IR 05000369/1981018
| ML20009D811 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 06/23/1981 |
| From: | Hosey C, Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20009D805 | List: |
| References | |
| 50-369-81-18, NUDOCS 8107240369 | |
| Download: ML20009D811 (6) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
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101 MARIETTA ST.. N.W.. SUITE 3100 ATLANTA, GEORGIA 30303
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Report No. 50-369/81-18 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire 1 Docket No. 50-369 License No. NPF-9 Inspection at McGuire site nearprnelius, North Carolina g
Gds /af Inspector:
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G. L. Troup' ;f ~[
Date Signed JM 6 2.7 j/
Approved by:
C. M. Ho'sey, Acting Ch[ef, Facilities Radiation Date Signed Protection Section,/ Technical Inspection Branch, Engineering and Technical Inspection Division SUMMARY Inspection on June 1-5, 1981 Areas Inspected This routine, unannounced inspection involved 32 inspector-hours onsite in the areas of radioactive waste management and radiation protection including effluents control, external exposure control, radiation worker training, technician qualifications, transportation activities and previously identified items.
Results Of the areas inspected, no violations or deviations ware identified.
8107240369 810626 PDR ADOCK C5000369 C
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REPORT DETAILS 1.
- Persons Contacted Licensee Employees
"M. D. McIntosh, Station Manager
- T. L. McConnell, Superintendent of Technical Services
- G. W. Cage, Superintendent of Operations
- T. J. Keane, Station Health Physicist R. P. Michael, Station Chemist
- W. M. Sample, Projects and L icensing Engineer
- R. M. Propst, Radwaste Chemistry Coordinator T. Parker, Training Supervisor J. W. Foster Health Physics Coordinator P. G. Huntley, Health Physics Supervisor
C. H. Bailey, Health Physics Administrative Supervisor
- D. M. Franks, Quality Assurance J. A. Effinger, Quality Assurance Engineer A. F. Batts, Assistant Engineer
- D. B. Lampke, Associate Engineer D. Motes, Jr. Engineer Other licensee employees contacted included two technicians, one operator, and two office personnel.
NRC Resident Inspector
- M. J. Graham
- Attended exit interview 2.
Exit Interview The inspection scopa and findings were summarized on June 5,1981 with those persons indicated in paragraph 1 above. Regarding the previously identified items on the stack sample probe evaluation and the evaluation of the charcoal adsorber residence. times, the inspector emphasized that these are Technical Specification or license requirements which must be met prior to criticality; this was acknowledged by the station manager.
The inspector also stated that the vent stack flow meter repair! must be completed in a timely manner; this was also acknowledged.
3.
Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items e--
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Unresolved items were not identified during this inspection.
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Radioactive Effluent Control a.
(0 pen) Design Basis of Stack Sampling Probe (78-41-02)
This item was orginally discussed in RII Report No. 50-369/78-41, paragraph 6 and dealt with the design basis and verification of the stack sampling probe. A licensee representative informed the inspector that the verification measurements (flow traverse) had been performed and documented.
The measurement report had been forwarded to Design Eigineering for evaluation but the acceptance and verification report had not been received.
Condition 2.c.(14)b of the operating license requires that this se completed prior to initial criticality.
b.
(Closed) Effluent Flow Rate Monitor on the Unit Vent (79-12-13)
This item was originally discussed in RII Report No. 53-369/79-12, paragraph 10.g and dealt with the need to install a flow rate monitor on the unit vent to measure the volume of air released.
Conditic, 2.c.(14)d of the operating license requires that the flow rate monitor be installed and operable prior to initial criticality. The inspector reviewed modification package (M6-024) and the work requests for the installation, and reviewed the instrument cal 1 oration records.
The inspector also observed the installation of the instruments (flow rate and total flow) on the HVAC control board. Although the flow rate monitor has been installed and completed, at the time of the inspection, it was out of service pending repair of a sensing line under a work request. The inspector informed licensee management that open item 79-12-13 was closed for record purposes but emphasized that
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the unit was required for operation; this comment was acknowledged.
6.
(0 pen) Charcoal Bed Residence Time (81-02-01)
This item was originally discussed in RII Report No. 50-369/81-02, paragraph 5.c and dealt with the incomplete evaluation of the residence time for charcoal adsorbers. A licensee representative informed the inspector that information had been received from Design Engineering concerning the maximum flow rates for each system which would provide residence times which meet
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the criterion of ANSI N510-1975. However, the evaluation was incomplete in that the residence time had not been evaluated for the actual flow rates.
The inspector stated that this iter remained open pending the completion of the residence time evaluatio.
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(0 pen) Spent Resin Sluice Pump Shielding (79-12-03)
Shielding has not been installed arcund the sluice pump to reduce radiation levels for maintenance of valves i.) the pump room. A licensee represent-ative informed the inspector that the shield design was still under evaluation.
