IR 05000269/1979002
| ML19281A386 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/15/1979 |
| From: | Gibson A, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19281A378 | List: |
| References | |
| 50-269-79-02, 50-269-79-2, 50-270-79-02, 50-270-79-2, 50-287-79-02, 50-287-79-2, NUDOCS 7903130142 | |
| Download: ML19281A386 (8) | |
Text
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Report Nos.:
50-269/79-2, 50-270/79-2 and 50-287/79-2 Docket Nos.-
50-269, 50-270 and 50-287 License Nos.-
DPR-38, DPR-47 and DPR-55 Licensee: Duke Power Company Post Office Box 2178 422 South Church Street Charlotte, North Carolina 28242 Facility Name: Oconee Nuclear Station Inspected at: Oconee Site, Seneca, South Carolina Inspection conducted: January 15-19, 1979 Inspector:
C. M. Hosey Reviewed by:
Z[f11 A. F. Gibson, hief Date Radiation Support Section Fuel Facility and Materials Safety Branch Inspection Summary Inspection on January 15-19, 1979 (Report Nos. 50-269/79-2, 50-270/79-2 and 50-287/79-2)
Areas Inspected:
Routine, unannounced inspection of radioactive waste management program, including radioactive effluent releases, records and reports of radioactive effluents, procedures for controlling the release of effluents, and follow-up on previously identified items.
The inspection involved 36 inspector-hours on-site by one NRC inspector.
Results: No items of noncompliance or deviations were identified.
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RII Rpt. Nos. 50-269/79-2, I-1 50-270/79-2 and 50-287/ 79-2 DETAILS I Prepared by:
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C. M. Hosey, Radiati Specialist Date Radiation Support Sec ion Fuel Facility and Materials Safety Branch Dates of Inspection: Ja uar 15-19, 1979
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2[if[7J Reviewed by:
A. F. Gi6 son, (hief Date Radiation Support Section
%{Fuel Facility and Materials Safety Branch 1.
Individuals Contacted
- J. E. Smith, Station Manager
- R. M. Koehler, Superintendent of Technical Services
- C. T. Yongue, Station Health Physicist D. P. Rochester, Station Chemist L. A. Blue, Health Physicist S. R. Hewcomb, Junior Health Physicist G. F. Davis, Health Physics Supervisor R. Adams, I&C Engineer D. L. Davidson, Health Physics Supervisor J. A. Long, Health Physics Supervisor
- R. T. Bond, Technical Services Supervisor R. Futrell, Health Physicist (Corporate Office)
- D.
J. Vito, Technical Services Engineer F. Jape, USNRC Resident Inspector The inspector also talked with and interviewed other licensee employees, including health physics technicians, reactor and auxiliary operators and general office personnel.
- Denotes those present at the exit interview 2.
Licensee Acti i on Previous Inspection Findings a.
(Closed) Unresolved Item (77-16-01), In Place Filter Testing Prerequisites Although the prerequisite test specified in ANSI-N510-1975 were not required by Technical Specifications, licensee management stated that those tests recommended by their ventilatinn system consultant would be performed. This item is discussed further in paragraph.
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RII Rpt. Nos. 50-269/79-2, I-2 50-270/79-2 and 50-287/ 79-2 b.
(Closed) Noncompliance (269/270/78-15-01; 287/78-16-01), Failure to Follow Procedure for Preparing Spent Fuel Cask for Shipment The inspector reviewed the licensee's corrective action in response to this item and had no further questions.
c.
(Closed) Noncompliance (269/270/78-15-02; 287/78-16-02), Failure to Perform Necessary Radiation Surveys in Interim Radwaste Building The inspector reviewed the licensee's corrective action in response to this item and had no further questions.
d.
(0 pen) Unresolved Item (269/270/78-15-03; 287/78-16-03), Contamination Control Program The inspector reviewed the licensee's corrective action specified in Duke Power's letter of October 25, 1978.
This item is discussed further in paragraph 3.
(Closed) Open Item (269/270/78-15-04; e.
287/78-16-04), Smear Counting and Instrument Calibration Procedures The inspector reviewed the licensee's methods of calibrating instruments and counting smears used for determining loose surface contamination levels and had no further questions.
f.
(Closed) Open Item (269/270/78-15-05; 287/78-16-05), Including Total Activity Released Year-to-Date on Liquid Waste Release Form The inspector discussed this item with a licensee representative.
The licensee representative stated that the amount of radioac-tivity released in gaseous and liquid effluents is included on the Radwaste Status Report which is issued daily, and that the indi-vidual approving the release of liquid waste has this report available.
