IR 05000321/1979019
| ML19248D492 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/09/1979 |
| From: | Hosey C, Jenkins G, Wray J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19248D480 | List: |
| References | |
| 50-321-79-19, 50-366-79-24, NUDOCS 7908160327 | |
| Download: ML19248D492 (5) | |
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UNITED STATES
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E REGION 11
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101 MARIETTA sT., N W., SUITE 3100 ATL ANT A, GEORGI A 30303
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Report Nos. 50-321/79-19 and 50-366/79-24 Licensee: Georgia Power Company 270 Peachtree Street
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Atlanta, Georgia 30303 Facility Name: Edwin I Hatch, Units 1 and 2 Docket Nos. 50-321 and 50-366 License Nos. DPR-57 and NPF-5 Inspection at Hatch Un~
1 ar4d 2 near Baxley, Georgia
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Inspectors:
ate Signed 22LJa rh/n
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[7J.R.Wray Date Signed
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Approved by:.
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G.R.Jeppns,ActingSectionChief, Date Signed FFMS Tranch SUMMARY Inspection on June 18-22, 1979 Areas Inspected This routine, unannounced inspection involved 68 inspector-hours on-site in the area of radioactive waste management program, including radioactive effluent release monitoring and records, reports of radioactive effluents, procedures for controlling the release of effluents, effluent control instrumentation, reactor coolant water quality, solid radioactive waste disposal and followup on pre-viously identified items.
Results Of the seven areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees M. Manry, Plant Manager C. T. Moore, Assistant Plant Manager T. Greene, Assistant Plant Manager
- W. H. Rogers, Health Physicist / Radiochemist T. R. Collins, Laboratory Supervisor D. Smith, Laboratory Supervisor M. Link, Laboratory Foreman B. Hand, Laboratory Foreman C. E. Belflower, Quality Assurance Site Supervisor
- G. E. Spell, Jr., Senior Quality Assurance Field Representative Other licensee employees contacted included five technicians, four operators, three mechanics, and two office personnel.
- Attended exit interview.
2.
Exit Interview The inspection scope and findingr. were summarized on June 22, 1979 with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Radioactive Effluent Release Monitoring and Records Environmental Technical Specification 2.1.2 specifies the sampling and a.
monitoring requirements for radioactive material in liquid waste effluents.
An inspector selectively reviewed liquid waste release recordo for 1979 and discussed the records with licensee representa-tives. The frequency, type of analysis, concentration and total radioactivity apparently met the requirements of the Environmental Technical Specifications. An inspector observed the discharge of the contents of a liquid waste tank and verified that the release was made in accordance with plant procedure HNP-7601, Liquid Radioactive Waste Analysis and Discharge Program and the Environmental Technical Speci-fications. The verification included a review of the valve lineup used, liquid radwaste discharge monitor setpoints and a check of the operability of the automatic discharge valve in the discharge line.
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Environmental Technical Specification 2.1.1 requires that~the opera-bility of the automatic isolation valve in the liquid radioactive waste discharge be demonstrated quarterly.
An inspector reviewed the quarterly operability chech records for the period of July 1978 through April 1979. The checks were apparently performed in accor-dance with the Environmental Technical Specifications.
Environmental Technical Specifications 2.1.2.f and 2.1.4.d require c.
that liquid and gaseous effluent monitors, respectively, be calibrated at least quarterly and functionally tested monthly.
An inspector reviewed the calibrations of the Unit I liquid discharge radiation monitor, Unit 2 reactor building radiation monitor and the Unit I recoabiner building radiation monitor and the stack monitor performed in 1979.
The calibrations were performed at the required frequency or more often and appear to have met the Environmental Technical Speci-fication requirements.
An inspector reviewed the functional test records for the Unit I recombiner building vent radiation monitor for the period of January 1979 through May 1979.
An inspector observed the functional test of the recombiner building monitor and verified that the test was performed in accordance with plant procedure HNP-7405, Recombiner Building Vent Radiation Monitor and the Environ-mental Technical Specifications. The inspector observed a check of the alarm / trip setpoints for the recombiner building vent monitor and verified that the setpoints for the gas monitor were set as required by plant procedure HNP-7450, Process Monitors, ARMS, Ventilation Monitors Setpoints, d.
