IR 05000155/1999005
| ML20212K780 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 09/30/1999 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20212K759 | List: |
| References | |
| 50-155-99-05, NUDOCS 9910070048 | |
| Download: ML20212K780 (54) | |
Text
l U.S. NUCLEAR REGULATORY COMMISSION REGIONlli Docket No: 50-155-License No: DPR-06 Report No: 50-155/99005(DNMS)
Licensee: Consumers Energy Company Facility: Big Rock Point Nuclear Power Plant Location: 10269 U.S. 31 North Charlevoix, MI 49720 Dates: July 31, through September 21,1999 - Site inspection September 29,1999 - Public Meeting l
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Inspectors: R. J. Leemon, Reactor Decommissioning Inspector R. B. Landsman, Project Engineer I W. G. Snell, Health Physics Manager . l
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P. W. Harris, License Project Manager Approved By: Bruce L. Jorgensen, Chief Decommissioning Branch Division of Nuclear Materials Safety i
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9910070048 DR 990 g g ADOCK 05000155 PDR j
EXECUTIVE SUMMARY Big Rock Point Restoration Project NRC inspection Report 50-155/99005(DNMS)
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This routine decommissioning inspection covered aspects of facility management and control, decommissioning support activities, spent fuel safety, and radiological safety. In addition, licensee, contractor, and Region ill staffs met at a public meeting on September 29,1999 in Region Il Overall, major decommissioning activities were properly monitored and controlled, and they were performed on schedule. The second phase of the spent fuel pool clean out project, involving processing and shipping control rod blades for burial and the removal of significant quantities of radioactive material from the spent fuel pool, was completed. Nine shipping casks, each loaded with crushed control blades and other reactor vessel components, were successfully loaded and shipped to a licensed burial site, with good worker performance around the fuel pool and notable as-low-as-reasonably-achievable success in achieving decreasing per-cask dose Facility Manaaement and Control 1
- Self-assessments and independent auditing by NPAD appeared to be effective and tha corrective action system was functioning as designe * The material condition of systems, structures, and components important for the safe storage of spent fuel and conduct of safe decommissioning appeared to decline, but was still being maintained at a good overall level. Housekeeping and control of combustible materials were good, and fire equipment was being properly maintaine * The licensee made the proper response and notifications to an actuation of a fire alarm on September 1,199 Decommissionino Support Activities
- Planning, coordination, management oversight and worker performance during the ;
second phase of the spent fuel pool clean out project remained goo j
- Maintenance, personnel safety, fire protection, radiation protection, and health physics !
survey practices were all performed well and in compliance with applicable requirements during plant dismantlement activitie Soent Foel Safety
- Tho safety of the fuel la the spent fuel pool was being maintained, with spent fuel pool terr perature at about 10 *F above the temperature of Lake Michiga J
Radioloaical Safety
- Condition Reports relating to radiation protection were sufficiently detailed with well stated conclusions and appropriate corrective actions. Event investigations were typically thorough with all aspects adequately addressed. However, there was some concern raised as a result of three unrelated incidents in a 15-day period that all contained a root cause related ta poor worker performance.
- Al. ARA planning and radiation work permit briefings for job tasks were effective, as was use of remote TV monitoring of spent fuel pool activities.
- The loading and shipment of a cask for transport to a licensed burial site were carried out as required, with associated documentation and record keeping was completed as specified by procedure.
- The " Phase 2" portion of the SFP cleanout project, involving processing and shipment control rod blades for burial, was accomplished with decreasing per-cask exposures as experience was gained; Al. ARA goals were reduced and the lower dose goals were met.
- Radiological control activities in the areas of effluents and solid radwaste were being conducted safely and in compliance with applicable requirements.