He further stated that plant management monitor the status of radioactive effluent releases and would take action to reduce releases if the quarterly limit were approached.
The inspector had no further questions.
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RII Rpt. Nos. 50-269/79-2, I-3 50-270/79-2 and 50-287/ 79-2 g.
(0 pen) Open Item (269/270/78-15-06; 287/78-26-06), Saturation of G-M Detectors The licensee reviewed the circuitry for effluent radiation monitors and determined that the G-M tubes in radiation monitors RIA-46 (vent gas monitor), RIA-38 (waste gas monitor) and RIA-51 (penetra-tion room exhaust) will saturate at high dose rates.
A modification request has been prepared and material ordered to backfit the equipment with non-saturating current-mode circuitry.
This item will remain open pending completion of the modification.
h.
(Closed) Noncompliance (269/270/78-20-01; 287/78-21-01), Failure to Keep Entrance to High Radiation Area Locked The inspector reviewed the licensee corrective action in response to this item.
The licensee determined that the design of the locking mechanism allowed the door to be unlocked without a key.
The inspector verified that the doors had been modified to preclude unlocking without a key.
The inspector had no further questions.
i.
(0 pen) Noncompliance (269/287/78-27-01; 270/78-26-01), Failure to Keep Entrance to High Radiation Area Locked Duke Power's letter of December 20, 1978 stated that hollow metal doors, metal frames, locks, closers and local battery powered alarms have been ordered for installation z.t the entrances to all high radiation areas.
Delivery of material is expected in February 1979 and installation completed within ten weeks following receipt of materials.
This item will remain open pending installation of the doors.
j.
(Closed) Noncompliance (269/287/78-27-02; 270/78-26-02), Failure to Follow Procedures The inspector reviewed the licensee's response to this item.
Instrument calibration procedures have been revised to reflect required calibration techniques and source levels. The new procedures were issued on January 10, 1979. The inspector had no further questions.
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RII Rpt. Nos. 50-269/79-2, I-4 50-270/79-2 and 50-287/ 79-2 k.
(Closed) Unresolved Item (269/287/.3-27-03; 270/78-26-03), Calibration of Effluent Radiation Monitors The inspector selectively reviewed functional test of RIA-33 and RIA-38 completed between August and December 1978 and had no further questions.
1.
(Closed) Open Item (269/287/78-27-04; 270/78-26-04), Prerequisite Testing of Air Filtration Systems The inspector reviewed a letter from the licenser's ventilation system consultant.
The consultant stated that tue prerequisite test required by ANSI-N510-1975, " Testing of Nuclear Air Cleaning Systems" had been performed as a part of systems acceptance testing; however, the results were not documented.
The consultant feels that the requirements of ANSI-N510 have been met and that no additional prerequisite tests are necessary.
The inspector had no further questions.
3.
Contamination Control Program The inspector reviewed the progress being made by the licensee to a.
reduce the background radiation levels in the vicinity of frisking stations so that the personnel friskers can be operated on the most sensitive scale (X1).
A licensee representative stated that all the necessary material would be on-site by January 22, 1979 and that the first shielded frisking booth would be ready for installation by February 1, 1979. The remaining shielded frisking booths are to be constructed and installed in a timely manner. A licensee management representative stated that the shielding of sample lines passing near exits from the Radiation Control Area (RCA) or the relocation of the sample lines was still being considered by the corporate design engineering staff; however, the necessary drawings to shield or relocate the lines would be sent to the plant within a week.
He further stated that most of the waterial was on-site to shield the lines if that was the elected course of action.
The inspector commented that the initial request for modification to the plant (Nuclear Station Modifi-cation Number ON-0795) was dated March 1977 and that nearly two years later the requested modifications have not been completed.
The inspector further stated that increased management attention was needed to ensure that the high background in the vicinity of friskers is promptly corrected. The inspector stated that unresolved item (269/270/78-15-03 and 287/78-16-03) would remain
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open pending completion of licensee's action to reduce the background radiation levels in the vicinity of frisking station.
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RII Rpt. Nos. 50-269/79-2, I-5 50-270/79-2 and 50-287/ 79-2 b.
During tours of the plant, the inspector observed personnel frisking themselves and using the portal monitors.
Plant personnel appear to be following the procedures for exiting Radiation Controlled Areas. A licensee representative stated that members of the health physics staff periodically observe personnel frisking practices as a method of ensuring that proper frisking practices are being used. The inspector had no further questions concerning frisking practices.
c.
