IR 05000029/1993007
| ML20059D648 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 12/28/1993 |
| From: | Bores R, Joseph Nick NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20059D632 | List: |
| References | |
| 50-029-93-07, 50-29-93-7, NUDOCS 9401100028 | |
| Download: ML20059D648 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION l
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REGION I '
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Report No.
50-29/93-07
Docket No.
50-29
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License No.
DPR-03 Category _C.
l Licensee:
Ynnkee Atnmic heric Comnany 580 Main Street
Anitnn. Mmeenchneette 01740-1398
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Facility Name:
Yankee Nuctaar Power Station Inspection At:
Rowe. Massachusetts
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t Inspection Period:
August 26.1993 through November 18. 1993 i
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12[/7/f2 Inspector:
J. Ni$, Radiation Specialist Date j
Facilities Radiation Protection Section -
12AFM3 Approved by:
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i.'Borel/ Chief Date.
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Facilities Radiation Protection Section i
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t reas Insnected:
Posting of radiological areas and other controls observed during facility tours,-
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organization and staffing, the program for maintaining exposures as low as reasonably achievable
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(ALARA), radiological information available to workers, and radiological controls for the asbestos l
abatement project in the vapor containment building.
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Results: Good performance was noted in most areas throughout the inspection. One violation of NRC requirements was identified involving the control of high radiation areas.
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9401100028 931229 l
PDR ADOCK 05000029
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DETA1IS 1.0 Individuals Contacted 1.1 Yankee Atomic Electric Company
- G. Babineau, Radiation Protection and Chemistry Manager J. Bourassa, Quality Assurance Audit Group D. Calsyn, Quality Assurance Supervisor W. Cox, ALARA Specialist M. Desilets, Radiation Protection Engineer T. Hend:rson, Assistant Plant Superintendent S. Litenfield, Health and Safety Supervisor G. Maret, Site Manager - Component Removal Project N. St. Laurent, Plant Superintendent M. Vandale, Radiation Protection Engineer 1.2 NRC Personnel P. Harris, Resident Inspector (Vermont Yankee Plant)
- Denotes those individuals participating in the exit briefing via telephone 2.0 Purpose The purpose of this unannounced inspection was to assess the licensee's implementation of the radiological controls program during the post operational period. Program elements reviewed included posting of radiologically controlled areas and other radiological controls observed during facility tours, organization and staffing, the licensee's progmm for maintaining exposures as low as reasonably achievable (ALARA), radiological information available to workers, and radiological controls for the asbestos abatement project in the vapor containment building.
3.0 Facility Tours The inspector toured many areas of the facility, including the vapor containment building,
. radioactive waste processing and packaging areas, the spent fuel pool building, and the auxiliary building. Postings were generally informative and properly placed in accordance with 10 CFR 20.203. Some minor discrepancies were noted and brought to the attention of j
l licensee representatives. The licensee took prompt corrective action and improvements were noted the next day. Imcked high radiation areas were secured as per Technical Specification requirements.
Most high radiation areas were barricaded to prevent inadvertent entry; however, several ladders that provided access to the steam generator cubicles from the top platform did not have a barrier. The platforms had a hatch door that opened to allow access via a ladder to the lower areas in the steam generator cubicles. The ladders protruded up through the
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platform approximately four feet and were posted with a "high radiation area-caution" sign at the top of theladder. But the inspector observed that the hatch doors in three out of the four steam generator platforms were left open and the licensee did not provide any other barrier. This is an apparent violation of the licensee's Technical Specification that requires -
a barricade for all high radiation areas (50-29/93-07-01).
The licensee responded in an effective and timely manner to the inspector's finding concerning the lack of a barrier to restrict inadvertent entry. Within one workday, the licensee had moved the posting to the points of entry to the steam generator platforms and had provided adequate barriers to prevent inadvertent entry to the steam generator platforms and cubicles. In addition, the licensee issued a memo to all technicians concerning the correct method for providing a barrier when a ladder is used to access a high radiation area.
Long term corrective actions had not been discussed with the inspector. During later decontamination work, the licensee removed the steam generator platforms to facilitate removal of the steam generators and there was no longer an access-way through the top of
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the steam generator cubicles.
Good housekeeping was observed by the inspector in most areas of the facility. The licensee -
had sent a large amount of bagged, dry active waste (DAW) that was noted in a previous inspection (NRC Inspection Report 50-29/93-05) to a vendor for processing and disposal.
