IR 05000327/1978044
| ML19283B590 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/10/1979 |
| From: | Gibson A, Jackson L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19283B589 | List: |
| References | |
| 50-327-78-44, 50-328-78-29, NUDOCS 7903010050 | |
| Download: ML19283B590 (4) | |
Text
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UNITED STATES
- g# #f 00g NUCLEAR REGULATORY COMMISSION o,,
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o REGION il
r 101 M ARIETTA STREET.N.W.
ATLANTA, GEORGIA 30303
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Report Nos.:
50-327/78-44 and 50-328/78-29 Docket Nos.: 50-327 and 50-328 License Nos.: CPPR-72 and CPPR-73 Licensee: Tennessee Valley Authority 830 Power Building Chattanooga, Tennessee 37401 Facility Name: Sequoyah I and 2 Inspection at: Soddy-Daisy, Tennessee Inspection conducted: December 18-22, 1978 Inspector:
L. L. Jackso y
\\1 Reviewed by:
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)/~l'/ l A. F. Gibson, Chief Date Radiation Support Section Fuel Facility and Materials Safety Branch Inspection Summary Inspection on December 18-22, 1978 (Report Nos. 50-327/78-44 and 50-328/78-29)
Areas lnspected:
Routine, unannounced inspection of the status of preoperational testing for radwaste systems and the status of radiation protection program. The inspection involved 35 inspector-hours on-site by one inspector.
Results: No items of noncompliance or oeviations were disclosed.
790301CC O
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RII Report Nos. 50-327/78-44 and 50-328/78-29 I-I L
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DETAILS I Prepared by:
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' d otN L. L. Jackson, Radiation Specialist Date k
Radiation Support Section I
Fuel Facility and Materials
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Safety Branch Dates of Inspection:
cember 18-22, 1978 I//C [7 i Reviewed by:
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N A. F. Gibsoh, Section Chief Date Radiation Support Section Fuel Facility and Materials Safety Branch 1.
Persons Contacted J. M. Ballentine, Plant Superintendent
- C.
E. Cantrell, Assistant Plant Superintendent
- W. E. Andrews, Quality Assurance Supervisor
- W. H. Kinsey, Jr., Assistant Results Supervisor
- J.
T. Dills, Jr., Chemical Engineer
- R.
L. Kitts, Health Physics Supervisor
- D. P. Ormsby, Regulatory Staff Member-TVA
- Denotes those present at the Exit Interview.
2.
Licensee Action on Previous Inspection Findings No licensee actions on previously identified findings were reviewed during this inspection.
3.
Unresolved Items There were no new unresolved items disclosed during this inspection.
4.
Representative Sampling:
Auxiliary Building Exhaust This item was first discussed in Region II Report Numbers 50-327/77-16, and 50-328/77-12 and later in Region II Report Numbers 50-327/77-33, 50-328/77-23, 50-327/78-23 and 50-328/78-17. The inspector discussed the status of proposed modifications to the auxiliary building exhaust sampling system with both site and corporate staff representatives.
Design is complete but an installation date has not been established because the materials of construction have not been procured.
When information becomes available regarding the time of delivery of materials and whether or not it is necessary or desirable to perform the installation prior to startup, further discussions will be held
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RII Report Nos. 50-327/78-44 and 50-328/78-29 I-2 with licensee representatives to establish a date by which installa-tion should be complete and the licensee's plans for interim sampling.
5.
Health Physics and Chemistry Organization The inspector reviewed the health physics and chemistry staffs to verify that staff size and qualifications were consistent with FSAR commitments. The staff size and qualifications meet the FSAR commitments.
6.
Radiation Protection Training and Retraining The inspector reviewed training records for training being conducted for the purpose of complying with 10 CFR 19.12 and commitments in the FSAR. A licensee representative stated that approximately 97 percent of the permanent plant personnel have received radiation protection training and many of the construction personnel have also received this training.
The training records for several individuals were checked and found to be satisfactory.
Some indi-viduals have already received retraining and it appears that a satisfactory system has been instituted to identify individuals requiring retraining.
7.
Radiation Protection Procedures The inspector reviewed all twelve approved radiological control instructions (RCI's) and observed that there were many section instruction letters (SIL's) written to implement the RCI's.
The RCI's appear to be compatible with requirements in 10 CFR 19 and 10 CFR 20.
RCI's are reviewed by the plant review committee and approved by the plant superintendent.
sit's are not necessarily reviewed by the plant review committee and are approved by the responsible supervisor.
Management represen-tatives were informed that although SIL's did not follow the same review and approval route as RCI's, certain SIL's would be reviewed at a later date and that adherence to SIL's as well as RCI's would be inspected.
8.
Instruments and Equipment The inspector observed the health physics instrumentation on hand and discussed the calibration program with a licensee representative.
The equipment on hand meets the FSAR commitment and portable health physics instruments are being calibrated by the Division of Environ-mental Planning-Laboratory Branch, in Muscle Shoals, Alabama. The Muscle Shoals calibration program is operated in general support of all TVA nuclear plants and has been inspected as part of the Browns Ferry Nuclear Plant operations.
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RII Report Nos. 50-327/78-44 and 50-328/78-29 I-3 The inspector found no problems in this area.
9.
Respiratory Protection Program The inspector reviewed the following elements of the respiratory protection program:
Written policy statement
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Air sampling procedures
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Bioassay program (whold body counting)
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Training, fitting and testing procedure
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Maintenance procedure Control, issuance, use and return of equipment
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Equipment on hand
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Equipment selection and use criteria
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These elements exist and are part of an established program.
Several hundred people have been trained and qualitatively fitted and many of these had background whole body counts performed.
10.
Plant Tour The inspector toured the plant, looking at the installation of various radiation monitors. These monitors are in varying stages of completion.
Some appear to be ready for calibration while others do not have sample piping or electrical service installed.
No problems were identified as a result of the plant observations.
11.
Exit Meeting The inspection scope and findings were summarized on December 22, 1978, with those persons indicated by an asterisk in paragraph 1, above.
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