The inspector reviewed the results of weekly surveys of the interim radwaste building corridors for December 1978 and January 1979 and performed independent radiation and smear surveys in the interim radwaste building and the auxiliary building.
It appears that the interim radwaste and the auxiliary buildings were properly posted by the licensee. The inspector had no further questions concerning contamination surveys.
4.
Radioactive Effluent Release Monitoring and Records The inspector observed the collection and analysis of a gaseous a.
activity sample from a waste gas tank and verified that the collection and analysis was performed in accordance with plant procedure HP/0/B/1000/60A, " Procedure for gaseous waste sampling and analysis". The inspector selectively reviewed gaseous waste release records for December 1978 and discussed the records with licensee representatives. The frequency, type of analysis, concentrations and total radioactivity released apparently met the requirements of the Technical Specifications.
The inspector also reviewed the analysis of waste gas tanks for the period of December 17-31, 1978. Apparently, no tank exceeded the limit of total activity contained in the tank during this period.
Gaseous effluent records are apparently being maintained in accordance with Technical Specifications.
The inspector also reviewed the following records:
(1) Unit 1 Vent Weekly Iodine analysis for December 1978 (2) Units 1 and Unit 3 Vent weekly gaseous analyses for December 1978 (3) Units 1, 2 and 3 Vent Quarterly composite particulate SR-89/90 analyses for 1st, 2nd and 3rd quarters 1978 (4) Units 1, 2 and 3 Vent Quarterly Gross alpha analyses for 1978 b.
The inspector selectively reviewed liquid waste release records for January 1979 and discussed the records with licensee repre-
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RII Rpt. Nos. 50-269/79-2, I-6 50-270/79-2 and 50-287/ 79-2 sentatives. The frequency, type of analysis, concentrations and total radioactivity released apparently met the requirements of the Technical Specifications.
The inspector also reviewed the monthly composite sample results for various liquid waste tanks for the period of June through November 1978.
It appears that liquid effluent reccrds are apparently being maintained in accordance with Technical Specifications.
The inspector had no further questions concerning effluent release monitoring and records.
5.
Radioactive Effluent Control Procedures The inspector reviewed changes made to the following effluent control procedures and verified that the changes are consistent with regula-tions and Technical Specifications:
a.
HP/0/B/1000/60A, " Procedure for Gaseous Waste Sampling and Analysis" b.
HP/0/B/1000/60B, " Procedure for Reactor Building Gaseous Purge" c.
HP/0/B/1000/60C, " Procedure for Sampling and Release Requirements for CTT, CMT and LHST" d.
HP/0/B/1000/60E, " Procedure for Preparation and Counting of CTT, CMT, LHST Composite Samples" e.
HP/0/B/1000/60D, " Procedure for Unit Vent Sampling and Analysis" f.
OP/1&2/A/1104/07, " Liquid Waste Disposal System" g.
OP/3/A/1104/18, " Gaseous Waste Disposal System" h.
OP/0/A/1104/32, " Interim Waste System" i.
OP/0/A/1104/33, " Transfer of Liquid Waste Concentrate to Mobile Unit" The inspector had no further questions.
6.
Control of Radioactivity in Chemical Treatment Ponds The inspector reviewed the procedure for controlling the release of radioactive spent powdex resin to the chemical treatment ponds. The inspector also reviewed the radionuclide inventory records of the chemical treatment ponds. The present inventory is apparently less than the limit that was committed to in Duke Power's letter ~of December 27, 1978. The inspector had no further question. '
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RII Rpt. Nos. 50-269/79-2, I-7 50-270/79-2 and 50-287/ 79-2 7.
Interconnection of Contaminated Systems with Breathing Air Systems The inspector discussed with a. licensee representative an event which occurred at another facility involving the contamination of the plant source of breathing air when contamination leaked from the radwaste system into the plant's service air system. A licensee representative stated that the plant has a separate breathing air system that is not interconnected with service air or any potentially contaminated system.
The system uses filtered outside air and potable drinking water-cooled compressors. The inspector reviewed the plant drawing of the breathing air system and apparently the system is not interconnected to any other system. The inspector also reviewed the records of the weekly 0, CO, CO, and hydrocarbon analysis of breathing air.
The inspector 2commented that periodic radioactivity analysis should be performed.
The licensee representative stated that this analysis would be considered the next time the system is placed in service.
8.
Exit Interview The inspector met with management representatives (denoted in paragraph 1) on January 19, 1979, and summarized the scope and findings of the inspection.
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