The inspector observed that there were still many contaminated items and a significant volume of radioactive waste that required ultimate disposal. A licensee wyistative stated -
that disposal of the materials was contingent upon budget allowances and radioactive waste shipment priorities. The licensee had no documented plan or schedule for shipment of the remaining radioactive waste.
The warehouse used to stage radioactive wastes was converted to a preparation area for the steam generators prior to shipment. Therefore, other areas were used to stage radioactive waste for eventual shipping and disposal.
4.0 Organ 17mtion and Staffing The licensee's permanent health physics staff had not changed significantly since the last inspection. The licensee's health physics staff had been augmented with contractor personnel to support the component removal work as documented in a previous NRC Inspection Report (50-29/93-04). The staffm' g level was appropriate for the work scope.
5.0 Rndinlorical Information Available to Plant Workers The licensee used general employee training, including radiation worker training, and speinli=1 training (i.e., health physics technician training) to educate workers about the radiological hazards present in the work-place. Radiation Work Permits (RWPs) and current radiological survey information were posted at the entrance to the Radiologically Controlled Area (RCA). Radiological area workers were required to read these documents to obtain specific information concerning dose rates in the immediate work area, special job requirements, respiratory protection, and protective clothing requirement. _ _ - _ _ _ _ _ _ _ _ _
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The licensee had implemented less restrictive security requirements as discussed in a previous inspection report (NRC Inspection Report 50-29/93-05). The inspector had expressed a concern that a visitor could gain access to the RCA without any knowledge of the radiation hazards. The RCA was contained in some areas with a fence approximately four feet in height with unlocked gates. Although the gates and fence were posted with warning signs, the radiological hazard was not defined. The licensee allowed unescorted visitors access to other areas of the site, excluding the RCA, without orientation or training concerning the radiological hazards on the site. The policy was reviewed by the licensee to ensure that instructions to workers wem commensurate with the potential radiological hazards M the restricted area. As a result of the review, the licensee implemented a brief orientation for visitors by the security personnel.
The orientation was given to visitors at the guardhouse before the visitors entered the site. The inspector reviewed the orientation material and found the information appropriate for the potential radiological hazard to unescorted visitors on the site.
6.0 Asbestos Abatement Project
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The licensee had started an asbestes abatement project in the vapor containment building around the beginning of May 1993. The @ included the removal of asbestos insulation on the four steam generators and the preprhr. Approximately eighty contractor personnel were employed to perform this insulation removal work. The licensee had estimated 152 person-rem for the total exposure to the workers involved in shielding placement, scaffold erection and dismantling, and asbestos insulation removal.
The actual dose accumulated by workers on the asbestos abatement project was approximately 73 person-rem, including the scaffold erection and removal for the project.
The licensee attributed the difference between the estimated and actual total exposure to the good condition of the asbestos insulation, lower than expected dose rates, and experienced workers.
7.0 Component Removal Proiect 7.1 Steam Generator Removal The licensee had removed the four steam generators and the pressurizer from the vapor containment building during the~ time period covered in this inspection. The inspector observed the removal of the first steam generator on September 23, 1993. The steam generator (#4) was raised from the steam generator cubicle by the containment polar crane.
The steam generator travelled over the reactor cavity and was lowered to the outside through the containment equipment hatch. As the steam generator was lowered, energy absorbers (impact limiters) were located on the ground beneath the generator in the event of a drop.
When the generator was low enough to the ground, a skid with a cradle was placed under the generator to set the generator down. At this point, the steam generator was supported in the equipment hatch with wooden blocks and the cables from the polar crane were detached from the generator's lifting trunnions. A lifting rig was placed between the generator and the polar crane cables to acilitate laying the steam generator on its side. After
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the blocks were removed, the generator was lowered and the skid was pulled away slowly to set the generator on its side.
Radiological controls and plans were well implemented. A very large radiation area was set up on the ground around the space into which the generator was lowered. Within this space
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was a smaller, concentric high radiation area surrounding the generator, These controls limited the number of pesple in the area and minimized collective radiation exposure from the generator. Dose rates were not as high as initially projected by the licensee, and dose i
rates at the pre-established, posted boundary for the high radiation area were between 10 and
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30 millirem per hour. Many licen::ee health physics technicians and supervisory personnel were present during all phases of the lift process. Dose rates and con' amination surveys
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were performed during the procedure. ALARA planning included specially designed shields for the generators on the ground, and remote monitoring through closed circuit television.