Environmental Technical Specifications 2.1.4 specified the sampling and monitoring requirements for radioactive material in gaseous ef-fluents.
An inspector selectively reviewed Gaseous Waste Release Permits for 1979 and discussed the records with licensee representa-tive s.
The frequency / type of analysis, concentrations and total radioactivity released apparently met the requirements of the Tech-nical Specifications. An inspector observed the collection and analysis of a gaseous activity sample from the pretreatment phase of the Unit 2 off gas system and verified that the collection and analysis was performed in accordance with plant procedure HNP-7116, Gaseous Waste Sample Analysis.
Environmental Technical Specification 2.1.3.h requires that the in-e.
stalled hydrogen monitors in the off gas system be set to limit the hydrogen concentration downstream of the recombiner to less than four percent by volume.
An inspector observed the readout of the Unit 2 monitor a,d verified that the hydrogen level was less than four per-cent by volume on June 19, 1979. The inspector also reviewed records of quarterly calibrations of the installed hydrogen monitors and verified plant procedures and environmental technical specifications are being complied with, f.
Environmental Technical Specifications 2.1.3.d requires that the operability of automatic isolation valve in the gaseous radwaste M_i.13
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discharge line be demonstrated quarterly.
An inspector reviewed the records of the quarterly operability checks performed between July 1978 and March 1979.
Apparently the checks were performed in ac-cordance with plant procedure HNP-3605, Off-gas System Automatic Isolation Valve Operability and the Environmental Technical Speci-fications.
6.
Radioactive Effluents Report Environmental Technical Specification 5.7.1.b requires that a report on the radioactive discharges released from the site during the previous six months of operation shall be submitt d to the NRC.
An inspector reviewed the plants Semi-annual Radioactive Effluent Release Report for the period of July 1978 through December 1978 and discussed the report with a licensee representative.
The inspector had no further questions concerning the report.
7.
Reactor Coolant Water Quality Through discussions with a licensee represei.tative and review of records for May and June 1979, the inspector verified that sampling and analysis frequency and the resultant data appeared to meet the requirements of Technical Specifications 3/4.6F (Unit 1) and 3/4.4.4 and 3/4.4.5 (Unit 2).
8.
Solid Radioactive Waste By review of records, observations and discussions with licensee repre-sentatives, an inspector reviewed the plant's solid radioactive waste processing and disposal program.
The licensee, at the request of the inspector, opened a drum of dewatered powder.esin.
The inspector verified that the drum contained no free-standing water.
The inspector performed independent radiation measurements on a trailer loaded with solid radio-active waste that the licensee was preparing for shipment to a licensed burial facility.
Radiation levels on the trailer did not exceed the limits specified by 49 CFR 173.393(j).
The inspector selectively reviewed shipping records for radioactive material shipped out during 1979. The inspector noted that the shipping papers did not contain the proper shipping name prescribed for the material by 49 CFR 172.101.
A licensee representative stated that this had been recognized and a change to the radioactive material shipping record frrm had been initiated.
The inspector had no further questions.
9.
Posting and Control The inspector observed the licensee's posting and control of radioactive material areas, high radiation areas, airborne radioactivity areas and contamination areas.
No items of noncompliance or deviations were iden-tified.
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Licensee Action on Previous Inspector Identified Items (Closed) Opra Item (366/78-42-02) Establishment of Setpoints for Liquid Effluent Monitors. The inspector reviewed a revision to plant procedure RNP-7601 which specifies that the setpoints are to be established based on a gamma spectrum analysis of the liquid effluent rather than on a gross radioactivity determination using a well counter.
The inspector had no further questions.
11.
Radioactive Effluent Control Procedures An inspector reviewed changes made to the following affluent control pro-cedures and verified that the changes are consistent with regulations and Technical Specifications:
HNP-7601, "I.iquid Radwaste Analysis and Discharge Program" a.
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HNP-7405, "Recombiner Building Vent Radiation Monitor" The inspector had no further questions.
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