IR 05000348/1979030
| ML19210E173 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/17/1979 |
| From: | Gibson A, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19210E171 | List: |
| References | |
| 50-348-78-30, NUDOCS 7911300655 | |
| Download: ML19210E173 (7) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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.E REGION 11
o 101 MARIETTA ST., N.W.. SUITE 3100 k
ATLANTA, GEORGIA 30303
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Report No. 50-348/7)-30 Licensee: Alab.ma Power Company 600 North 18th Street Pirmingham, Alabama 35202 Facility Name: Farley Nuclear Plant Licen.se No. NPF-2 Inspectionat(arleyNye ar Site near Dothan, Alabama Inspected by:
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C. M. H6shp
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Date Signed
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Approved by:
/0//7/71 A. F. Gibson,' Sect' n Chief, FFMS Branch Date Signed SUMMARY Inspection on September 10-14, 1979.
Areas Inspected This routine, unannounced inspection involved 39 inspector-hours onsite in the areas of radiation protection program, including licensee audits, posting, labeling and control of radiologically controlled areas and material, training, instruments and equipment, posting of notices and notification and reports; followup on Bulletins, Circulars and Notices; and followup on previously identified items.
Resul*s Of the 9 areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Pereon Contacted Licensee Employees
- W. G. Hairston, III, Plant Manager
- J. Woodard, Assistant Plant Manager K. W. McCracken, Technical Services Superintendent
- C. D. Nesbitt, Chemistry / Health Physics Supervisor
- M. W. Mitchell, Assistant Chemistry / Health Physics Supervisor
- P. E. Farnsworth, Chemistry / Health Physics Foreman
- J. Walden, Chemistry / Health Ph sics Foreman f
P. Patton, ALARA Engineer W. Cooley, Plant Security L. S. Williams, Training Supervisor J. Kale, Jr., Quality Assurance Engineer Other licensee employees contacted included 2 construction craftsmen, 4 technicians, 1 operator, 2 mechanics, and 3 office personnel.
Other Organizations W. Pynes, Supervisor, Peabody Testing Company L. Masters, Chief of Security, Daniel Construction Company
- Attended exit interview.
2.
Exit Interview The inspection scope and findings were summarized on September 14, 1979, with those persons indicated in Paragraph I above.
In addition, a telephone conversation was held with the plant manager on October 3, 1979.
3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved (50-348/79-11-02) Qualification of Chemistry / Health Physics Technicicas. An interpretation of regulatory requirements by the NRC, concluded that it was acceptable to define a working year as 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> for the purpose of determining if a licensee's employee meets the minimum experience requirements of ANSI N18.1-1971.
It is also permissible to include overtime hours when determining the experience an employee may be credited with. The C/HP Technicians in question, had in excess of 4000 hours0.0463 days <br />1.111 hours <br />0.00661 weeks <br />0.00152 months <br /> experience required by the ANSI standard. The inspector had no further questions.
(Closed) Noncompliance (50-348/79-21-02) Inadequate Posting of Radiation Area. The inspector reviewed the corrective action taken in responae to this item and had no further questions.
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(Closed) Noncompliance (50-348/79-21-01) Inadequate Design Control of Drains. The inspector reviewed the corrective action taken in response to this item and had no further questions.
(Closed) Noncompliance (50-348/79-21-03) Failure to Comply with Health Physics Procedures.
The inspector reviewed the corrective action taken in response to this item and had no further questions.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Licensee Audits The inspector discussed the audit program related to radiation protection and radioactive waste management with a licensee representative and reviewed the following audit reports:
OQA AUDIT REPORT 79-6, dated April 20, 1979, Respiratory Protection Equipment (Plant Procedure FNP-0-RCP-101)
PQAE AUDIT REPORT 78-15, dated November 15, 1978, Radioactive Material Inventory and Control.
0QA AUDIT REPORT 79-1, dated January 22, 1979, Radioactive Waste Disposal Prog ram.
The inspector evaluated the frequency, scope and followup actioe of radiation protection related audits and had no questions.
6.
Training Technical Specification 6.4 states that a retraining and replacement a.
training program for the facility staff shall be maintained and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971. ANSI 18.1-1971 states that a training program shall be established which maintains the proficiency of the operating organi-zation. Plant Procedure FNP-0-AP-45 " Training Plan" states that the normal frequency for C/HP technician training is annually. Appendix F and G of FNP-0-AP-45 specifies the scope of the training.
b.
