ML15224A465
| ML15224A465 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/13/1981 |
| From: | Collins T, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A463 | List: |
| References | |
| 50-269-81-21, 50-270-81-21, 50-287-81-21, NUDOCS 8112070316 | |
| Download: ML15224A465 (3) | |
See also: IR 05000269/1981021
Text
- REGo
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION Il
101 MARIETTA ST., N.W., SUITE 3100
ATLANTA, GEORGIA 30303
Report No. 50-269/81-21, 50-270/81-21, and 50-287/81-21
Licensee:
Duke Power Company
422 South Church Street
Charlotte, NC
28242
Facility Name:
Oconee Nuclear Power Station
Docket Nos. 50-270, 50-270, and 50-287
License Nos. DPR-47, DPR-38, and DPR-55
Inspection at Oconee site near Seneca, South Carolina
Inspector:
/'
'
T. R. Collins
Date Signed
Approved by:___
C. Hos 'y,
Acting Section Chief
Date Signed
Techoe'cal Inspection Branch
Engineering and Technical Inspection Division
SUMMARY
Inspection on September 21-23, 1981
Areas Inspected
This special,
unannounced inspection involved 13.5 inspector-hours on site to
review the radiological aspects of a steam generator tube leak.
Results
In the area inspected, one deviation was identified (Exceeding the total radio
activity limit for the chemical treatment pond).
8112070316 811i1'
PDR ADOCK 05000269
REPORT DETAILS
1.
Persons Contacted
Licensee Employees
- J. E. Smith, Station Manager
- T. B. Owen, Superintendent of Technical Services
D. P. Rochester, Station Chemist
J. J. Sevic, Biologist
J. A. Long, Health Physics Support Functions Coordinator
- T. E. Cribbe, Licensing Engineer
- T. C. Matthews, Technical Specialist-Licensing
- H. Lowery, Operating Engineer
NRC Resident Inspector
- D. Myers
W. Orders
.
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on September 22,
1981 with
those persons indicated in paragraph 1 above. The inspector stated that
failure to meet the requirements of Duke Power Company, Oconee Nuclear Power
Station letter to the Nuclear Regulatory Commission,
dated December 27,
1978, Attachment 1, Chemical Treatment Pond radioactive material release
limits would result in a Notice of Deviation.
Plant management acknowledged
the inspector's comments and stated their intention was not to continue dis
charging radioactive material to the Chemical Treatment Pond #2 and their
prime responsibility was to protect public health and safety.
3.
Licensee Action on Previous Inspection Findings
Not inspected.
4.
Unresolved Items
Unresolved items were not identified during this inspection.
5. Radiological Aspects of Steam Generator Tube Leak of September 18, 1981
a.
On September 21 and 22, 1981,
an inspector reviewed health physics
records and interviewed personnel to ascertain the extent of radio
logical problems associated with the steam generator tube leak to the
turbine building (secondary system) and release of radioactivity to the
environment. Based on a review of the Auxiliary Building vent monitor
data R1A-43, R1A-44, and R1A-45, environmental air sample records,
2
environmental TLD results, and environmental liquid samples taken from
the plant surroundings indicated no regulatory limits were exceeded and
the dose to members of the general public were minimal. The inspector
determined that appropriate evaluations of release of radioactivity to
the environment as a result of the steam generator tube leak were made.
b.
Further review by the inspector revealed that the licensee did release
radioactivity to the Chemical Treatment Pond #2 in excess of the limits
specified in Duke Power Company, Oconee Nuclear Station, letter to the
Nuclear Regulatory Commission, dated December 27, 1978. Attachment 1
of the licensee's commitment states in part that radiaoctive material
in the Chemical Treatment Ponds (CTP)
shall be limited so that, for all
radionuclides identified, excluding noble gases, the sum of the ratios
of activity to the limits in 10 CFR 20, Appendix B, Table II,
Column 2,
shall not exceed 1.7 X 10s.
As a result of the steam generator tube
leak the licensee did discharge radioactive material to the Chemical
Treatment Pond #2 (CTP) in excess of 1.7 X 10s. The value of the ratio
summation of all radionuclides identified as of September 21, 1981 was
5.19 X 10'.
The major contributor to the CTP #2 was Iodine-131, 127,
745 microcuries.
C. As a result of the steam generator tube leak from approximately
1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on September 18,
1981,
to approximately 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on
September 20,
1981,
approximately 200,000 gallons of radioactive
secondary water was collected in units 1, 2, and 3 turbine building
sumps and basements. Licensee management personnel stated that this
volume of water would be held and processed using two portable mixed
bed demineralizers and released via the normal liquid radwaste release
systems. At the time of this inspection,
no radioactive secondary
water had been released. The inspector concluded that this was an
appropriate method for release and had no further questions.
d. The total gaseous activity released through the SJAE Monitor, 2R1A
40,
from September 18,
19,
and 20,
1981 was 8.94 curies which was
4.65 X 10-4 percent of the total release of gaseous activity during
1980; total particulates and halogens were
.078 curies which was
5.83 X 10-1 percent of the total release of halogens and particulates
during 1980. Total gas for all three units released during this same
period was 246.29 curies through the vent stack (monitor R1A-45) which
was 1.28 X 10-2 percent of the total release of gaseous activity during
1980 and the total iodine released through the vent stack for all three
units was 1.3 X 10-4 curies (monitor R1A-44)
which was 1.13 X 10-3
percent of the total releases of iodine during 1980.