IR 05000528/1998016
| ML17313A587 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/17/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML17313A586 | List: |
| References | |
| 50-528-98-16, 50-529-98-16, 50-530-98-16, NUDOCS 9809220005 | |
| Download: ML17313A587 (16) | |
Text
ENCLOSURE U.S. NUCLEAR REGULATORYCOMMISSION
REGION IV
Docket Nos.:
License Nos.:
Report No.:
Licensee:
Facility:
Location:
Dates:
.Inspector:
Approved By:,
50-528 50-529 50-530 NPF-41 NPF-51 NPF-74 50-528/98-16 50-529/98-16 50-530/98-16 Arizona Public Service Company Palo Verde Nuclear Generating Station, Units 1, 2, and 3 5951 S. Wintersburg Road Tonopah, Arizona August 24-28, 1998 Larry Ricketson, P.E., Senior Radiation Specialist Plant Support Branch Blaine Murray, Chief, Plant Support Branch Division of Reactor Safety Attachment:
Supplemental Information 9809220005 9809i7 PDR ADOCK 05000528
I
e-2-EXECUTIVE SUMMARY Palo Verde Nuclear Generating Station, Units 1, 2, and 3 NRC Inspection Report 50-528/98-16; 50-529/98-16; 50-530/98-16 A routine, announced inspection was performed.
The inspection focused on exposure controls, controls of radioactive materials and contamination, surveying and monitoring, and quality assurance oversight of the radiation protection program.
Plant Su ort Radiation exposure controls were good.
Radiological areas were posted properly and high radiation areas were controlled effectively. High quality pre-job briefings on radiological hazards and dose reduction techniques were provided to radiation workers.
Radiation protection technicians provided good oversight of work activities (Section-R1.1).
Radiation survey information was current, and a good calibration program was maintained for radiation protection instruments.
Licensee controls worked effectively to keep radioactive material inside the radiological controlled area (Section R1.2).
A good audit of the radiation protection program was performed by the Nuclear Assurance Division. The audit team consisted of members that were well qualified. The scope and depth of review were appropriate, and the audit findings demonstrated that the audit was self-critical (Section R7).
f
-3-IV. Plant Su ort R1 Radiological Protection and Chemistry Controls R1.1 Ex osure Controls a.
Ins ection Sco e 83750 The inspector interviewed radiation protection personnel and reviewed the following:
Radiological controlled area access controls Control of high radiation areas High radiation area key control Radiological posting Radiation work permits and pre-job briefings Radiation protection job coverage Dosimetry use Condition reports b.
Observations and Findin s 83750 The licensee required all radiation workers entering the radiological controlled area to log into the access control computer and carry an alarming; electronic dosimeter.
The inspector observed radiation workers as they followed radiological controlled area access and egress procedures.
The inspector concluded that the access control system functioned properly and was easy for the radiation workers to use.
Radiation protection personnel were prompt to respond to questions or occasional problems experienced by radiation workers.
During tours of the radiological controlled area, the inspector observed that high radiation areas were properly controlled. Condition reports indicated that high radiation area controls had not presented a problem during the last 2 years.
The inspector's independent radiological measurements confirmed that radiological areas were correctly posted.
The inspector confirmed that high and very high radiation area keys were inventoried as required and radiation protection personnel accounted for all keys.
'he inspector attended pre-job briefings conducted before a containment building entry and before the movement of a container of high activity resin. During both briefings, radiation protection personnel provided proper information to inform the work groups of radiological hazards and to enable the workers to protect against unnecessary radiation doses.
Discussions between radiation protection personnel and members of the work groups were open and orderly.
The inspector observed radiatio'n protection oversight of work activities within the radiological controlled area and determined that the radiation protection technicians
-4-provided proper instruction and assistance to radiation workers to minimize radiation exposure All radiation workers observed within the radiological controlled area wore dosimetry devices appropriately.
Thermoluminescent dosimeters were processed by the licensee.
The dosimetry processing program was being evaluated by the National Voluntary Laboratory Accreditation Program at the time of the inspection.
c.
Conclusions Radiation exposure controls were good.
Radiological areas were posted properly, and high radiation areas were controlled effectively. High quality pre-job briefings on radiological hazards, and dose reduction techniques were provided to radiation workers.
Radiation protection technicians provided good oversight of work activities.
R1.2 Control of Radioactive Material and Contamination Surve in and Monitorin a.
Ins ection Sco e 83750 The inspector interviewed radiation protection personnel and reviewed the following:
Radioactive contamination controls.
Radioactive source accountability Personnel contamination events Radiological survey records Portable survey instrument calibration Personnel contamination monitors and tool monitor calibration Alarming dosimeters/pocket ion chambers calibration Whole-body counter calibration b.