Public Meetina
- A public meeting was held in Region 111 on September 29,1999, to discuss the project status and future plans for the Big Rock Point Restoration Project. The licensee's presentation handout is attached to this repor r-Report Details Summary of Plant Activities During the inspection period, equipment not necessary for the oafe storage of spent fuel was
- removed from the facility. The second phase of the spent fuel pool (SFP) clean out project, involving processing and shipping control rod blades for burial and removal of significant quantities of radioactive materials form the spent fuel pool, was completed. The third phase of the spent fuel pool clean out project (processing fuel channels and support tubes for burial) was begu .0 ~ Facility Management and Control General The inspector conducted frequent reviews of ongoing plant activities and attended licensee meetings and reviews addressing these activities, in order to assess overall facility management and controls. Specific events and findings are detailed in the sections belo .2 Oroanization. Manacement. and Cost ContrW at Permanentiv Shut Down Reactors (36801)
The inspector selectively reviewed the licensee's activities involving overall management and control of the decommissioning process. The effectiveness of the licensee's review of regulatory information applicable to the facility was selectively examine .2.1 Manaaement Re-Oraanization On August 10,1999, a new Big Rock Point Site Organization was put into place. The new organizational departments and managers are as follows:
Site General Manager- Ken Powers Cost, Scheduling & Purchasing - Bill Trubilowicz Engineering, Operations & Licensing - Greg Withrow Dismantlement Maintenance and Planning - Harry Linsinbigler Radiation Protection & Environmental - Mark Lesinski Human Resources, Training & Administrative - Ellen Zienert 1.2.2 Decommissionina Fund Manaaement With interest eamed on the decommissioning fund and the new money collected, the balance of the decommissioning fund has remained roughly equal to the money that was in the fund when the decommissioning project started, around $180 million. Fund management and overall control of the project budget were considered goo _ _ . - Safety Reviews. Deslan Chanaes. and Modifications at Permanentiv Shut Down Reactors (37801) Insoection Scooe The inspector monitored the licensee's safety review program to determine if the program was effective at identifying potential unreviewed safety questions (URSQs) in accordance with 10 CFR 50.59. The activities of the licensee's onsite safety review committees (SRC) were evaluated to determine whether they were fulfilling their respective charters, the requirements of Defueled Technical Specification (DTS), and the requirements of the quality assurance (QA) pla Observations and Findinas The SRC continued to perform frequent reviews of modifications and procedures during the decommissioning proces When attending SRC meetings, the inspector observed that a quorum was present and that the members understood the change to the procedure or plant modification under discussion. Procedures related to cutting and crushing fuel channels and support tubes were reviewed during this inspection period. The members held challenging discussions on items prior to determining that the change did not create an URS Safety Review Committee members discussed and reviewed procedure changes to ensure they were clear, accurate, and had the same meaning to all members of the committee. Human factors wee considered in the changing of these procedures. Each procedure change was evaluated to determine if an URSQ was created. None were create Conclusion Safety committee discussions were challenging and there were no issues which required changes to Technical Specifications (TSs), no URSQs were identified, and the requirements of 10 CFR 50.82 were me .4 Monitored Decommissionina Activities The inspector attended licensee meetings where the planning, reviewing, assessing, and scheduling of decommissioning activities were observed. The inspector ascertained that activities were in accordance with licensed requirements and docketed commitments as stated in 10 CFR, DTS, Updated Fina Hazards Summary Report (FHSR), Post-Shutdown Decommissioning Activities Report (PSDAR), and Defueled Emergency Plan (DEP). Decommissioning activities monitored by the inspector were as described in the following section .4.1 Plant Systems and Comoonents Removed from Service Plant systems and components determined not needed for the safe storage of spent fuel and permanently removed from service during this inspection period were:
portions of the post incident shutdown cooling system
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portions of the reactor cooling system (a support cooling system interface between radioactive systems and the service water system)
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turbine lube oil system i
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original spent fuel pool cooling system
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1.4.2 Plant Modifications Specific design changes or modifications were reviewed to assess program t effectiveness. This included a review of written safety evaluations and other records. In addition, a sample of maintenance and repair activities was reviewed to ascertain whether the licente had made changes to the facility without properly invoking their safety review proces ]
Plant modifications that were in progress or completed during the inspection period were:
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planning fo dry c'ask storage of spent fuel I
execution ,2; the SFP clean out project Phase 2 {
. Installation of pipe tunnel to containment access door
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building an enclosure for the hazardous materials building Two major criter'a used by the licensee for scoping decommissioning activities were annual budgeted money and budgeted person-rem exposure. No concems were identified with the scope and status of monitored decommissioning activitie .5 Self-Assessment. Auditino. and Corrective Action (40801)
1. General The 'icensee's controls for identifying, resolving and preventing issues that degrade
% or quality were examined, including self-assessments, auditing, corrective au ans, root cause evaluations and third party reviews. The inspector also attended corrective action review boards (CARBs) and management review boards (MRBs).
The QA plan and applicable implementing procedures formed the basis for the inspection. In addition, the procedures were evaluated from the perspective of their adequacy to accomplish the objective of assuring that management and staff are knowledgeable of plant / activity performance and contribute effectively to safety and quality in conduct of important activitie .5.2 Independent Assessment of BRP Activities Inspection Scope The inspector held discussions with Nuclear Performance Assessment Department (NPAD) assessors, attended NPAD exit meetings, and reviewed NPAD audits and reports and condition reports written by NPAD. The condition report provides tracking of the finding and assigns resources to determine the root cause of the finding so tnat the root cause can be correcte Observations and Findinas .
The inspector observed NPAD actively monitoring decommissioning activities and pre-job briefings, and providing management timely feedback on their concerns. The area of health physics was well monitored, with field reports written, and corrective actions generated by the NPAD health physics inspector. This indiviaual recently moved on to a new job outside the company, which has created a vacancy in NPAD staffing in a critical area. The licensee plans on filling this position with rotational personnelin the short term and then refilling the positio The onsite leader of NPAD met with plant management at a planned monthly meeting to discuss NPAD's findings, and to answer any questions on the findings. Conditions identified by NPAD as adverse to quality were entered into the plant corrective action system via condition report to ensure follow u When the licensee self-identified concerns or abnormal conditions, the appropriate condition report was written and dispositioned by the CARB. The inspector reviewed condition reports, reviewed closed corrective actions for condition reports, and reviewed trend reports for the correctiva action system. The inspector also attended CARBs and MRBs. The corrective action system was being managed, generally correct root causes were being identified, and corrective actions were being closed in a reasonable tim Conclusion NPAD appeared to be effectively performing their function and the corrective action system was functioning as designed.
