IR 05000269/1982017
| ML20058H596 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/10/1982 |
| From: | Barr K, Collins T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058H495 | List: |
| References | |
| 50-269-82-17, 50-270-82-17, 50-287-82-17, NUDOCS 8208030636 | |
| Download: ML20058H596 (8) | |
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%g UNITED STATES Jg NUCLEAR REGULATORY COMMISSION g
p, REGION 11
E 101 MARIETT A ST., N.W.. SUITE 3100
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ATLANTA. GEORGIA 30303
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Report Nos. 50-269/82-17, 50-270/82-17 and 50-287/82-17 Licensee: Duke Power Company P. O. Box 2178
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Charlotte, NC 28242 Facility Name:
Oconee 1, 2, and 3 Docket Nos. 50-269, 50-270 and 50-287 License Nos. DPR-38, DPR-47 and DPR-55 Inspection at Oconee Nuclear site near Seneca, South Carolina Inspector:
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T. R. Collins
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Date Signed Approved by:
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K. P. Barr, Section Chief Da'te Signed Technical Inspection Branch Division of Engineering and Technical Programs
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SUMMARY Inspection on May 10-14, 1982 Areas Inspected This routine, unannounced inspection involved 34 inspector-hours on site in the areas of radiation protection, radwaste shipments, health physics appraisal findings, previous unresolved and inspector follow-up items.
Results i
Of the five areas inspected, no vio.lations or deviations were identified in four areas; one violation was found in one area.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. E. Smith, Station Manager
- J. T. McIntosh, Superintendent of Administration
- J. N. Pope, Superintendent of Operations
- C. T. Yongue, Station Health Physicist
- T. Barr, Performance Engineer
- R. J. Brackett, Senior Quality Assurance Engineer
- T. E. Cribbe, Licensing Engineer
- T. C. Matthews, Licensing Technical Specialist
- R. Rogers, Licensing Associate Engineer
- R. L. Gill, Licensing (General Office)
- D. Austin, Training and Safety C. C. Jennings, Licensing and Projects S. E. Spear, Health Physics Supervisor Other licensee employees contacted included five technicians and two office personnel.
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Other Organizations KMAC Contract Services RAD Services, Inc.
NUMANCO NRC Resident Inspector
- W. T. Orders
- D. P. Falconer
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on May 14, 1982, with those persons indicated in paragraph 1 above. The inspector discussed the apparent violation of Technical Specification, Section 6.4.1.g., Failure to Follow Radiation Control Procedures, in that Station Directive 3.8.23 requires all high radiation doors to be locked or guarded at all times except for entry and exit. The inspector informed licensee management that failure to lock a high radiation area door leading to The Radwaste Compacter Room would result in a notice of violation.
Licensee management acknowledged the inspectors finding.
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3.
Licensee Action on Previous Inspection Findings a.
(Closed) Infraction (78-11-02) Contrary to 10 CFR 20.203 a high radiation area surrounding a dewatered resin cask was not alarmed.
locked or directly surveilled. The inspector reviewed the licensee's response to this infraction. Written instructions were distributed to reiterate the required actions to be taken by Health Physics and security personnel in the control of high radiation areas.
The inspector concluded that this appeared to be adequate and had no further questions.
b.
(Closed) Unresolved Item (77-02-01) Audits of Radiochemistry.
The
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inspector discussed this requirement with licensee personnel and was informed that an audit was performed by NSRB as required by Technical Specification 6.1.3.1.
The inspector concluded this appeared to be
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i adequate and had no further questions.
c.
(Closed) Infraction (79-33-02) Failure to Follow Liquid Waste Proce-dures. The inspector reviewed the procedure revision of CP/0/B/100/2, Chemistry Action Guidelines; Steam Generator Sampling Section and concluded this appeared to be adequate to eliminate radioactive liquids from being disposed of in the sanitary waste system. The inspector had no further questions, d.