Industrial safety and planning were also evident. Temporary railings were installed on building roofs being used as observation areas. The inspector observed that all personnel working near openings with a large drop were weari.g a safety harness tied to a permanent structure. No personnel were allowed directly under the steam generator when it was in transit. The inspector observed personnel wearing sfety equipment such as eye protection and hard-hats.
Overall, the first steam generator lift operation went very well. The entire operation lasted approximately thirteen hours from the start of the lift until the steam generator was resting on the skid. The steam generator was transferred from the skid to a hydraulic trailer. The trailer was then hauled to the warehouse where the preparations for shipping were performed.
7.2 Steam Generator Preparation Two areas were set up in the warehouse, each area for preparing one steam generator for
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shipment. Both areas were lined with concrete blocks taken from the vapor containment generator bays for radiation shielding. Containment tents were purchased and erected around the steam generators to facilitate control of radioactive contamination. The steam generators were decontaminated, fitted with radiation shielding material, filled with a low density concrete material for additional radiation shielding and stability, and sealed with metal covers welded into place. Impact limiters were placed on both ends of the steam generators for final preparation before shipment.
7.3 Steam Generator Shioment After the steam generators were prepared for shipment, they were transported to a local rail line via a truck and trailer designed for heavy loads.- The licensee and its contractor i
maintained very good quality controls over the truck transport. Appropriate controls included very slow transit speed (approximately 5 miles per hour); a dry run using the actual hauling vehicles and a heavy non-radiological cargo before the first steam generator shipment; and accompaniment of the shipment by health physics personnel, other licensee
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l representatives, and State Police vehicles. The inspectors observed the shipments and j
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reviewed the shipping paperwork. All dose rates and contamination levels were within NRC/ DOT regulations. The packages had been sealed and welded as mquired and the
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impact limiters were attached. The vehicle was placarded as required by regulations.
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One generator was transported to the rail line each day for two consecutive days on -
j November 16 and 17,1993. At the rail line, approximately 6 mile = from the plant at the-
- 1 Hoosac Tunnel, the steam generators were loaded on a train car fa rail shipment to the radioactive waste disposal site near Barnwell, South Carolina. The t ' o fers from the trailer
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to the rail cars were done with lifting jacks. A crane was used to,
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supports, but the came was not used to lift the steam generators. A dedicated rail shipment -
.l containing two steau generators was sent on November 17,1993. The train cars included '
two engines, an idler car, and the two steam generators. The inspectors verified that a
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health physics technician was accompanying the rail shipment and the required placards were
attached to the rail cars.
i 8.0 ALARA Program
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As of November 18,1993, the total radiation exposure to workers performing the component
.l removal work was approximately 130 person-rem._ The total dose accumulated for work at
Yankee Rowe by workers in 1993 was approximately 160 person-rem. This total includes -
.l the dose to workers erecting scaffolding and constructing enclosures around the steam
generators, removing asbestos insulation, removing the reactor components (steam generators.
and pressurizer), modifying the shield tank cavity, segmenting the reactor vessel internals,
and preparing reactor components for shipment.
l The highest whole body dose assigned to an individual for the third calendar quarter of 1993
was approximately 915 millirem. This exposere is well below the whole body exposure
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allowed by NRC regulations of 3,000 millirem per calendar quarter. There were no significant skin of whole body, extremity, or internal dose assignments for the third quarter
of 1993.
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ALARA post-job reviews were conducted on jobs with significant personnel exposure
estimates. These jobs included the asbestos abatement scaffolding project and the asbestos j
removal. Personnel radiation exposure was considered as thejob planning progressed. Pre-
job briefings were held forjobs with expected significant personnel exposure.. The inspector -
reviewed the material for the pre-job brief for the steam generator removal work. The i
presentation included safety issues, contamination control, and ALARA issues.
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The licensee used many controls to maintain personnel radiation dose as low as reasonably
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achievable.
Closed circuit ' television cameras were installed in areas of the vapor
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containment so that work could be monitored from a lower radiation dose area. The licensee l
had monitors in the Technical Support Center (TSC) adjacent to the control room.
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radiation protection group also provided job tracking reports to site workers that monitored accumulation of radiation dose by job and type of worker, j
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9.0 Exit Meetine
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A meeting was held with a licensee representative via telephone at the end of the inspection
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period on November 24,1993. The purpose and scope of the inspection were reviewed and the findings of the inspection were discussed. The licensee representative acknowledged the inspector's findings.
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