IR 05000395/1982020
| ML20050K384 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/18/1982 |
| From: | Evans C, Montgomery D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20050K271 | List: |
| References | |
| 50-395-82-20, NUDOCS 8204140218 | |
| Download: ML20050K384 (4) | |
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t; UNITED STATES
8 NUCLEAR REGULATORY COMMISSION o
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E REGION 11 g[
101 MARIETTA ST., N.W., SUITE 3100 o,
ATLANTA, GEORGIA 30303
Report No. 50-395/82-20 Licensee:
V. C. Summer Facili/ Name: South Carolina Electric
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and Gas Company Columbia, SC 29218 Docket No. 50-395 License No. CPPR-94 Inspection at V. g Su erSi[
Inspector:
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C. D. Evans, Date Signed C';
3 - /9 [r7 Approved by: _
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I n. M.liontgomery, C)fdf Date Signed D
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I dependent Measur6ments and Environmental Protection Section, Division of Emergency Preparedness
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and Operational Support Suitt1ARY Inspection on itarch 1-2, 1982 Areas Inspected This routine, unannounced inspection involved 13 inspector-hours on site in the areas of quality control for radiochemistry including a review of the laboratory quality control program and the radioactive effluent accountability program.
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Results Of the two areas inspected, no violations or deviations were identified in these areas.
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8204140218 820322 PDR ADOCK 05000395 O
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l DETAILS I
1.
Persons Contacted
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l Licensee Employees
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- J. Connelly, Deputy Plant Manager
- S. S. Howze, Licensing Engineer
- H. C. Fields, Licensing Engineer
- D. A. Lavigne, Quality Assurance
- R. G. Sweet, Quality Assurance
- L. A. Blue, Health Physics Supervisor
- J. W. Cox, Health Physics Supervisor Other licensee employees contacted included one technician.
NRC Resident Inspector J. L. Skolds
- Attended exit interview-2.
Exit Interview The inspection scope and findings were summarized on March 2,1982, with those persons indicated in paragraph 1 above. The inspector requested that the licensee provide a space within the protected area with electrical power receptacles for the NRC Mobile Laboratory. The Deputy Plant Manager agreed to provide these facilities by May 31, 1982. The inspector informed licensee representatives that the capability to perfonn tritium analyses of effluent samples needs to be established prior to initial criticality (82-04-09).
3.
Unresolved Items Unresolved items were not identified during this inspection.
4.
Review of Radiochemistry Procedures and Records The inspector reviewed the following procedures and records:
a.
Procedures 1.
HPP-808, " Sample Analysis", 2-10-82, 2.
CHP-305, " Technical Ruiew of Radiological Monitoring Programs",
2-3-8.
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3.
HPP-817, " Quality Control of Sampling and Sample Analysis Methods", 2-10-82.
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HPP-709, " Release of Radioactive Gaseous Effluents", not issued.
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HPP-802, " Operation of Beckman L. S. 7500 Liquid Scintillation Counter", not issued.
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Records 1.
Efficiency Calibration Records for Ge (Li) Detectors 1 and 2.
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QA Type I Surveillance Report, No. 3828.
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Memorandum to SC&G Nuclear Engineering Manager from Gilbert Associates, letter No. 26032 j
The inspector discussed the results of the procedure and record review with licensee representatives as noted in paragraphs 4c - 41.
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i The inspector noted that procedure HP-808, " Sample Analysis", had been c.
revised to incorporate a methodology for compositing samples from the
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j turbine sump for weekly analysis. This closes a previously identified item (82-04-07).
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d.
The inspector noted that corporate procedure CHP-305, " Technical Review i
of Radiological Monitoring Programs", details provisions for a comprehensive annual audit of activities required by the Laboratory i
Quality Assurance Program to meet the criteria of Regulatory Guide 4.15.
The procedure assigns responsibility for conducting the audit to the SCE&G Environmental Laboratory. This closes a previously identi-fied item (82-04-04).
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The inspector detemined that audits of the radiochemistry and chemistry programs are conducted by the Plant Quality Assurance Staff
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as required by the, " Operational Ouality Assurance Program Manual".
These audits are performed annually and are intended to vedfy compliance with Technical Specifications and Operating Procedures.
This closes a previously identified item (82-04-03).
f.
The inspector noted that procedure HPP-808, " Samples Analysis", had been revised to incorporate a methodology for normalization of the waste gas decay tank activity to Ye-133 equivalency. This closes a previously identified item (82-04-06).
The inspector noted that procedure HPP-817, "Ouality Control of Sampling and Sample Analysis Methods", had been revised to allow for periodic review of laboratory analytical results by management. This closes a previously identified item (82-04-02).
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The inspector noted that procedure HPP-817, " Quality Control of Sampling and Sample Analysis Methods", had been revised to include the establishment of an interlaboratory cross-check program with the SCE&G Environmental Laboratory.
Spiked samples will be issued quarterly to the plant countroom for analysis. This closes a previously inspector identified item (82-04-01).
h.
The inspector noted that procedure HPP-703, " Release of Radioactive Gaseous Effluents", was still in draft form. A licensee representative indicated that they were waiting on approval of changes to the Offsite Dose Calculation Manual before finalization of the procedure could be made. The inspector stated that this area would be carried as an inspector identified item (82-20-01).
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The inspector noted that the licensee's engineering consultant had recommended a flow rate of 3.6 CFM for the process stack sampler in order to maintain isokinetic sampling. The inspector was informed by a licensee representative that no velocity traverse measurements had been done of the stack at the point of sampling. The inspector informed licensee representatives that velocity traverse measurements in the process stack and evaluation of charcoal cartridge collection efficiencies would be necessary to demonstrate the validity of the stack sampling system.
A licensee representative stated that the velocity traverse measurements will be made, and that the collection efficiency of the charcoal cartridge as a function of flow rate would be evaluated. This area will be reviewed in a subsequent inspection.
(82-20-02)
5.
Capability Tests The licensee has not completed the required analysis of the DOE simulated waste liquid sample for tritium and strontium 89 and 90.
A licensee representative stated that the selection of a contract laboratory for strontium 89 and 90 analysis was taking longer than expected because of the delays in the approval process by corporate QA and; that analysis capability for tritium was dependent upon satisfactory operation and performance of the liquid scintillation counter. This is a previously identified item (82-04-12).
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