IR 05000331/1993008
| ML20044E074 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 05/13/1993 |
| From: | Kozak T, Snell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20044E068 | List: |
| References | |
| 50-331-93-08, 50-331-93-8, NUDOCS 9305210242 | |
| Download: ML20044E074 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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REGION III
l Report No. 50-331/93008(DRSS)
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Docket No. 50-331 License No. DPR-49
Licensee:
Iowa Electric Light and Power Company IE Towers P. O. Box 351 Cedar Rapids, IA 52406 Facility Name: Duane Arnold Energy Center Inspection At: Duane Arnold Site, Palo, Iowa i
Inspection Conducted: April 19 - 23, 1993
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LO:00l s E [
r/,3/g3 Inspector:
T. J. Kozak
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Senior Radiation Specialist Approved By:
( A9C RJ
.s/n/13 William G. Snell, Chief Date
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Radiological Controls Section 2
Inspection Summary Inspection on April 19 - 23. 1993 (Report No. 50-331/93008(DRSS))
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Areas Inspected:
Routine, announced inspection of the~ licensee's radiation'
protection program, including: licensee actions on previous inspection findings; refueling floor operations; control of radioactive material and contamination, surveying, and monitoring; and maintaining occupational
exposure as-low-as-reasonably achievable (ALARA) (Inspection Procedure (IP) 83750).
Results: The licensee's radiation protection program appears to be generally effective in controlling radiological work and in protecting the public health
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and safety. One non-cited violation was identified associated with an --
unauthorized entry by four individuals at the same time into a' posted high radiation area.
Excellent performance was noted during the Lead Test-Assemblies project.
Source term reduction plans remained on course for the summer refueling outage.
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9305210242'930513 r
DR ADOCK 05000332 PDR
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DETAILS 1.
Persons Contacted Licensee Staff
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- P. Bessette, Regulatory Communications Supervisor
- D. Blair, QA Assessment Supervisor
- D. Engelhardt, Security Superintendent
- P. Louis, Health Physics Foreman
- R. Hite, ALARA Coordinator
- J. Hogan, Decontamination Coordinator
- W. Holden, Training Supervisor - Radiation Protection
- R. Perry, ALARA. Specialist
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- K. Putnam, Technical Support Supervisor
- D. Robinson, Regulatory Communications
- D Schebler, Supervisor, Radioactive Waste
- W. Simmons, Maintenance Specialist
- M. Teply, Project Engineer - Refueling and Fuel Storage
- B.
Watts, Instructor - Radioactive Waste
- E. Wienola, QA Specialist i
- T. Wilkerson, Manager, Radiation Protection
- D. Wilson, Plant Superintendent
- J. Zahrt, Instructor - Health Physics
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Nuclear Reoulatory Commission C. Miller, Resident Inspector
- M. Parker, Senior Resident Inspector The inspector also interviewed other licensee personnel in various departments during the course of the inspection.
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- Denotes those present at the interim exit meeting on April 23, 1993.
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General l
This inspection was conducted to review aspects of the licensee's l
radiation protection program.
Included in this inspection was a
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followup of outstanding items in the radiation protection area. The
inspection included tours of radiologically controlled areas, the reactor building, and radwaste facilities, observations of licensee
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activities, a review of representative records, and discussions with licensee personnel, j
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Licensee Action on Previous Inspection Findinas (IP 83750)
(Closed) Violation (331/93001-01): Workers did not initiate a Fuel Storage Pool / Cask Pool Storage Permit or obtain approval prior to storing a stellite bearing from a control blade in the cask pool.
Further, the stellite bearing had contact dose rates greater than
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20,000 rads per hour which was above the level allowed to be stored in the cask pool. The inspector verified that all licensee commitments,
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which included staff training and procedure modifications, have been met. This item is closed.
4.
Refuelina Floor Operations (IP 837501 The inspector reviewed records and conducted interviews with appropriate personnel regarding the disassembly of Lead Test Fuel Assemblies (LTA)
in preparation for shipment offsite. Al indications were that the licensee's performance during this evolut ion was excellent.
Contingency l
actions were discussed for possible signi'icant increases in the general
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area radiation levels due to the disassembly of fuel pins in the fuel
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pool. Radiation protection technicians performed appropriate surveys during the project and promptly recognized that the fuel pool skimmer surge tank room became a high radiation area due to contamination release during fuel pin disassembly. Once the project was completed, an extensive decontamination of the fuel pool floor was conducted using an underwater vacuum which was effective in reducing general area radiation levels surrounding the pool. Decontamination of the skimmer surge tanks-was also planned but was delayed because the interior of the tanks were
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found to be in poor shape. At the time of the inspection, the licensee was developing a plan for maintenance on the tanks and subsequent
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decontamination.