8.
(0 pen) Exhaust Monitor Sample Lines (80-21-02) - Radwaste Addition Facility This item was originally discussed in RII Report No. 50-369/80-21, paragraph 7.b, and dealt with the unsatisfactory installation of sample lines due to numerous bends and long horizontal runs. A licensee representative informed the inspector that the sample line would be madified to relocate the
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particulate / iodine filter holder near the sample point. This work has not been accomplished. This item remains open.
9.
(Closed) Waste Solidification Procedures (30-12-05)
This item was originally discussed in RII Report No. 50-369/80-12, paragraph 14, and dealt with the status of the implementing procedures for the waste solidification program.
A licensee representative informed the inspector that chemistry procedure CP/0/B/8600/13, "Radwaste Chemistry Procedure for Solidification and Preparation for Shipment", had been approved.
The inspector reviewed the procedure and informed licensee management that this item was closed.
10.
Posting of Notices 10 CFR 19.11 requires that Form NRC-3 and certain documents be posted in a sufficient number of places to permit individuals engaged in licensed activities to -observe them on the way to or from any particular licensed activity location. In lieu of posting a'l of the documents, a notice may be posted stating where the documents may be examined. The inspector observed
that the Form NRC-3 and the notice were posted in numerous locations around the plant. However, the notice did not list the current facility license; an updated notice was posted during the inyection.
The inspector had no further questions.
11.
External Exposure Control a.
10 CFR 20.101(b) specifies the requirements for authori:ing an individual to receive * quarterly dose up to 3 rems.
The inspector selected twelve indivir als at random who are listed in the exposure printout as radiation 5 (ers with authorized exposures of 3 rems. The individuals selected included maintenance, security, chenii s try,
operations, health physics and supervisory personnel.
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b.
The inspector reviewed the records for the twelve individuals and verified that each had a completed Form NRC-4 un file and that previous exposures had been documented, as required by 10 CFR 20.101(b).
The inspector also verified that each individual had received a whole body count and completed the exposure questionnaire as required by station procedure HP/0/8/1000/01, " Personnel Radiation Exposure Control".
c.
10 CFR 20.104 limits the exposure of minors to 125 mrem per quarter. A licensre representative informed the inspector that no minors were employed at the station.
d.
Regulatory Guide 8.13, " Instruction Concerning Prenatal Radiation
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Exposure", states the exposure of a pregnant female snould not _xceed
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500 mrem during the gestation period. The licensee's exposure control program includes a special category in the printout for pregnant females.
A licensee representative stated that persons in this category are limited to 500 mrem and require the approval of the station health physicist to be returned to another exposure category.
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The inspector informed licensee management that he had no questions in the areas of the exposure control program which were inspected.
12. Qualifications of Health Physics Technicians Technical Specifications 6.3.1 states, in part, "Each 9 ember of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971".
The inspector reviewed the qualifications of eight health phys r technicians who were designated " qualified" in approximately the last year.
All exceeded the qualifications of ANSI N18.1-1971.
The inspector had no further questions.
13.
Health Physics Training a.
Technical Specification. 6.4.1 states, in part, "A retraining and replacement training program for the unit staff...shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971". Procedure HP/0/C/1000/01, " Personnel Radiation Exposure Control" requires that healch physics training be completed prior to the issuance of dosimetry devices. Station Directive 2.5.0, "Trainino Program Implementation", requires that health physics and security training be completed annually ( 3 months).
b.
The. inspector reviewed the " Access Training Record" for twelve individuals (see paragraph 11.a). All of the individuals had completed the training as required by Station Directive 2.5.0.
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c.
The inspector also discussed the retraining program for health physics technicians with the cognizant supervisor.
The supervisor explained that the retraining program was on a two year cycle and was conducted by the Training Center.
This training is in addition to periacic training conducted for each crew approximately every sixteen weeks.
14.
Transportation Activities IE Bulletin 79-19, " Packaging of Low-Level Radioactive Waste for Transport and Burial", described actions to be taken to assure the proper transfer, packaging and transport of low-level radioactive waste.
The inspector reviewed the various actions (maintain current regulations and disposal site licenses, provide written procedures, provide training, conduct an audit program) with licensee r?presentatives and verified that each of the actions had been completed.
The inspector had no further questions.
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15.
Radioactive Sources Technical Specification 4.7.9.2 requires that each radioactive source containing more than 100 uCi of beta gamma activity or 5 uCi of alpna activity be leak tested at least every six months. Technical Specification 4.7.9.2.c requires that startup sources be tested within 31 days prior to installation in the core.
The inspector reviewed the records of PT/0/B/4600/13, " Inventory and Leak Test of Sealed Sources", and verified that the required tests had been performed as required. The inspector had no further questions.
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