ML20138M560
| ML20138M560 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/08/1985 |
| From: | Hosey C, Revsin B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20138M553 | List: |
| References | |
| 50-269-85-30, 50-270-85-30, 50-287-85-30, NUDOCS 8511040099 | |
| Download: ML20138M560 (6) | |
See also: IR 05000269/1985030
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UGelTED STATES
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OCT 16 1985
Report Nos.-
50-269/85-30, 50-270/85-30, and 50-287/85-30
Licensee: Duke Power Company
422 South Church Street
Charlotte, NC 28242
Docket Nos. 50-269, 50-270, and 50-287
License Nos.
Facility Name: Oconee Nuclear Station
Inspection Conducted:
September 16 - 20, 1985
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Inspector:
B./ K. Riv si n'
Date Signed
Accompanying Personnel:
M. Poston-Brown
Approved by:
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C.M.Hosey,SectyonChief
Date Signed
Division of Radiation safety and Safeguards
SUMMARY
Scope: This routine, unannounced inspection entailed 38 inspector-hours onsite
during regular hours in the area of radiation protection including external
exposure control; internal exposure control; training and qualifications of
personnel; radioactive materials contrcl, posting and labeling; and program for
maintaining exposures as low as reasonably achievable (ALARA).
Results: One violation - failure to label containers of radioactive material.
8511040099 851016
ADOCK 05000269
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REPORT DETAILS
1.
Persons Contacted
Licensee Employees
- M. S. Tuckman, Station Manager
- R. T. Bond, Compliance Engineer
- G. T. Powell, Health Physics, General Office
- S. A. Coy, Associate Health Physicist
- C. T. Yongue, Station Health Physicist
- T.
S. Barr, Superintendent of Technical Services
C. L. Harlin, Health-Physics Coordinator
T. L. Cherry, ALARA Supervisor
D. Austin, Training and Safety Coordinator
T. E. Carroll, Health Physics Supervisor
M. L. Lynch, Health Physics Supervisor
D. R. White, Health Physics Supervisor
NRC Resident Inspectors
J . Bryant, Senior Resident Inspector
K. Sasser, Resident Inspector
L. King, Resident Inspector
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on September 20, 1985,
with those persons indicated in paragraph 1 above. An apparent violation
for failure to label containers of radioactive material (paragraph Sa) was
discussed in detail.
Licensee management took no exceptions. The licensee
did not identify as proprietary any of the materials provided to or reviewed
by the inspector during this investigation.
3.
Licensee Action on Previous Enforcement Matters
This subject was not addressed in the inspection.
4.
Training and Qualifications (83723)
a.
Radiation Protection Technician Training and Qualification
The licensee was required by Technical Specification (T.S.) 6.1.1.4 to
qualify health physics (HP) technicians in accordance with Section 4 of
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ANSI /ANS-3.1-1978. The inspector discussed the training and qualifica-
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tion program with the HP Technical Associate in charge of implementa-
tion of the HP technician training program. The course outline for HP
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training was reviewed and selected records of HP technicians were
examined to verify that all mandatory classroom and on-the-job training
had been completed. A licensee representative stated that both the HP
and chemistry technician training programs would be submitted for
accreditation to the Institute for Nuclear Power Operations (INP0) by
December 31, 1985.
T.S.
6.1.1.5 specified that retraining and replacement of station
personnel shall be in accordance with Section 5.5 of ANSI /ANS-3.1-1978.
The inspector discussed the training / replacement program with the HP
Technical Associate and with the Training and Safety Coordinator.
b.
Basic Radiation Protection Training
The licensee was required by 10 CFR 19.12 to provide basic radiation
safety training for workers with Regulatory Guides 8.27, 8.29 and 8.13
providing an outline of topics that should be included in such
training.
The inspector discussed the initial general employee
radiation protection training (GET) with the Training and Safety
Coordinator and reviewed course outlines and lesson plans that
described the GET program.
For annual GET retraining, the licensee
stated that workers may opt to take a by pass examination which
includes an update briefing covering changes that have occurred at the
facility as well as operating problems at other facilities.
The
inspector discussed the training tracking system with the licensee and
found adequate controls in place to assure that radiation worker
training was up-to-date.
Selected records of plant radiation workers
and outage radiation workers were examined to verify that their GET
training was current.
c.
Respiratory Protection Training
The licensee was required by 10 CFR 20.103 to establish a qualification
program for workers who wear respiratory protection equipment.
Elements of the qualification program outlined in 10 CFR 20.103 were
delineated in NUREG-0041.
The inspector discussed the respiratory
protection training with the Training and Safety Coordinator and by
review of records, verified that selected workers had completed the
training.
No violations or deviations were identified.
5.
Centrol of Radioactive Materials and Contamination, Surveys and Monitoring
(83526)
The inspector observed the posting and labeling of Radioactive Materials
Areas, Radiation Areas and High Radiation Areas during tours of the
Auxiliary Building, Unit 3 Reactor Building, Turbine Building, Unit 3 Spent
Fuel Building, Warehouse No. 5 and other areas where radioactive materials
were stored within the protected area.
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a.
10 CFR 20.203(f) required that each container of licensed material bear
a durable, clearly visible label which bears the radiation caution
symbol and the words " Caution" or " Danger, Radioactive Materials" and
sufficient information to permit individuals to avoid or minimize
exposures.
The inspector noted that the area adjacent to the Unit 3 loading dock
was used for storage of radioactive materials.
The area itself was
fenced and permitted entry through two access points, a locked door for
personnel entry and a gate for vehicle access. Most of the containers
were wrapped in yellow herculite secured by duct tape. A licensee
representative informed the inspector that the contair,ers were incore
casks used for storing used incore tubes.