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The inspector also reviewed preparations for the LTA shipment.
Verifications were made that both the licensee and the receiving party
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were authorized to use the shipping cask and to receive the material and that appropriate material classifications were made.
No problems were noted.
No violations or deviations were identified.
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5.
Control of Radioactive Materials and Contamination. Surveys. and i
Monitorino (IP 83750)
The inspector reviewed the licensee's program for control of radioactive
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materials and contamination, including: maintenance and calibration of contamination survey and monitoring equipment; adequacy of review and dissemination of survey data; and effectiveness of radioactive and i
contaminated material controls.
The inspector verified by a review of records, discussions with licensee personnel, and tours of operational areas that the supply, maintenance, and performance checks of survey monitoring instruments were adequate.
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Radiation surveys of areas were conducted in accordance with procedures and the results were routinely posted at the entrance to the respective
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area.
Decontamination workers routinely mop within the radiologically
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controlled area in an effort to maintain contamination levels low.
The
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skimmer surge tank room was one of the areas that was cleaned on a
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weekly basis. The licensee's policy was to not routinely clean in high
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radiation areas. As mentioned above, the skimmer surge tank room became
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a high radiation area during the LTA project. On March 17, 1993, four i
decontamination workers were scheduled to do routine cleaning on the j
fourth floor of the reactor building including the skimmer surge tank
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room. The workers were not specifically notified of the change in
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conditions in the room and did not notice the high radiation area sign on the door when they entered the room. They were not accompanied by a t
health physics technician nor did they have a dose rate meter or an j
alarming dosimeter.
Entry into a high radiation area without a dose i
rate meter, an alarming dosimeter, or a qualified health physics i
technician with a dose rate meter is a violation of Technical i
Specification 6.9.2.
Once the workers had entered the room, they
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noticed a change in the posting configuration within the room and
contacted health physics.
It was at this time that it was determined i
that an unauthorized entry into a high radiation area had been made.
The workers were in the room for only a few minutes and the dose they
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received was not measurable. Corrective actions to prevent recurrence
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of a similar event included administrative 1y locking high radiation
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areas to prevent unauthorized entries and improved briefings by the -
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decontamination foreman to better disseminate information about
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radiological conditions in the work areas assigned to his staff. The
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licensee plans to conduct a further review of the event to determine if j
additional correctivo actions need to be conducted to improve
radiological controls in the plant. The corrective actions taken prior to the end of the inspection appear to be acequate to prevent recurrence j
of a similar event.
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During this inspection, certain activities, as described above, appear l
- to be in violation of NRC requirements. However, the licensee
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identified this violation and it is not being cited because the criteria i
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specified in Section VII.B.1 of the " General Statement of Policy and
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Procedures for NRC Enforcement Actions," (Enforcement Policy,10 CFR
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Part 2, Appendix C) were satisfied.
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One non-cited violation was identified.
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6.
Maintainina Occupational Exposures ALARA (IP 83750)
The inspector reviewed the licensee's program for maintaining j
occupational exposures ALARA, including:
the source term reduction l
program; ALARA group staffing and qualification; changes in ALARA policy '
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and procedures, and their implementation; ALARA considerations for '
planned maintenance and refueling outages;-and worker awareness and involvement in the ALARA program.
Plans were still to remove the remaining high stellite containing I
control rod blades and to replace the internals ofithe feed regulating j
valves during the summer refueling outage. - Other source term reduction
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efforts included the continued use of-a hydrolazer'for decontamination-of drains and flushing of the spent fuel pool heat exchanger. The ALARA'
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group remained essentially the same as last reported.
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The licensee expressed concern about the dose that will be expended
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during this and next year on the motor operated valve (MOV) testing program. Several suggestions for a reduction in the testing scope have
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i been developeu and submitted to NRC for consideration. The inspector walked down many valves requiring testing and noted that several were i
located in high radiation areas. The development of this program and l
ALARA considerations for it will be reviewed during future inspections.
No violations or deviations were identified.
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Exit Meetino The inspector conducted an exit meeting with licensee representatives (denoted in Section 1) on April 23, 1993, to discuss the scope and findings of the inspection.
During this meeting, the inspector discussed the likely informational content of the inspection report with regard to documents or_ processes
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reviewed by the inspector during the inspection.
Licensee
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representatives did not identify any such documents or processes as i
proprietary. The inspector specifically discussed the following items:
The excellent radiological performance during the LTA project.
- The non-cited violation associated with the unauthorized entries l
into a posted high radiation area.
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