' Decommissionina Performance and Status Review at Permanentiv Shut Down Reactors (71801)
1. General The performance of the licensee and contracted workforce in conducting decoinmissioning activities was evaluated to determine if the activities were in comr liance with license requirements and commitments. Control and conduct of facility dec9mmissioning activities were examined to verify the requirements of the license and DTS were fellowed, and to ensure the requirements and commitments described in the Updated Final Hazard Summary Report, PSDAR, and DEP were followed. Specific events and findings are detailed in the section belo .6.2 Plant Tours to Evaluate Material Conditions. Housekeeoina. and Fire Protection Inspection Scope The incpector conducted plant tours to evaluate the material integrity of systems / structures / components (SSCs) necessary for the safe storage of spent fuel and conduct of safe decommissioning, to observe and assess the status of facility housekeeping, and to evaluate fire protection issues such as control of combustibles, condition of fire fighting equipment and presence of the plant fire brigad Observations and Findinos Observations from plant tours showed that the material integrity of SSCs important to safe storage of spent fuel (ISSSF) was being maintained. The inspector discussed tour observations with plant management. The inspector also observed that plant management was actively monitoring plant material conditions. During this inspection period, the plant's material condition declined but remained at a good leve Housekeeping observations focused on the areas adjacent to and containing SSCs necessary for the safe storage of spent fuel, effluent control, or radiation protection and monitoring. All areas of the plant were kept adeqately clean; dismantlement debris was promptly placed into metal boxes. Portable cables were routed so as not to cause tripping hazards. Geneal area housekeeping was good during this period with no areas of inspector conce The storage of combustible and flammable materials met fire loading limits for transient combustibles and combustible materials were not accumulating in the plant. The fire fighting equipment and stations were properly maintained and ready for use. The installed fire detection and suppression systems were effectively maintained, surveillance tests were performed, and the equipment was capable of performing the intended function Active dismantlement activities which included cutting and grinding were performed with the proper fire protection in place. No fires were started during these activitie Conclusion Material integrity of SSC's important to safe storage of spent fuel and safety in decommissioning was being maintained. Housekeeping, control of combustible materials and operation of fire equipment were properly maintaine .6.3 Fire Alarm Actuation and 4 Hour Notification to the NRC On September 1,1999, smoke in the recirculation pump room caused a fire alarm in the
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monitor station. The plant procedures and emergency plan ( DEPlP-3, Emergency Notifications) require calling the Charlevoix Township Fire Department and having the trucks respond and standby at the site. Two trucks responded and stood by at the main gate. The emergency plan requires that a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> notification be made to the NRC of any planned press release that is related to health and safety of the public or onsite personnel. Since the fire trucks at the front gate could generate news interest, the phone call was make within the time limit. A short news article, " Smoke, no fire at Big Rock," was printed in the Charlevoix Courier on September 8,199 The smoke was caused by a smoldering ember on the cloth lagging cover. The metal sleeve for the main steam line penetration was being cut with a cutting torch. Some slag dropped on the cloth lagging cover and started smoldering. Since the recirculation pump room was at a more negative pressure than the pipe tunnel where the cutting was taking place, the smoke went to the recirculation pump room and caused the fire alar The fire brigade responded and sprayed water onto the smoldering cloth extinguishing the ember. The fira brigade did not observer any flames or fir The licensee made the proper response and the correct notifications for a smoldoe ng ember on the lagging cover. Decommissioning Support Activities Maintenance and Surveillance at Permanentiv Shut Down Reactors (62801)
The inspector evaluated maintenance and surveillance on SSCs potentially affecting the safe storage of spent fuel and reliable operation of radiation toonitoring and effluent control equipment. Direct observations, reviews, and interviews of licensee personnel .