The inspector noted that
three of the containers had no labels, four containers had labels that
were suf ficiently weathered to erase all markings and that three other
containers had labels that were barely legible.
A survey data sheet posted next to the personnel door indicated dose
rate on the bottom of one of the containers was 250 mR/ hour.
In
general, dose rates on the containers appeared to vary between
12-50 mR/hr. Dose rate on the containers indicated that they contained
greater than the quantity of radioactive material specified in
10 CFR,.20, Appendix C.
The inspector noted that housekeeping in the area was such that on
September 16, 1985, two security persons were observed exiting the area
using the containers of radioactive material to maintain their balance
as they exited through the debris.
Failure to label containers with a durable, clearly visible label
bearing the radiation caution symbol and the words " Caution" or
" Danger,
Radioactive
Material"
and which provided
sufficient
information to perrait individuals to avoid or minimize exposures was
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identified as an apparent violation of 10 CFR 20.203(f) (50-269, 270,
287/85-30-01).
b.
10 CFR 20.203 requires the posting and control of radiation areas and
During plant tours, the inspector examined radiation and contamination
survey results outside selected rooms and cubicles.
The inspector
performed independent radiation surveys of selected areas using NRC
equipment and compared them to licensee survey results. The inspector
reviewed surveys performed in conjunction with Radiation Work Permit
(RWP) Nos. 740, reactor coolant pump work, and 764, control rod drive
mechanism gasket replacement. Alpha, beta and gamma survey results
were reviewed. The inspector noted that selected locked high radiation
areas inside the Auxiliary Building were maintained as required by
No violations or deviations were identified.
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6.
External Occupational Dose Control and Personal Dosimetry (83724)
The licensee was required by 10 CFR 20.202, 20.201(b), 20.101, 20.102,
20.104, 20.402, 20.403, 20.405, 19.13, 20.407 and 20.408 to maintain
worker's radiation exposure below specified levels and to keep records of
and make reports of such exposures.
The inspector reviewed licensee
requirements for extremity monitoring and multibadging with licensee
representatives and reviewed the methodology used by the licensee to capture
this dose data by the computer system.
The daily computer printout of
cumulative radiation worker exposure was examined and it was determined that
no worker had exceeded any regulatory limit. Selected records of personnel
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working on RWP Nos. 740 and 764 were examined to verify completion of a Form
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NRC-4.
No violations or deviations were identified.
7.
Internal Exposure Control and Assessment (83725)
The licensee was required by 10 CFR 20.103, 20.201(b), 20.401, 20.403 and
20.405 to control uptakes of radioactive material, assess such uptakes and
keep records of and make reports of such uptakes.
During plant tours, the inspector observed the use of temporary ventilation
systems and respirators.
The inspector reviewed respiratory protection
training, respirator fit testing, and medical qualifications of selected
individuals involved in RWP Nos. 740 and 764.
The inspector reviewed the
MPC-hour records for the month of September 1985 and verified that no
personnel had exceeded 40 MPC-hours in one week. Air sample results for RWP
Nos. 740 and 764 were examined.
No violations or deviations were identified.
8.
Maintaining Occupational Doses ALARA (83728)
10 CFR 20.1(c) specified that licensees should implement programs to keep
worker's doses as low as reasonably achievable ( ALARA).
The recommended
elements of an ALARA program are contained in Regulatory Guide 8.8,
"Information Relevant to Ensuring that Occupational Radiation Exposure at
Nuclear Power Plants Will Be ALARA," and Regulatory Guide 8.10, " Operating
Philosophy for Maintaining Occupational Radiation Exposures ALARA."
The inspector c*ncussed the ALARA goals and objectives for 1985 with the
As of September 18, 1985, the actual collective
exposure was 1155 man-rem as measured by self-reading dosimeter (SRD). The
estimated exposure for the year was projected to be 1098 man-rem as measured
by thermoluminescent dosimeter (TLD). The licensee stated that the TLD dose
usually approvimated 85 percent of the SRD dose, but nonetheless, expected
to exceed their 1985 projection.
The reason specified for the overrun of
the 1985 goal was the unexpected maintenance and repair work performed on
one reactor coolant pump (RCP) and the control rod drive mechanism gasket
replacement during the Unit 3 refueling outage.
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The estimate of collective dose for the Unit 3 outage was 320 man-rem and as
of September 18, 1985, the actual man-rem were 313 as determined by SRD.
The estimate for the RCP work had been 40 man-rem, but as of September 18,
1985, the accumulated total had already reached 48 man-rem and the licensee
was still experiencing problems in the reassembly of the pump.
No violations or deviations were identified.
9.
IE Information Notices (92717)
The following IE Information Notices were reviewed to ensure receipt and
review by appropriate licensee management.
85-46,
Clarification of Several Aspects of Removable Radioactive Surface
Contamination Limits for Transport Packages
85-42,
Loose Phosphor In Panasonic 800 Series Badge Thermoluminescent
Dosimeter (TLD) Elements
85-57,
Lost Iridium-192 Source Resulting In the Death of Eight Persons in
Morocco
85-07,
Cpntaminated Radiography Source Elements
85-43,
Radiography Events at Power Reactors
85-06,
Contamination of Breathing Air Systems
84-56,
Respiration Users Notice for Certain 5-Minute Emergency Escape
Self-Contained Breathing Apparatus
85-48.
Respirator users Notice:
Defective Self-Contained Breathing
Apparatus Air Cylinders
85-60,
Defective
Negative-Pressure,
Air-Purifying,
Full
Facepiece
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Respirators
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