(Closed) Infraction (79-33-03) Failure to Review Modification of Steam Generator Sample Line Drain. The inspector was informed by a licensee representative that the temporary drain lines were removed and the sample flow routed correctly to the liquid waste system. The inspector
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concluded this appeared to be adequate and had no further questions.
e.
(Closed) Violation (81-04-03) Failure to Label Radioactive Waste. The inspector toured the facility auxiliary building and no discrepancies in the labeling of radioactive material were observed.
The inspector had no further questions.
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f.
(Closed) Unresolved Item (81-23-01) Effluent Grab Samples of Tritium.
The inspector reviewed the revision of the Unit Vent Sampling Proce-dure which requires weekly grab samples of tritium for each operating unit. The inspector concluded this appeared to be adequate and had no
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further questions.
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(Closed) Violation (81-23-02) Missing Gasket in Unit Vent Sample Apparatus.
The inspector reviewed the revision of the Unit Vent Sampling and Analysis Procedure, HP/0/B/1000/6D, which includes a reference for proper sampling apparatus arrangement (gasket and filter paper). The inspector concluded this appeared to be adequate and had no further questions.
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(Closed) Violation (81-23-03) Tritium Sampling and Report.
The Unit Vent Sampling Procedure was revised to include weekly grab samples of i
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tritium for each operating unit. The inspector concluded this appeared to be adequate and had no further questions.
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(Closed) Violation (81-23-04) Use of Out of Calibration Instruments.
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The inspector verified the use of within calibration instruments by observing the calibration due dates on numerous instruments in use.
The inspector concluded that no discrepancies were observed and had no further questions.
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(Closed) Violation (81-26-01) Failure to Perform Adequate Redundant Sampling When Discharge Effluent Monitors are Inoperable as Required by Technical Specification 3.9.7.
The inspector reviewed the revision to the Chemistry Sampling Procedure, CP/0/A/200/8, which reflected the new sample points when effluent monitors are inoperable.
The inspector concluded this appeared to be adequate and had no further questions.
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(Closed) Violation (81-26-02) Failure to Have Adequate Procedure for Sampling Condensate Storage Tanks Prior to Release as Required by
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Technical Specification 6.4.1.
This item is closed.
See item 3.j above.
1.
(Closed) Violation (81-28-01) Failure to Follow Certificate of Com-pliance on Spent Fuel Shipment to McGuire Nuclear Station USA /9010/B-D-F.
The inspector reviewed the procedure revision of OP/0/A/1510/10, Shipment of Spent Fuel Using NL1-1/2 Cask, identifying the correct connection of the vent and drain lines to V-1 and V-2.
The inspector concluded that this appeared to be adequate and had no further questions.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Health Physics Appraisal Inspector Follow-up Items i
a.
(Closed) IFI (80-31-06) Quality Control Checks of TLD Systems.
A licensee representative stated that several TLD's are exposed at
different levels of radiation on a periodic basis and sent to their Dosimetry Services group for analysis.
The inspector concluded this appeared to be adequate and had no further questions.
b.
(Closed) IFI (80-31-04) Upgrading General Employee Radiation Protection i
Training.
The inspector reviewed the licensee's study guide and attended part of the GET Training and determined the program appeared
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to be adequate. The inspector had no further questions.
c.
(Closed) IFI (80-31-08) Quality Control Check of Internal Monitoring System. The inspector reviewed the procedure revision of Body Burden Analyzer Syste n, HP/0/B/1000/67, which incorporates the quality control
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checks of.the Body Burden Analyzer on a periodic frequency. The i
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inspector concluded this appeared to be adequate and had no further questions.
d.
(Closed) IFI (80-31-10) Updating RWP's With Current Radiological
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The inspector reviewed the procedure revision of Initiation, Preparation, Issuance, and Use of the Radiation Work Permit
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(RWP) and Standing Radiation Work Permit (SRWP), HP/0/B/1000/104, which incorporates the appropriate measures to be taken to update RWP's if
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radiological conditions change significantly.
The inspector had no further questions, e.