were conducted to evaluate the proper implementation of DTS, and 10 Cf R 50, Appendix B requirements. Dismantlement Activities (62801)
Dismentlement activities observed or evaluated by the inspector during the period were:
- - removal of equipment from the electrical and air compressor room
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reactor cooling heat exchanger room dismantlement completion a lube oil room dismantlement '
The inspector observed that proper maintenance, personnel safety, fire protection,-
radiation protection, and health physics survey practices were performed during these activities. Soent Fuel Pool Clean Out Proiect Activities (62801)
a. Inspection Scope The SFP clean out project involves the removal of all non-fuel bearing components from the SFP. For this project, the reactor vessel was being used as a water shielded processing tank. Each component was surveyed, radioactively characterized and classified, processed, packaged, and shipped for burial-inspection of radiological control activities is discussed in Paragraph 4.3 below. The inspector observed workers performing various of these activities in and around the SFP and the reactor cavity. The inspector also attended planning meetings, attended pre-job and as-low-as-reasonably-achievable (Al. ARA) daily briefings and reviewed the SFP clean out project contingency plan b. Observations and Findinas The SFP project meetings were well organized. The daily plans were described, including possible ' fill in" work identified at the previous day's planning meeting. Work experiences from the previous day were discussed at each meeting. Contingency measures for unexpected radiological conditions were provided, along with discussion of the overall Al. ARA plan for the project. Worker participation was fostered by asking questions and by generating interactions among the various work groups. Daily, staff ;
were reminded that radiation protection (RP) had the authority to stop work at any time that the dose rate or RP practices were in question. When the dose rates from objects coming out of the water were in question this authority was exercised and the object was lowered back into the water until the situation was evaluated. Thus, no unnecessary radiation exposure was received by the workers. Daily work activities were performed
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I well on the reactor deck. When problems were encountered, the supervisors were notified and the activity was stopped. The correct contingency plan was generated and executed or repairs were made to processing equipment. Appropriate condition reports were written so the problems could be evaluated by managemen '
The second phase of the SFP clean out project, which was completed during this inspection period, mcluded the following activities for each shipment:
1) Filling the inner basket: transporting control road blades (CRBs) to the reactor vessel, crushing them, then loading them into a basket along with a container of Stellite rollers which had been cut off the CRBs before crushing. Also, transporting other items to the reactor to fill the basket (CRB spud ends, incore detectors, and other radioactive reactor hardware).
2) Filling the cask: removing the CRB crusher from the reactor vessel, dose profiling the bottom of the cask liner, placing the shipping cask into the reactor vessel, inserting the liner into the shipping cask, placing the basket into the liner, placing the liner closure lid on the liner, dose profiling the upper portion of the liner, and placing the shipping cask closure lid on the shipping cas ) Draining and deconning the cask: removing the cask from the reactor vessel, draining, surveying and moving the cask from the reactor deck to the equipment lock lay down area, decontaminating, and re-surveying to determine that radioactive material shipping requirements were me ) Placing the cask on the truck: removing the cask from the containment, transporting to the turbine building truck bay, loading onto the shipping truck, and surveying and smearing the cask again to ensure that the department of transportation regulations were me Nine shipping casks have been loaded and transported to the burial site. Each shipping cask typically held 13 CRBs, but one shipment held only two CRBs. The nine shipments completed Phase 2 of the projec The third phase of the spent fuel pool clean-out project processes fuel channels and support tubes for burial has begu At the end of the inspection period, equipment setup and dry run testing for the third phase of the spent fuel pool clean out project had begun. The team will work two 10-hour shifts and plans to complete the third phase (process and send for burial 441 fuel channels with support tubes) by the end of January 200 c. Conclusion l
Good worker performance was observed during the second phase of the SFP clean out !
project. NRC and Department of Transportation requirements were me .4 Ooerational Safetv Verification (71707)
i The standards of performance being observed by the operations staff remained well disciplined. No violations of NRC requirements occurred during this inspection perio .0 Spent Fuel Safety Jnggection Scooe (60801)
The inspector evaluated spent fuel and fuel pool safety. Factors considered in the evaluation included: SFP heatup rate; SFP instrumentation, alarms, and leakage detection; SFP chem'stry and cleanliness control; criticality controls; and SFP operation and power supply. 7ne inspector reviewed station logs and held discussions with the licensee. The inspisctor also inspected the SFP and SFP support system's valve lineups during plant tour Observations and Findinas The inspector locally monitored SFP level and temperature. The inspector verified the criticality monitor was functioning. The inspector also observed that foreign material controls were being used in and around the SF On September 8, the SFP temperature was 76*F and the time for the temperature to rise to 150*F was 14.0 days. The present SFP hestup rate is 0.22*F/ hour. The SFP temperature is about 10 *F above the temperature of Lake Michigan. During this inspection period the SFP altemate cooling system was shut off during the time when the SFP clean out project activities were in progress to reduce the amount of corrosion products potentially getting into the system. Controlling the temperature of the SFP within the operating band with this type of operation was not a proble Conclusion The safety of the fuel in the SFP was being maintained. Also, the SFP temperature is being maintained about 10 *F above the temperature of Lake Michigan. Radiological Safety General The inspector conducted reviews of ongoing activities in order to assess the overall RP program. Specific findings are detailed in the sections below. Occuoational Radiation Exoosuri a. Inspection Scooe (83750)