Observations and Findin s The inspector observed radiation work practices in contaminated areas and identified no problems.
The inspector also observed the release of items from the radiological controlled area and confirmed that radiological surveys were performed properly.
The inspector randomly selected source identification numbers lrom the licensee's source inventory and, with the aid of source custodians from different site organizations, confirmed the radioactive sources were stored as indicated on the inventory.
The inspector randomly reviewed radiological survey records and noted the records were complete and easy to understand.
The inspector reviewed selected examples of air sampling data and confirmed the accuracy of airborne radioactivity calculations performed by radiation protection technicians.
The radiation protection organization was responsible for the calibration of portable radiation detection instruments, small article monitors, personnel contamination
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-5-monitors, and portable air samplers.
The inspector obtained portable radiation detection instrument identification numbers at random from the licensee's radiation survey records and checked the calibration dates of the instruments.
The inspector determined that all radiation survey instruments selected were within the allowable calibration interval at the time of use.
The inspector visited the licensee's portable instrument calibration facility and noted it was as described in the licensee's Final Safety Analysis Report.
Through observation and personnel interviews, the inspector determined the licensee had an adequate supply of operable radiation detection instruments to meet the commitments in the Final Safety Analysis Report.
The licensee maintained three whole-body counters.
The inspector reviewed records of the two most recent calibrations for each counter and confirmed that all whole-body counters were calibiated annually, as required by the licensee procedures.
The inspector reviewed personnel contamination event reports and noted the type and location of the contamination involved. For the examples in which there existed the possibility of internal radiation dose, the inspector confirmed that dose assessment had been performed properly through whole-body counting.
Conclusions Radiation survey information was current, and a good calibration program was maintained for radiation protection instruments.
Licensee controls worked effectively to keep radioactive material inside the radiological controlled area.
R7 Quality Assurance in Radiation Protection &Chemistry Activities The inspector reviewed the latest quality assurance audit of the radiation protection program.
b.
Observations and Findin s The inspector reviewed the audit team membership and noted the team included a technical specialist from the licensee's staff and a technical specialist from another nuclear power generation site.
In addition to the technical specia!'its, the team included three additional qualified auditors.
The audit scope included a large number of radiation protection program areas.
The inspector concluded that the depth of review was appropriate.
The audit team concluded that the radiation protection program effectively implemented regulatory and license requirements.
The audit identified areas of possible improvement, demonstrating the ability to be'self-critical. The areas of possible improvement were documented through the licensee's condition reporting system.
The radiation protection organization responded to the items promptly and implemented corrective actions or enhancements, as appropriat Conclusions A good audit of the radiation protection program was performed by the Nuclear Assurance Division. The audit team consisted of members that were well qualified. The scope and depth of review were appropriate, and the audit findings demonstrated the audit was self-critical.
V. Mana ement Meetin s X1 Exit Meeting Summary The inspector presented the inspection results to members of licensee management at an exit meeting on August 24, 1998. The licensee acknowledged the findings presented.
No proprietary information was identifie i
ATIACHIVIENT Su lemental Information PARTIALLIST OF PERSONS CONTACTED Licensee M. Fladager, Radioactive Material Control Section Leader J. Gaffney, Radiation Protection Operations Department Leader T. Gray, Radiation Engineering Section Leader R. Hazelwood, Nuclear Regulatory Affairs Engineer V. Huntsman, Radioactive Material Control Department Leader M. Lantz, Senior Health Physicist D. Leech, Nuclear Assurance Department Leader J. Levine, Senior Vice President, Nuclear M. Shea, Site Radiation Protection Director NRC J. Moorman, Senior Resident Inspector D. Carter, Resident Inspector INSPECTION PROCEDURES USED 83750 Occupational Radiation Exposure ITEMS OPENED CLOSED AND DISCUSSED
~Oened None Closed None Discussed None
-2-LIST OF DOCUMENTS REVIEWED Procedures 75DP-ORP02 75DP-9RP01 75RP-9EQ20 75RP-9MC01 75RP-9OP01 Radioactive Contamination Control, Revision 2 Radiation Exposure and Access Control, Revision
Calibration of Portable Gamma and Beta-Gamma Dose Rate Instruments, Revision 4 Control of Radiation Protection Instrumentation, Revision 9 Control of Locked High Radiation Areas and Very High Radiation Areas, Revision 12 75RP-ORP01 75RP-ORP02 75RP-9RP07 75RP-9RP09 75RP-9RP15 75RP-9RP26 Radiological Posting, Revision 16 Radiological Survey Schedule, Revision 3 Radiological Surveys, Revision 9 Release of Personnel, Vehicles, Equipment, and Material from the Radiological Controlled Area, Revision16 Control and Storage of Radioactive Material, Revision 11 Source Control, Revision 3
A.