(Closed) IFI (80-31-11) Establishment of Specific Requirements for Technicians to Serve in Responsible Positions. The inspector reviewed the procedure revision of Initiation Preparation, Issuance, and Use of the Radiation Work Permit (RWP) and Standing Radiation Work Permit, (SRWP), HP/0/B/1000/04, which allows technicians to stop work on RWP's or SRWP's if radiological conditions change significantly and addresses the authorized persons that can approve these RWP's and SRWP's before
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issuance. The inspector concluded that this appeared to be adequate and had no further questions, f.
(Closed) IFI (80-31-14), Verification of RM-14 Alarm Setpoints. The inspector reviewed the procedure revision of Daily Source Checks of RM-14's, HP/0/B/1005/07A, for the appropriate measures to be taken to
verify the proper alarm setpoints and actions taken necessary to
maintain the proper alarm setpoints. The inspector concluded that this appeared to be adequate and had no further. questions.
(Closed) IFI (80-31-25) Use of Ba-133 Measurements in Calibrating Effluent Monitors.
The inspector reviewed the procedure revision of Process Radiation Monitoring RIA-44 Vent Iodine Monitor, IP/0/A/360/1B, which eliminates the use of Ba-133 in the acceptance criteria of the calibration results.
The inspector concluded this appeared to be adequate and had no further questions.
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(Closed) IFI (80-31-27) Posting Current Protective Clothing Require-ments and Radiological Status of Work Areas. This item is closed. See item a.d above.
1.
(Open) IFI (80-31-07), Calibration of TLD System with Radiation Sources Similar to Those Expected Within the Plant.
The licensee has agreed with the goals of such a program, but is experiencing difficulty in
obtaining appropriate NBS (National Bureau of Standards) traceable
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sources in a timely manner.
This item will remain open until the program in implemented.
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(0 pen) IFI (80-31-21), Implementation Date of System ALARA Manual. A licensee representative stated that the manual was not yet fully implemented.
The following reasons and information were offered in i
explanation; the Manual is sweeping in scope and requires extensive
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change throughout the facility and its operation and staffing; the highest levels of management at Duke Power Company are concerned and committed to ALARA and all reasonable effort is being expended to implement this policy Manual.
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(0 pen) IFI (80-31-22), Review of Plant Procedures by' Health Physics Staff.
Plant Technical Specifications do not require a multi-disci-plainary review of all procedures at this time.
As a result the concerns of this item will not be addressed until the ALARA Manual implementation referenced above takes place.
1.
(0 pen) IFI (80-31-23), Isolation of Counting Room in the Event of High Airborne Radioactivity in Plant.
The licensee has investigated this problem and agrees to its validity.
Currently, procedures are under development to provide a counting facility outside the Auxiliary
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Building which would not be affected.
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(0 pen) IFI (80-31-26), Review of Fixed Monitor Calibration Procedures
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and Techniques. Some work in this area has been done by the licensee, but it is not complete. The licensee is in the process of obtaining the appropriate ANSI standards and will compare their requirements for applicability and practicality against current procedures.
6.
Licensee Actions on Previous Inspector Identified Items
a.
(Closed) IFI (79-35-05) Review of IE Notice 79-09 and Circular 79-21.
The inspector reviewed the licensee's response to IE Notice 79-09 and IE Circular 79-21, Spill of Radioactive Contaminated Resin, which included three areas of liquid waste transfers.
The inspector con-cluded the licensee's review appeared to be adequate and had no further questions.
b.
(Closed) IFI (79-35-06) Incorporate 10 CFR 71 Requirements Review in -
l Plant Procedure HP/0/A/1006/01. The inspector reviewed the revision to procedure HP/0/A/1006/01, Packaging and Shipment of Radioactive
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Material, to verify 10 CFR 71 requirements.
The inspector hs
'o further questions.
c.
(Closed) IFI (79-20-03) Qualification of Utility Operators.
The
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inspector reviewed Station Directive 3.1.40, Qualification of On Shift i
Non-Licensed Operators, for the appropriate measures to ensure
non-licensed operators are qualified in their assigned task.
The inspector concluded this appeared to be adequate and had no further questions.
