IR 05000269/1981011
| ML15224A398 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/23/1981 |
| From: | Franklin L, Hosey C, Jonathon Puckett NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A397 | List: |
| References | |
| 50-269-81-11, 50-270-81-11, 50-287-81-11, NUDOCS 8107240418 | |
| Download: ML15224A398 (7) | |
Text
REGU 1 0UNITED STATES NUCLEAR REGULATORY COMMISSION REGION il 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-269/81-11, 50-270/81-11, and 50-287/81-11 Licensee:
Duke Power Company 422 S. Church Street Charlotte, NC 28242 Facility Name:
Oconee Docket Nos. 50-269, 50-270, and 50-287 License Nos. DPR-38, DPR-47, and DPR-55 Inspection at Oconee facility near Seneca, South Carolina Inspectors:
,
.
.7/
J. M. Puckett Date' Signed L. A. Frank Date Signed Approved by:
"
7,
'J3 C. M. Ho e, Acting S ction Chief
'ate Signed Technical Inspection Branch Engineering and Tec nical Inspection Division SUMMARY Inspection on May 26-29, 1981 Areas Inspected This routine, unannounced inspection involved 52 inspector-hours onsite in the area of HP appraisal finding Results Of the areas inspected, no violations or deviations were identifie PDR ADOCK 05000269 G
REPORT DETAILS Persons Contacted Licensee Employees
- J. E. Smith, Station Manager
- J. N. Pope' Superintendent Operations
- C. L. Thames, Health Physics
- C. T. Yongue, Station Health Physicist
- T. C. Matthews, Technical Specialist, Licensing Other licensee employees contacted included five technicians Other Organizations
- F. B. Foster, Institute for Nuclear Power Operations (INPO)
- T. L. Cellmer, INPO
- A. S. Bunker, INPO NRC Resident Inspector
.
- Jape
- W. T. Orders
- Attended exit interview Exit Interview The inspection scope and findings were summarized on May 29, 1981 with those persons indicated in paragraph 1 above. The inspector thanked the licensee representatives, for their cooperation in the inspection and noted that it must have been a difficult week with both INPO and the NRC inspecting the facility simultaneousl The Station Manager made a commitment to the inspectors regarding concerns about personnel contamination action levels for HP notificatio This is fully explained in Section 5 of the detail.
Licensee Action on Previous Inspection Findings (Closed)
Infraction (80-31-17),
Failure to Follow Procedure This item concerned potentially radioactive tools, equipment, or waste and the failure to wrap, bag, tag or identify the equipment when it was removed from the work area where it was use The inspectors toured the facility auxiliary building and no discrepan cies in the labelling and containment of radioactive material were observed. In the areas inspected, the housekeeping in general was observed to be well above averag (Closed)
Infraction (80-31-19),
Failure to Perform Safety Evaluatio This item refers to the placement of lead shielding on seismic classi fied safety systems without evaluation of the impact of associated static and dynamic loads the extra weight would demand during system operation. During the tour, the inspectors noted no instance where lead shielding had been improperly utilized. The licensee also has an approved procedure which provides (1) assessment of loading, (2)
contains criteria for shielding use, and (3) a surveillance program for installed shieldin.