Numerous aspects of licensee processes to minimize occupational radiation exposure were selectively examined in order to evaluate overall radiation safety and to provide for early identification of potential problems. Areas examined included: audits and appraisals; planning and preparation; training and qualifications of personnel; external exposure control; intemal exposure control; control of radioactive materials and contamination; surveys and monitoring; and maintaining occupational exposure ALAR Observations and Findinas A review was conducted of radiation protection related Condition Reports (CRs) issued during June and July 1999. The reports were noted to be sufficiently detailed with well
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stated conclusions and appropriate corrective actions. The investigations into the events that precipitated the CRs were determined to be very thorough with all aspects adequately addressed. However, three of these CRs occurred during a 15-day period between late May and early June, and could all be attributed to poor worker performance. The first, CR C-BRP-99-135, involved a contaminated jacket being taken offsite as a result of a radiation protection technician (RPT) not following proper personnel monitoring practices. The second, CR C-BRP- 99-147, occurred when an RPT failed to properly post a high radiation area (HRA). The third, CR C-BRP-153, involved cutting Circulation Water System supply lines flush with the floor, which was contrary to the work procedure, and subsequently allowed potentially contaminated water to enter these lines when an accidental spill occurred. Although these appeared to be unrelated events, the fact that they all contained a root cause related to poor worker performance is of concem. Subsequently, from the time these events occurred (in late May to early June) through early August, no additional worker performance problems caused radiological event c. Conciegignf k Radiation protection related Condition Reports reviewed were sufficiently detailed with well stated conclusions and appropriate corrective actions. The investigations into the events that precipitated the CRs were determined to be very thorough with all aspects adequately addressed. However, there was some concemed raised as a result of three unrelated incidente in a 15-day period that all contained a root cause related to poor woAer performanc j Processina and Removal of Materials from the SFP a. Insoection Scooe (83750. 83728) i The inspector reviewed the licensee's program for processing and removal of materials (CRBs, incore detectors, etc.) from the SFP, as described in Paragraph 2.3, above. The inspector also attended a kick-off and ALARA briefing for phase three of the spent fuel pool clean out project. During the inspection the inspector reviewed the following radiation work permits (RWPs):
RWP 899004 Tours, inspections, evaluations and job planning, security functions except coverage of specific RWP RWP B993025 Rigging / loading / handling / inspection and mockup of shipping cas RWP B993029 Repair of underwater equipmen RWP B993033 Processing CRBS and incore detectors in SFP/ Reactor Vessel for shipping and disposa RWP B993034 Dose Profiling Channels, Reactor Deck Setup, Characterize and !
Package LSA Items for Disposal j i
The inspector attended the pre-job, RWP, and ALARA briefings for jobs requiring the use of these RWP '
b. Observations and Findinas The ALARA and the RWP briefings addressed the anticipated radiological conditions, access control, and contamination control and hot particle issues. The licensee also generated specific dose goals for each RWP which were job task evaluated. For ALARA purposes (keeping unnecessary personnel off the reactor deck area during the SFP clean out project) RWP B99004 was rewritten to remove the reactor deck from the general tour fiWP. Several different RWPs were written to utilize the different ALARA considerations related to various tasks for the SFP clean out project. This was a good ALARA practice. Briefings reached the level of excellence as experience was gained, and the assignments of workers to the job tasks, and the communication of the work scope to the ALARA planners also improve With experience, the dose the workers received for processing each FSV cask was reduced. The ALARA goal was then also reduced, from 17.938 to 13.649 Person-Re The processing of control rod blades were completed within the reduced ALARA goa This was accomplished by continuous awareness of the dose on the reactor deck, waiting in the low dose waiting areas, and continuously filtering the water in the reactor vessel and the SFP to maintain the activity level of the water in the range of 1E-05 uci/cc. This translated into an effective dose of 1.4 mrem /hr on the bridges (a reduction from 6 mrem /hr at the start of the project) where most of the work was being performe TV monitors for monitoring the SFP Clean Out Project activities were placed in the computer room outside the controlled area. This was an ALARA item which allows management oversght of the project without the managers entering the controlled area, thus saving dose. There are two zoom, pan and tilt cameras which allow viewing activities in the SFP, in the reactor vessel and on the reactor deck. The inspector has observed good use by management of these monitor including determining when plant personnel should go to the reactor deck at the correct time for that person's activit c. Conclus,cns The SFP clean out crew's efforts to perform work in a more efficient manner, incorporate lessons leamed, pay attention to details, and always keep ALARA principles '