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d.
(Closed) IFI (78-PC-03) Licensee's Practices for Personnel Neutron Dosimetry. The inspector reviewed Procedure for Personnel Neutron Dose
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Accountability, HP/0/B/1000/02/D, for appropriate measures and adequacy for controlling neutron exposures.
The inspector concluded this appeared to be adequate and had no further questions.
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e.
(Closed) IFI (81-11-01) Change Word " Extensive" in Station Directive 3.8.10 Concerning Self Frisk.
The inspector reviewed the procedure revision of Station Directive 3.8.10, Procedure for Use of Count Rate Meters and Portal Monitors, Section 4.1.2.3, to determine appropriate measures are included in the event personnel determine they are contami-nated. The inspector concluded that this appeared to be adequate and had no further questions.
7.
Shipment of Radioactive Material The inspector reviewed a radwaste shipment, Duke Power Company, Oconee Nuclear Station number 82-211, for Department of Transporation (DOT) ship-ping requirements.
The licensee was shipping low specific activity (LSA)
material to Chem Nuclear System, Inc. (CNSI) for burial.
The inspector concluded after his review of the Radioactive Shipment Record (RSR) and performance of independent measurements of the shipping containers and external dose rates of the shipping vehicle, the radwaste shipment appeared to meet all requirements of DOT.
8.
Instruments and Equipment The inspector observed a variety of radiological instruments (portable survey instruments, portal monitors, personnel friskers) in use and avail-able for use. The inspector checked calibration stickers, performed battery checks for selected portable instruments in the health physics office, and response checked selected portable instruments for proper operation.
The inspector discussed the radiation survey instrument calibration program, with licensee representatives. The inspector had no further questions.
9.
Posting, Labeling and Control
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The inspector toured all three units to ensure proper posting and labeling of contaminated areas, radioactive materials areas, radiation areas, and high radiation areas. The inspector performed independent measurements of radiation levels of selected radiation control areas and concluded that the posting, labeling and control appeared to be adequate with one exception discussed in paragraph 13.
10.
Respiratory Protection Program The inspector reviewed the respiratory protection program which included proper storage of full face respirators, monthly inspections of self con-tained breathing apparatuses (SCBA), hydrostatic tests of breathing air bottles, and issuance of respiratory equipment.
The inspector concluded that the respiratory protection program appeared to be adequate and had no further questions.
11.
Housekeeping Inside Containment The inspector reviewed procedure QCD-1, Housekeeping During the Operations Phase of Nuclear Stations, to evaluate the licensee's program for control of
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I loose material inside containment to keep sumps free and clear 50 that
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recirculation path would not be hindered under accident conditions.
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inspector concluded that the licensee's program appeared to be adequate and had no further questions.
12.
Control and Accountability of Lead Shielding The inspector reviewed Station Directive 3.8.25, Shielding of Piping and Equipment, to evaluate licensee's program for control and accountability of lead shielding on safety related equipment and verify that an engineering evaluation is required prior to installation of lead shielding. The inspec-ter concluded that they licensee's program appeared to be adequate and had no further questions.
13.
Radwaste Compactor Room On May 13, 1982 the inspector observed a high radiation area door, which leads to the Radwaste Compactor Room, elevation 796 in the Auxiliary Building to be open. Station Directive 3.28.23. Health Physics High Radia-tion Door Tour Procedure, requires this area, Radwaste Compactor Room number 304, elevation 796 in the Auxiliary Building, to be locked or guarded at all times except for entry and exit. Apparently the door closure device is not strong enough to allow the door to securely close when the radwaste truck bay roll up door is open during the loading of radwaste shipments.
A radiation survey performed by the licensee on May 13, 1982 revealed radia-tion levels of 500 mr/hr to 600 mr/hr contact and 80 mr/hr to 120 mr/hr at eighteen inches. The inspector stated that failure to keep the entrance to a high radiation area locked and to maintain positive control over each individual entry was a violation to Technical Specification 6.4.1.g; Failure to Follow Procedure (269/270/287/82-17-01).
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