Licensee Action on Previous Inspector Identified Items (Closed)
Inspector followup item (IFI)
(80-31-01),
Inconsistencies Between Station Procedures and the System Health Physics Manua The Station Health Physicist informed the inspectors that as procedures are revised or originally written a copy is now sent to the Corporate Health Physics Office for review and comment as to its adequacy and consistency prior to its implementation at the facilit This will result, in time, in all procedures receiving such a review. In addi tion, the Corporate Health Physics Staff will be performing informal reviews on their own initiative towards achieving the same goal (Closed)
IFI (80-31-02),
Address Audits Performed by System Health Physics Staff to Station Manage The inspector was shown a recent System Health Physics Audit and it was addressed to the Station Manage (Closed) IFI (80-31-03), Verification of the Qualifications of Vendor Supplied Health Physics Technicians. The licensee's Corporate Office now performs a verification check on the resumes of vendor-supplied HP technicians. The inspector examined a recent verification and noted that the qualifications of four individuals had been questioned by the licensee. The vendor was notified by the licensee that three of these individuals would not be accepted and had requested additional informa tion on the fourth. This program appears adequate to protect against unqualified personnel being given responsibilities when they are not qualified in accordance with the-Technical Specification ANSI N1 requirement (Open) IFI (80-31-04), Upgrading General Employee Radiation-Protection Training. A licensee representative stated to the inspectors that the Duke Power Company System General Employee Radiation Protection
Training Program was being revised in its entirety and that the con cerns from IE Report 80-31 were under evaluation for inclusion in this revision. This item will remain open until the completion and imple mentation of the revisio (Closed)
IFI (80-31-05),
High Dose Range Reading Capability of the Thermoluminescent Dosimeter (TLD)
Syste The licensee has, via a study performed by the University of Michigan, found that there is good agreement and linearity by the present Teledyne 9100 system up to the 700 rad dose leve Excellent agreement is found up to 100 rad. The licensee plans to extend testing to 1000 rad dose at the next testing interva The inspectors had no further question (Open)
IFI (80-31-06),
Quality Control Checks of TLD Syste The licensee has decided to implement a "blind check" of TLD badges, but formal procedures have not yet been written and approve This item remains open until the check system is institute (Open)
IFI (80-31-07), Calibration of TLD System with Radiation Sources Similar to Those Expected Within the Plan The licensee has agreed with the goals of such a program, but is experiencing difficulty in obtaining appropriate NBS (National Bureau of Standards)
traceable sources in a timely manne This item will remain open until the program is implemente (Open)
IFI (80-31-08),
Quality Control Check of Internal Monitoring System. The licensee has instituted a plan for all of Duke Power Company's nuclear facilities to perform this chec Details of how this will be accomplished have not yet been determine (Closed)
IFI (80-31-09)
Storage of Respirator The licensee has examined this problem and has determined it is unfeasable to change the system as established. The original problem was centered around the potential for accidental cross-contamination of clean respirator Since no incident of this type has been observed, this appears to not be a significant concer (Open)
IFI (80-31-10),
Updating Radiation Work Permits (RWPs)
With Current Radiological Informatio The inspectors were shown a new form intended for inclusion in the RWP procedur This procedure is currently under revision and the change appears to adequately address this proble (Open)
IFI (80-31-11),
Establishment of Specific Requirements for Technicians to Serve in Responsible Position As a temporary measure, the licensee has issued a memorandum to the Operating Health Physics Supervisors instructing them to ensure only ANSI N18.1 qualified
personnel shall write RWPs and set radiological protection requirements for work. The RWP procedure revision addressed in paragraph 4.j. of this report includes this requiremen (Closed)
IFI (80-31-12),
Establish RM-14 Frisker Response Check Criteria. Licensee procedure, "Procedure for Daily Source Check of the RM-14 and RM-15 Beta-Gamma Radiation Monitors",
HP/0/B/1005/07A, properly outlines the technique for source check of these instrument The licensee believes that the technician who provided information to the inspector at that time merely failed to communicate his knowledge of this procedure adequately to the inspector and did in fact know the requirement (Closed)
IFI (80-31-13),
Policy Concerning Notification of Health Physics of all Personnel Contaminatio This item relates to the statement in the licensee's General Employee Radiation Protection Training that individual radiation workers should attempt self decon tamination prior to notifying H This item is discussed further in paragraph 5. of this repor (Open)
IFI (80-31-14),
Verification of RM-14 Alarm Setpoint The licensee is still seeking a solution to the problem of how to ensure the alarm setpoints on these instruments can be consistently set at a realistic level and maintained at that poin Some of the problems encountered are (1) varying background levels and the attendant false alarms, (2) unauthorized change of the setpoint due to easy accessi bility of the adjusting knob, and (3) determination of appropriate leve.