in mind, resulted in a notable per-cask dose reduction and achieved compliance with reduced ALARA goals Radwaste Treatment. and Effluent and Environmental Monitorina (84750)
The inspection included an evaluation of various aspects of licensee activities in the areas of waste treatment and effluent and environmental monitoring to ensure that radioactive waste treatment systems were being maintained and operated to keep onsite and offsite doses ALARA; to ensure that the licensee effectively controlled, monitored, and quantified releases of radioactive materials to the environment; and to ensure that required radiologicai 9nvironmental monitoring programs were effectively implemente :
I No problems were noted in review of these activitie )
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' Solid Radwaste Manaaement and Transoortation of Radioactive Materials (86750)
4.5.1 freneral The inspection included an evaluation to determine whether the licensee properly processed, packaged, stored, and shipped radioactive materials, in order to assess the potential for safety problems resulting from these activities and from the transportation of radioactive material No problems were noted in the evaluation of this area. Radiological control activities in the areas of effluents and solid radwaste were being conducted safely and in compliance with applicable requirement .5.2 Packina and Shionina the Shlooina Cask (86740. 86750) Inspection Scope (86740. 86750)
The inspector evaluated licensee compliance with NRC and Department Of Transportation (DOT) regulations for packaging and shipment of radioactive material Specifically, the inspection focused on the shipment of a significant quantity of licensed material inside a Type B shipping cask. Areas examined included: 1) shipping documentation; 2) loading of the cask within the reactor vessel; 3) closure of the cask for transport; 4) daily RWP briefings; and 5) Radiation Survey Technique Observations and Findinas This inspection covered several of nine shipments of reactor components for low level radioactive waste disposal. The licensee is using a cask provided by General Atomics to transport the components for disposal. The cask is designated FSV-1 (designed and used in Fort St. Vrain decommissioning) and it is a Type B shipping cask with Certificate of Conformance (CoC) No USA /9277. The licensee contracted with NUKEM to manage the loading of the cask and to assist the licensee's waste management group for the shipment of the waste. The shipment normally included:
13 Control Rod Blades Incore detectors 52 Stellite rollers i spud ends and other reactor parts i
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In order to determine the nuclides and activity of the above components, the licensee contracted with Waste Management Group (WMG) to characterize the above components. Information provided to WMG includes, but is not limited to, dose profiles of the above components, metallurgic analysis of the components and estimated time and conditions while the components were being irradiated within the reactor vesse The characterization is provided to the licensee to be used in the completion of waste l documents for the disposal of the waste which includes, but is not limited to, nuclides present, activities of each nuclide and characterization of the waste class. The licensee appeared to have adequately monitored the interaction between the above contractors to ensure compliance with NRC and DOT regulation l
I c. Conclusions The loading of a FSV shipping ca',k onto a transport carrier and subsequent shipment to Bamwell in South Carolina was <>bserved to be carried out as required, and with associated documentation and record keeping completed as required by procedure. No problems were identified with the activities surrounding the shipmen .0 Meeting Insoection " Exit" The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on September 21,1999. The licensee acknowledged the findings presented. The licensee did not identify any documents or processes reviewed by the inspectors as proprietary. This meeting concluded the NRC's continuous on site inspection program at Big Rock Point. The inspection program will now be conducted from Region Il .2 Manaaement Meetina The licensee presented the status of the Big Rock Restoration Project at a public meeting at Region lli on September 29,1999. No proprietary information was presented. A copy of the licensee's presentation handout is attached to this repor !
PARTIAL LIST OF PERSONS CONTACTED Licensee M. Bourassa, SFP Clean Out & Licensing Supervisor M. Lesinski, Radiation Protection and Environmental Services Manager (RP&ES)
R. McCaleb, Nuclear Performance Assessment, Site Lead (NPAD)
G. Petitjean, Design Basic Engineering Supervisor L. Potter, Maintenance Supervisor K. Powers, Site General Manager J. Rang, industry issues G. Rowell, Engineering Administrative Supervisor G. Szczotka, Manager, Nuclear Performance Assessment Department (NPAD)
W. Trubilowicz, Cost, Scheduling & Purchasing Manager M. VanAlst, Security Manager 1 R. Wills, Radwaste Superintendent G. Withrow, Engineering, Operations & Licensing Manager E. Zienert, Human Resources , Training & Administrative Department Manager Attendees at Public Meeting Ken Powers Licensee Gregory Withraw Licensee William Trubiowicz Licensee Mark Le:Eski Licensee Harry Linsinski Licensee Gregory Szczotka Licensee Rob Mc Caleb Licensee Gerald Slade Licensee Dennis Demoss Licensee Steve Raupp Licensee Bart Slimp Licensee Jim Thuot Licensee Cynthia Pederson NRC Bruce Jorgensen NRC Paul Harris NRC Ross Landsman NRC Roy Leemon NRC William Snell NRC There were no members of the public present at the meeting.
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INSPECTION PROCEDURES USED
' IP 36801: Organization, Management, and Cost Controls at Permanently Shut Down Reactors IP 37801: Safety Review, Design Changes, and Modifications at Permanently Shut Down Reactors .
