312 Sample Program to Determine isotopic Concentrations and Scaling Factors for Classification of Low Level Solid Radioactive Waste dated 3/20/97 RP 320 Routine Packaging of Radioactive Waste dated 12/16/96
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RP 323 Packaging Dry Radioactive Waste in Metal Boxes dated 6/3/98 l
The procedures reviewed were complete and current and included the relevant I
requirements from Title 49 of the Code of Federal Regulations. In addition to the review I
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During 1998,122 radwaste shipments had been made by the licensee, primarily to the U.S. Ecology site at Hanford, Washington for burial and to a laundry services for cleaning of protective clothing.- Shipments were typically classified as low specific activity (LSA) or surface contaminated objects.
On July 28,1998, the licensee had completed activities related to three shipments of radwaste. Prior to the shipments leaving the Trojan site, an independent assessment was made by the inspector. Two shipments were destined for U.S. Ecology and one shipment for Interstate Nuclear Services, Richland, Washington. Radiation levels for all three shipments were independently verified and found to be consistent with the
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measured radiation levels included in the shipping paperwork. The trucks were observed to be properly placarded.
Shipment No.98-122 consisted of four large boxes on a flatbed trailer. The shipment included metal, cables, and trash. The shipment was classified as LSA-Il and consisted of 2.6 mci, primarily iron-55, nickel-63, cobalt-60, and cesium 137. The shipping paperwork provided to the truck driver was reviewed. The paperwork included NRC Form 540 and 541, Waste Manifest, and the following completed attachments to Procedure RP 300, " Radioactive Material Shipment by Public Highway":
RP 300 Attachment 3 Carrier / Driver Instructions for Maintenance of Exclusive Use Shipment Controls RP 300 Attachment 6 Vehicle Survey RP 300 Attachment 9 Low Level Radioactive Waste Shipment Certificate i
RP 300 Attachment 10 Certification RP 300 Attachment 13 Discrete Radioactive Particle Letter RP 300 Attachment 15 Twenty-four Hour Emergency Contact All paperwork was found to be complete. In addition, the truck driver was knowledgeable concerning the type of materialin the load, the relative hazard of the i
radioactive material, and the process for notification of the licensee if problems were encountered.
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in order to determine the isotopic content in a radwaste shipment, the licensee had sent a number of samples over the past several years to a contract laboratories for isotopic analysis and characterization. Samples had been taken from spent resins, filters, drains, storage tanks, concrete and scrapings from pipes.
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Many of the samples had been taken during 1992 to 1994 and were c.
corrected to provide current isotopic levels. Spent resins were analyzed for shipping.ae spent resin liners. Predominant isotopes included uranium-235/238, plutonium-238/239/240, cobalt-60, cesium-137, iron-55, tritium, and nickel-63. For piping, scrapings were taken
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and analyzed in June,1998. Predominant isotopes in the pipe scrapings included cobalt-60, manganese-54, plutonium-239/240, and curium-243/244. For dirty waste l
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system samples taken in 1992 and 1994, the predominant isotopes were iron-55, nickel-63, cobalt-60, and cesium 137.
5.3 Conclusion Selected radioactive waste shipping procedures were reviewed and determined to be current.' implementation of the procedures was verified for three shipments of radwaste conducted during the week of this inspection. Characterization data being used for current radwaste shipments were appropriate for the type of radwaste being shipped.
Exit Meeting The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on July 30,1998. The licensee acknowledged the
'e Jings presented. The licensee did not identify as proprietary any information provided 9., or reviewed by, the inspector, f
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ATTACHMENT PARTIAL LIST OF PERSONS CONTACTED Licensee A. Aldrich, Auxiliary Operator A. Bowman, Radiation Protection Supervisor J. Cooper, Emergency Preparedness Engineer J. Fisher, Engineering K. Hanson, Operations G. Huey, Radiation Protection Technical Support Manager E. Lazier, Shift Manager 1. Li, I&C Engineer T. Meek, Radiation Protection Manager J. Mihelich, Engineering Manager M. Murdock, Radwaste Specialist H. Pate, Licensing Manager L. Rocha. Health Physicist S. Schnieder, Plant Operations Manager State of Oreaon A. Bless, Resident inspector, Oregon Office of Energy Offsite Suocort Organizations T. Grice, Chief, Rainier Fire Department S. Spears, Coordinator, St. John Medical Center l
INSPECTION PROCEDURES USED l
36801 Organization, Management, and Cost Controls at Permanently Shutdown Reactors 60801 Spent Fuel Pool Safety at Permanently Shutdown Reactors
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l 71801 Decommissioning Performance and Status Review at Permanently Shutdown j
l Reactors 83750 Occupational Radiation Exposure 86700 Spent Fuel Pool Activities 86750 Solid Radwaste and Transportation i
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ITEMS OPENED, CLOSED, AND DISCUSSED l
Opened 50-344/9803-01 IFl Verification of Adequacy for Location of the Spent Fuel Pool i
Temperature Sensor
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50-344/9803-02 IFl Review of New Spent Fuel Pool System Against Applicable NRC Information Notices and Bulletins q
Closed None Discussed f
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LIST OF ACRONYMS I
CFR Code of Federal Regulations IFl Inspection follow-up item
l LSA low specific activity
NIST NationalInstitute of Standards Technology
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PRTS platinum resistance thermometer system RTD resistance temperature detector
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