IR 05000335/1979005
| ML17206A731 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/08/1979 |
| From: | Gibson G, Hufham J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17206A729 | List: |
| References | |
| 50-335-79-05, 50-335-79-5, NUDOCS 7904170528 | |
| Download: ML17206A731 (5) | |
Text
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%p*y4 UNITED STATES NUCLEAR REGULATORYCOMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303 Report No.:
50-335/79-5
'Licensee:
Florida Power 8 Light Company Advanced Systems and Technology P. 0. Box 529100
.
Miami, Florida 33152 Facility Name:
St. Lucie, Unit 1 Docket No.:
50-335 License No.:
DPR-67 Inspection at St. Lucie Site near Hu ch on Island, Florida Inspector:
6.
. Gibso 3%
%7)
ate Signed Approved by:
J.
W. Hufham S
tion ief, FFSMS Branch ate Signed SUMMARY Inspection on January 29-30, 1979 This routine, unannounced inspection involved 9 inspector hours on site and 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> off-site in the areas of confirmatory measurements including:
examination of laboratory radiochemical equipment and instrumentation; review of laboratory quality control and quality assurance records; and a
collection of confirmatory measurements samples for future comparison of their analytical results.
Results Of the 3 areas inspected, no apparent items of noncompliance or deviations were identifie DETAILS 1;
Persons Contacted Licensee Em lo ees C. Wethy, Plant Manager R. Jennings, Technical Supervisor J. Barrow, Operations Superintendent
+N, Roos, QA Engineer-A. Bailey, Quality Assurance Supervisor R. Frechett, Chemistry Supervisor
+Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on January 30, 1979 with those persons indicated in Paragraph
above.
The inspector summarized the scope of the inspection and the findings.
3.
Licensee Action on Previous Ins ection Findin s Not inspected, 4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Radiochemist Procedures The inspector review the licensee's radiochemistry program, and discussed with licensee personnel the implementation of the radiochemistry and reactor coolant chemistry analysis programs.
The inspector noted the licensee's procedures were approved and reviewed as per Technical Specification 6.8.1.
6.
Radiochemist E ui ment and Instrumentation The inspector examined the licensee's chemistry and radiochemistry laboratory, including instrumentation and equipment.
The inspector noted the licensee has initiated appropriate quality control programs to assure proper instrument calibration.
The inspector examined calibration records for 1978 for selected instrument.
Anal tical Measurements a.
The inspector examined all liquid waste release documentation regarding gamma spectroscopy records for the months of November and December 1978.
The inspector observed that the analyses and analytical sensitivity limits of Technical Specification 2.4.2 were met for the records reviewed.
The inspector had no further questions regarding this item at this time.
b.
The inspector observed that the licensee has initiated appropriate methods for the calculation of the selected nuclides, when the nuclide is undetected but the sensitivity of the measurement is above prescribed limits of Technical Specifications 2.4.2 and 2.2.2.
Previous items 335-77-07-02 and 335-77-07-01 are considered closed.
8.
ualit Assurance
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inspection.
(335-79"5-01 9.
Confirmator Measurements The inspector discussed with licensee personnel the quality assurance audits conducted since the last inspection in 1977.
The inspector was unable to review audit results which are performed by FP&L headquarters personnel.
Therefore, this item will be examined during a subsequent
)
The inspector collected actual plant waste gas, liquid waste tank, building particulate filter, and charcoal adsorber effluent samples for confirmatory measurements.
These samples were forwarded to the NRC reference laboratory in Idaho Falls, Idaho.
The results of these analyses will be compared with the licensee's results of these samples, during a subsequent inspection.
(335-79"05-02)
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