IP 40801: Self-Assessment, Auditing, Corrective Action i
IP 42700: Review of Modifications and Procedures IP 60801: Spent Fuel Pool Safety at Permanently Shut Down Reactors IP 62801: Maintenance rend Surveillance at Permanently Shut Down Reactors IP 71707: Operational Safety Verification IP 71801: Decommissioning Per' formance and Status Review at Permanently Shut Down Reactors
' iP 81700 Safeguards Program implementation IP 83750: Occupational Radiation Exposure IP 84750: - Radwaste Treatment, Emuent and Environmental Monitoring IP86740: Inspection of Transportation Activities IP 86750: Solid Radweste Management and Transportation of Radioactive Materials ITEMS OPENED, CLOSED, AND DISCUSSED Ooened None-Closed None Discussed None i
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l UST OF ACRONYMS USED ALARA As-Low-As-Reasonably-Achievable BNFL British Nuclear Fuels Limited CARB Corrective Action Review Board CoC Certificate of Compliance CFR Code of Federal Regulations CRB Control Rod Blade DEP Defueled Emergency Plan DOP Defueled Operating Procedure DOT Department of Transportation DTS Defueled Technical Specifications FHSR Final Hazards Summary Report
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FSV Fort Saint Vrain (Shipping Cask)
ISSSF Important to Safe Storage of Spent Fuel i LSA Low specific activity MIS Maintenance Information System MRB Management Review Board NPAD Nuclear Performance Assessment Department NRC Nuclear Regulatory Commission OCA Owner Controlled Area PSDAR Post-Shutdown Decommissioning Activities Report QA Quality Assurance PA Protected Area RP Radiation Protection RWP Radiation Work Permit PSP Physical Security Plan SFP Spent Fuel Pool SRC Safety Review Committee SSCs Systems, Structures and Components TS Technica! Specification URSQ Unreviewed Safety Question WMG Waste Management Group LICENSEE DOCUMENTS REVIEWED Licensee documents reviewed and utilized during the course of this inspection are specifically identified in the ' Report Details" abov l
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ATTACHMENT BIG ROCK POINT RESTORATION PROJECT NRC - STATUS MEETING AGENDA September 29,1999 OVERVIEW (Ken Powers)
- 9:30 - 9:50-COST & SCHEDULE STATUS _(Bill Trubilowicz)
9:50-10:05 RADIATION PROTECTION & ENVIRONMENTAL (Mark Lesinski)
10:05-10:20
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ENGINEERING & OPERATIONS (Greg Withrow)
10:20-10:35 DISMANTLEMENT, MAINTENANCE & PLANNING (Harry Linsinbigler)
10:35-10:50 MAJOR COMPONENT REMOVAL (Gerry Slade)
-10:50 -11:00 RESTORATION OVERSIGHT (G.B. Szczotka / Rob McCaleb)
11:00 -11:15 FUTURE COMMUNICATIONS (Ken Powers)
11:15 -11:30 l
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RISKS TO A SUCCESSFUL DECOMMISSIONING
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. Hurting People, Spilling or Dropping Things
. Believing That The Regulatory Period is Over i
. Having an Unmotivated Workforce
. Lacking Project Wide Teamwork
. Having Inadequate Planning
. Running Out of Money
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COST & SCHEDULE STATUS
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COST STATUS ($ IN MILLIONS)
Budget Actual Variance Year to Date (August) $3 $3 ($2.5)
j Project To Date $11 $10 ($2.5)
Management Reserve Utilized $ Remaining $4 STAFFING {
Peak Current Change l (March '98) (September) )
i Consumers 209 112 (97)
Trades 93 59 (34)
Staff Support 167 119 (48)
Total 469 290 (179)
DEPARTMENTAL Cost, Scheduling & Purchasing 51 Dismantlement, Maintenance & Planning 95 Engineering, Operations & Licensing 51 i General Manager 10 ,
Human Resources, Training & Administrative 17 l Nuclear Performance Assessment 2 Radiation Protection & Environmental 64 l
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% OF COST $ YOE (M) COST CATEGORY RISK ACTUAL COSTS 5 PERIOD A ZERO 5 PERIOD B ZERO j 10 TOTAL ACTUAL COST THRU JULY 1999 4 REMAINING CONTINGENCY LOW TO GO COSTS 36 % 7 STAFFING LOW 18% 3 MAJOR COMPONENT REMOVAL LOW 11 % 2 LOW LEVEL RADWASTE DISPOSAL MEDIUM 9%- 1 DRY FUEL STORAGE MEDIUM - HIGH 5% 1 PROJECTS / SYSTEM DISMANTLEMENT MEDIUM - LOW 2% RPV BURIAL MEDIUM 2% SPENT FUEL POOL CLEAN OUT MEDIUM - HIGH 17% 3 MISCELLANEOUS LOW HEAW EQUIPMENT RENTAL INSURANCE EMPLOYEE TRANSITION ROSTS EES - NRC, EMERGENCY 3'5 PLANNING, ET .9 TOOLS / SUPPLIES PROPERTY TAXES 1 OTHER OVERHEADS / MISCELLANEOUS 3 SUBTOTAL l
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SCHEDULE STATUS
. 520 Level II Activity Finishes Targeted 1997 - 1999 425 Completed through Mid-September (82%)
61 Projected Ahead (12%)
22 Projected Behind (4%)
. Asbestos Abatement Sequencing (2)
. Electrical & Air Compressor Room
. Regen / Non-Regen Heat Exchanger Room
. Late Construction Starts (3)
. Recirc Pump Room
. Filter Room
. Pipe Tunnel Door
. Dwp Development (17)
. Spent Fuel Storage Area .