The inspector discussed the training / retraining program for C/HP tech-nicians with a licensee representative and reviewed the training records of selected C/HP technicians. During the review of training records, the inspector noted that one technician had not received the training specified in Table 1 of Plant Procedure FNP-0-AP-45 since joining the staff in May 1977 and another technician had not received the specified training since April 1978. A licensee representative stated that the plant had intended to conduct the training for all C/HP technicians in fall 1978, however, the maintenance outage fol-lowed by the extended refueling outage this year had prevented the 1437 213
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-3-completion of the training for all personnel. He further stated that the annual retraining requirement was deleted from Procedure FNP-0-AP-45 in February 1979.
The inspector stated that maintaining the proficiency of C/HP technicians without conducting retraining at least annually was questionable. The inspector also reviewed the results of a written test on health physics, radiation and contamination control and health physics instruments given to four C/HP technicians prior to receiving retraining. All of the individuals failed to obtain a grade of 70% or better on at least one of the areas examined.
Three failed to receive a grade of 70 in two areas. The inspector stated that this is further evidence that frequent training is not only desirable, but necessary to maintain the proficiency of the technicians.
A licensee representa-tive stated that the licensee was committed to a strong C/HP technician training program and that the retraining of technicians would begin this fall. The plant manager stated that plant procedures would be revised to require completion of the initial training of new C/HP technicians in three years. Provisions will also be made to exempt part of the training : f an individual has had formal training in the He also stated that each C/HP technician will receive retraining area.
at least every two years. The inspector stated that this item would remain open (348/79-30-01) pending change of plant procedures.
7.
Instruments and Equipment The inspector observed a variety of radiological instruments (portable a.
survey instruments, portal monitors, personnel friskers, pocket dosimeters)
in use and available for use, checked calibration stickers, performed battery checks for selected portable instruments in the health physics office, and selectively examined calibrations records for survey instruments in use. The inspector discussed the radiation survey instrument calibration program with licensee representatives.
b.
The inspector examined the following procedures:
FNP-0-RCP-201, " Calibration and Control of Portable Health Physics Instruments" FNP-0-RCP-328, " Operation and Calibration of Staplex High Volume Air Sampler" FNP-0-RCP-253, " Operation and Calibration of Eberline Portal Monitors PMC-4B and PMP-4B.
FNP-0-RCP-1, " Schedule of Health Physics Activities" The inspector examined records of the radiation dose to one technician c.
who calibrated portable survey instruments and noted a whole body dose of approximately 600 millirem directly attributable to instrument calibration. The inspector questioned whether the dose was being maintained as low as reasonably achievable.
Licensee representatives stated that they had recognized the need for an improved calibration 1437 214
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-4-system to reduce radiation doses and to improve the accuracy and precision of calibrations.
The inspector stated that prompt actions should be taken to reduce the radiation dose received by technicians and te improve the technical aspects of instrument calibrations. The inspector further stated that the licensee should consider following the recommendations of ANSI N323-1978 " Radiation Protection Instrumen-tation - Test and Calibration". The plant manager stated that a review of the instrument calibration program would be conducted, and appropri-ate action taken. The inspector stated that this item would remain open (348/79-30-05) pending completion of the review.
8.
Posting, Labeling and Control The inspector reviewed the licensee's posting and control of radiation areas, high radiation areas, airborne radioactivity areas, contamination areas, and radioactive material areas and the labeling of radioactive material during tours of the plant. No items of noncompliance or deviations were observed.
9.
Notification and Reports The inspector reviewed the licensee records to determine if exposure a.
data had been provided to terminated employees as required by 10 CFR 19.13(d). The inspector selected several names of recently terminated employees and verified that each employee had been sent a letter regarding his exposure history. The inspector had no further questions.
b.
The inspector discussed with a licensee representative the reporting requirements of 10 CFR 20.402, 10 CFR 20.403 and 10 CFR 20.405 and 10 CFR 20.408 and reviewed plant records. No items of noncompliance or deviations were identified.
10.
IE Notices, Circulars and Bulletins a.
Information Notice 79-07, Rupture of Radwaste Tanks.
The inspector reviewed the licensee's evaluation of the potentia; for a radioactive waste tank rupture at this plant. Although, the waste concentration system tank is designed for atmospheric pressure and the waste evapora-tor concentrate pump develops a dead head pressure of 85 psig, both the vent and the siphon breaker line would have to plug to overpres-surize the tank.
Both vent and siphon breaker lines are heat traced.
The problem of chlorides entering the aerated waste system is minimal due to the source of the water. The inspector had no further questions.
b.
Information Notice 79-09, Spill of Radioactively Contaminated Resin.
The waste transfer line from the plant's waste system to the mobile solidification unit is either stainless steel pipe or steel braided hose. The plant's process control procedure (PCP) manual addresses all the concerns listed in the notice with the exception of hydrostatic testing of the waste transfer line. Three hydrostatic testing flanges have been installed to facilitate testing of the line. The process 1437 215
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-5-control procedure manual will be revised to require hydrostatic test-ing of the waste transfer line whenever the line is disconnected and reconnected. This will remain an open item (348/79-30-02) pending revision of the PCP.