(Closed)
IFI (80-31-15),
Conversion to HP-210 Probe for Personnel Monitorin The licensee stated that personnel monitoring is now accomplished using thin-window detectors of the HP-210 typ (Closed) IFI (80-31-16), Improved Sensitivity of Portal Monitors. The'
licensee has adjusted the count time on portal monitors and achieved a 20% increase in sensitivit Self frisking is regarded as being the primary means of personnel contamination according to licensee repre sentatives. Portal monitors are regarded as a backup check at this facilit (Closed) IFI (80-31-18),
Personnel Contamination Monitorin Personnel contamination monitoring is discussed further in IE Report 269/270/
287/81-0 (Closed)
IFI (80-31-20),
Solid Radioactive Waste Volume Reduction Training for Station Staf Solid radwaste volume reduction training is being incorporated in the upgraded general employee training discussed in paragraph 4.d of this repor (Open) IFI (80-31-21), Implementation Date for System ALARA Manual. A licensee representative stated that the manual was not yet fully implemented. The following reasons and information were offered in explanation; the Manual is sweeping in scope and requires extensive 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 Manua (Open)
IFI (80-31-22),
Review of Plant Procedures by Health Physics Staff. Plant Technical Specifications do not require a multi-disci plinary review of all procedures at this tim As a result, the concerns of this item will not be addressed until the ALARA Manual implementation referenced above takes plac (Open) IFI (80-31-23), Isolation of Counting Room in the Event of High Airborne Radioactivity in Plan The licensee has investigated this problem and agrees to its validity. Currently, procedures are under development to provide a counting facility outside the Auxiliary Building which would not be affecte (Closed)
IFI (80-31-24),
Replacement of Internal Check Sources for Fixed Area Monitor New sources were being installed during the course of this inspectio (Open)
IFI (80-31-25),
Use of Ba-133 Measurements in Calibration Procedures and Techniques. IE Report 80-31 explains that the Ba133 measurement made during the course of the calibration of RIA 48 was in error by a factor of 20, yet there was no procedural action statement to resolve this erro The licensee has investigated this situation and found that one of a pair of mylar windows was missing from the detecto This condition was corrected and action level statements are being added to the calibration procedur (Open)
IFI (80-31-26),
Review of Fixed Monitor Calibration Procedures and Techniques. Some work in this area has been done by the licensee, but it is not complet The licensee is in the process of obtaining the appropriate ANSI standards and will compare their requirements for applicability and practicality against current procedure (Open)
IFI (80-31-27), Posting Current Protective Clothing Requirements and Radiological Status of Work Areas. This item is addressed in the RWP procedure change discussed in paragraph 4.j of this repor (Closed) IFI (80-31-18),
Perform Safety Evaluation of Auxiliary Boile The inspector was shown a safety evaluation dealing with this topi *
It appeared adequat.
Personnel Contamination Reporting Enclosure 5.1 to Station Directive 3.8.10 requires personnel to notify Health Physics when a self-frisk for contamination reveals levels in excess of 200 counts per minute. The Directive, in paragraph 4.1.2.3 states that if contamination is "extensive" then HP should be informed prior to self decontamination. Due to the potential in such cases for the possibility of significant skin dose, this statement is unacceptabl CFR 20.101 states regulatory limits for skin dose, and 10 CFR 20.201 requires the licensee to evaluate such dose. The licensee's Technical Specifications require this type of evaluation to be performed by an individual qualified to the level stated in ANSI N18.1, a level of qualification not normally achieved by most radiation workers. The Station Manager committed to the NRC at the exit interview on May 29, 1981 that the word "extensive" would be changed to an appropriate value. This value would be assigned after an evaluation, as required by 10 CFR 20.201, was performed. This is an open item (IFI 269/
270/287/81-11-01).
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