. Service Building - 3rd Floor I
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DISMANTLEMENT STATUS MATRIX DWP/
SCHEDULE PROJECT / IN READY TO IN PHYSICALLY PACKAGE PACKAGE DISMANTLEMENT PLANNING WORK EVALUATION PROCESS COMPLETE CLOSED CODE
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TECHNICAL BUDGET SCHEDULE O ' '
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0B04 OUT BUILDINGS CONDENSATE & DEMire OB08A TANKS 0B12 SECURITY BUILDING 0813 WASTE HOLO TANK 0B14 RADWASTE DUILDING OB15A SUBSTATION _> 8j 53% ' ".'y 100 %
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RADIATION PROTECTION & ENVIRONMENTAL
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l . Enhancement Plan Status
. History l . Original Plans
. Procedure Upgrade
. Remaining Plans
. Self Assessment Program
. Reassess 3/2000
. Self Assessment Program
. Radworker Practices
. Ongoing "Back to Basics"
. Safety Lunches, Safety Days, Coaching
. Accountability i
. ALARA Performance 1998 Performance i 1999 Status
. Overall Goal
. Solid Materials Release Program
. Site Characterization
. Current Status
. Partial Release
. Future Plans l
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. Radwaste Volume Shipped 81,000 Curies 2 Million Pounds
. Volume Reduction 20 to 1
. PCB Painted Material Disposition 400,000 LB Stored Currently
. Contractor Storage Permit Pending 1,500,000 LB Total
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. Barnwell Status
. Current Work
. Estimated Impact
. Ongoing Initiatives
. Complacency / Attention to Detail
. Attrition
. Retraining
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ENGINEERING & OPERATIONS
COMMUNITY INVOLVEMENT
. Citizens Advisory Board
. CMS Energy Community Service Agencies Funding i
. Sponsored Public Events INDUSTRY LEADERSHIP
. Executive Committee of ANS DD&R Division
. Oversight Committee - Connecticut & Maine Yankee
. EPRI Decommissioning Task Force
. ANS Executive Conference (Highest Turnout)
. EPRI - NEl Hazardous Materials Conference
. Strong Support & Participation in Industry Meetings &
Conferences
,
SPENT FUEL STORAGE
. Defueled Technical Specifications
. Temperature
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. Chemistry
. Fuel Storage
. Make Up Flow
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. TriNuc Filter
. Temperature & Level Monitoring '
. Direct Readout, Recorded & Alarms e increased Physical inspection on Perameters
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. New Heat Exchanger Modification !
!
. Quarterly Decay Heat Load Test
. Tighter Control of Spent Fuel Pool Material
. Video Tape Inspection of Each Fuel Bundle
ENGINEERING & OPERATIONS ACCOMPLISHMENTS
. Revised UFHSR
. Revised Technical Specifications
. Revised Emergency Plan
- Revised Security Plan
. Revised Q-List & Drawings
. Certified Fuel Handlers. Qualifications & Shift Manning
. Spent Fuel Pool Cleanout Project
. Hazard Reduction Modification Projects
ENGINEERING & OPERATIONS ONGOING INITIATIVES
. Spent Fuel Pool Cleanout Lessons
- Pool Syphon Event
. FSV Cask Lid Sealing Problems e Lowering Control Blade Improperly e Neutron Source Pins Mistaken as Tie Rods
- Reactor Cavity Shielding Void
. Waste Water Processing
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. Continually Changing Conditions for Operations
- Keeping Fire Equipment & Pathways Open 3 Procedure Changes for Added and Removed Equipment
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l DISMANTLEMENT, MAINTENANCE & PLANNING 2 I
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DISMANTLEMENT, MAINTENANCE & PLANNING ,
ACCOMPLISHMENTS
. Integration of Utility Workers & Building Trades
. Two Years of Decommissioning Without a Lost Time Accident (For a Total of 22 Years)
. Decommissioning Work Package Process
. Major Modifications
. Decommissioing Power
. Spent Fuel Pool Cooling I
. Alternate Liquid Radwaste
. HEPA Filter
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. Access Control
. Hazard Abatement
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MAJOR COMPONENT REMOVAL ACTIVITIES AND ISSUES FOR 2000 Activities issues Containment Access Opening Containment Closure Alternate Shutdown Building None Large Component Movement Fuel in Spent Fuel Pool
. Poison Tank
. Emergency Condenser
. Steam Drum Reactor Vessel Shipping NRC Review Resources .
Container Design
___1
RESTORATION OVERSIGHT
'
I NPAD - OVERSIGHT !
. Onsite Nuclear Performance Assessment Staff
. Fill RP Assessor Vacancy l
. Perform Daily Assessments
. Conduct Employee Concerns Program i
. Perform Bench Marking at Other Decommissioing Sites
. Off-Site Resources to Augment NPAD Site Assessment
. Routine Utilization of Palisades NPAD Assessors
. Periodic Multi-Disciplined External Audits
. Special Assessmentrs by Outside Contractors
. Supplier Evaluations & Audits
. Independent Safety Review Group
- Routine Review of Procedures & Modifications
. Periodic Review Meetings
. Proactive Review of Critical Evolutions i
I
. Restoration Safety Review Committee '
. On-Going Review of Materials
. Monthly Conference Calls
. Site Meetings 1
'
28 a
FUTURE ROUTINE COMMUNICATIONS
- Conference Calls ?
- Written Status Reports ?
- Face to Face Meetings ?
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29
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