Circular 79-09, Occurrences of Split or Punctured Regulator Diaphragms c.
in Certain Self-Contained Breathing Apparatus.
The inspector discus:<d the Circular with a licensee representative.
The licensee does not use either the Scott Air Pak II/ IIA or the Presur-Pak II/ IIA. Plant procedures have been revised to include periodic inspection of the diaphragm for the self-contained breating apparatus (MSA Model 401 pressure demand) in use.
The inspector had no further questions.
d.
Circular 79-15, Bursting of High Pressure Hose and Malfunction of Relief Valve and "0"-ring in Certain Self-Contained Breathing Apparatus.
The SurvivAir Mark I SCBA is not used by the licensee. The inspector had no further questions.
11.
Other Areas Inspected The inspector toured the licensee's sanitary landfill and scrap yard a.
and performed independent radiation surveys to determine if radioactive material had been disposed of in uncontrolled areas. No radioactive material was found during the survey. During the tour of the landfill, the inspector found yellow gloves (radiation symbol affixed), glove liners and yellow plastic shoe covers used for contamination control.
The gloves were surveyed by the inspector and a licensee representative and found to be free of radioactive contamination. A licensee repre-sentative stated that the clothing was probably used for handling chemicals or cleanup of Unit 2 Auxiliary Building following an overflow of a sanitary tank temporarily installed on the 100 foot elevation.
The plant manager stated that action would be taken to restrict the use of specifically marked anti-contamination clothing to radiological control applications.
This will remain an open item pending followup by an inspector (348/79-30-03).
b.
The inspector discussed with a licensee representative the plant's policy concerning whole body counts for individuals terminating em-ployment or work assignment at the plant. The licensee representative stated it was the plant's policy to give every individual a whole body count pric to termination; however, some individuals fail to notify Health Physics that they are terminating. Therefore, no whole body count is performed. The inspector selectively reviewed the personnel dosimetry file for individuals who terminated employment or work assignment at the plant between May 1, 1979 and August 1, 1979. Four records reviewed did not include termination whole body count. Two of the individuals failed to notify the health physics group that they were terminating and two individuals refused to remain at the plant for a whole body count. The four individuals were not permanent plant employees.
It should be noted that none of the individuals entered areas of the plant that would have required the use of respiratory 1437 216
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-6-e protection equipment because of airborne radioactivity.
The inspector had no further questions concerning whole body counts The inspector reviewed the results of a radiation survey performed c.
during the initial transfer of spent fuel through the fuel transfer tube. Radiation levels ranged from 10/R Hr at the cork seam between f
the reactor building and the auxiliary building adjacent to the fuel transfer tube on the 112' elevation to 120 R/Hr at the same seam on the 100' elevation.
.1 licensee representative stated that access to the high radiation areas was not permitted during subsequent fuel transfers and that a letter (FNP-79-0473, dated April 10, 1979) had been sent to the Architectural Engineering firm for the plant request-ing that permanent shielding for the fuel transfer tube be designed.
The inspector stated that this item vill remain open pending modifi-cation of the shielding (348/79-30-04).
12.
Licensee Action on Previous Inspector Identified Items (0 pen) Open Item (50-348/79-26-04) Temporary Shielding.
This item has a.
been previously discussed in IE Reports 50-348/78-26 and 50-348/79-11 nd concerns the installation of temporary shielding on safety-related
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plying. The licensee's architectural engineering (AP) firm has provided the 'icensee with specific requirements for temporarily shielding of pip Ng in three systems. A licensee representative stated that a procedure would be prepared and issued within 60 days which will include the specific shielding requirements and which would prohibit the installation of shielding on any other system until a safety evaluation has been performed. This item will remain open pending issuance of the procedure.
b.
(Closed) Open Item (50-348/79-11-01) Helath Physics Review of Main-tenance Procedures. The licensee's health physics group is now re-viewing maintenance procedures and changes. The inspector had no further questions.
c.
(Closed) Open Item (50-348/79-11-03) Storage of Respirators.
The inspector observed that respirators are now being stored on shelves in a manner such that they are not damaged by adjacent equipment or twisted out of their normal configuration. The inspector had no further questions.
13.
Posting of Notices 10 CFR 19.11 requires, in part, that each licensee post current copies of 10 CFR 19 and 10 CFR 20 or if posting of the documents is not practicable, the licensee may post a notice which describes the document and states where it may be examined.
10 CFR 19.11 further requires that copies of any Notice of Violation involving radiological working conditions be conspicuous-ly posted within two working days after receipt of the documents from the Commission. The inspector observed the posting of notices required by 10 CFR 19.11 and had no questions.
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