IR 05000348/1979042
| ML19309C019 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 01/29/1980 |
| From: | Gibson A, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19309C001 | List: |
| References | |
| 50-348-79-42, NUDOCS 8004080043 | |
| Download: ML19309C019 (6) | |
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Report No. 50-348/79-42 Licensee: Alabama Power Co.
600 North 18th Street Birmingham, Alabama 35202 Facility Name: Farley License No. NPF-2 Docket No. 50-348 Inspection at Farley site near <;hford, Alabama Inspector:
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21[TO C. M. Hosey
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Date Signed
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App ved by:
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I[ENIO A. F. Gibson Date Signed
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SUMMARY Inspection on December 10-14, 1979 Areas Inspected This routine, unannounced inspection involved 35 inspector-hours onsite in the areas of the radioactive waste management program, including radioactive' effluent i
release reports, radioactive effluent release records, procedures for controlling
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the release of effluents; review of licensee action on IE bulletins and circulars
and followup on an unplanned gaseous release.
Results
i Of the six areas inspected, no items of noncompliance or deviations were identi-fied in five areas; one apparent item of noncompliance was found in one area -
Infraction Failure to follow procedures for reviewing maintenance work
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request paragraph 10.
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e DETAILS i
1.
Persons Contacted Licensee Employees
- W.
G. Hairston, III, Plant Manager
- C. D. Nesbitt, Chemistry / Health Physics Supervisor D. N. Morey, Maintenance Supervisor J. Carlington, Operations Superintendent
- H. W. Mitchell, Assistant C/HP Supervisor P. E. Farnsworth, Chemistry / Health Physics Foreman
- J. Walden, Chemistry / Health Physics Foreman W. R. Bayne, Chemistry / Health Physics Foreman L. S. Williams, Training Supervisor
- J. W. Kale, Jr., Quality Assurance Engineer D. DuBois, Shift Supervisor
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Other Licensee employees contacted included, five technicians, two operators, and three office personnel.
- Attended exit interview 2.
Exit Interview
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The inspection scope and findings were summarized on December 14, 1979, with those persons indicated in Paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings i
Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Radioactive Effluent Release Reports
Environmental Technical Specification 5.6.1.b requires, in part, that a report on radioactive effluents released from the site be submitted and that the report include a summary as outlined _ in Regulatory Guide 1.21, Revision 1, Appendix B.
The inspector reviewed the plant's Semiannual Radioactive Effluent Release Reports for the period of July 1978, through June 1979, and discussed the reports with a licensee representative. The inspector identified several inconsistencies in the ' report for the period of July 1978 through December 1978. A licensee representative stated that the data would be reviewed and an amended report submitted. The inspector
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stated that this item will remain open (348/79-42-03) pending receipt of the amended report.
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6.
Radioactive Effluent Release Monitoring and Records
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' Environmental Technical Specification 2.3.4 specified the sampling and monitoring requirements for radioactive material in gaseous effluents..The
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inspector reviewed selected Gaseous Waste Release Permits for 1979. During the review the inspector noted that part three of the release permit was not, fully-completed on'several of the release permits for 1979. The RM-14 set point values were not recorded. A. licensee representative stated a review of the form was in progress, and that the recording of the monitor set point. might be eliminated, since the set point is a constant. The-inspector stated that this item will remain open (348/79-42-02) pending
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followup at a later date.
7.
Radioactive Effluent Control Procedures -
The inspector reviewed changes made to the following effluent control
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procedures and verified that the changes were consistent with regulations
and Technical Specifications.
n FNP-0-RCP-474, " Mobile Solidification Unit Operation" a.
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FNP-0-RCP-58, " Waste Management"
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FNP-0-RCP-372, " Sampling Radiological Process Streams for Analysis"
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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.
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9.
Followup on I&E Bulletins and Circulars a.
Circular 79-21, Prevention of Unplanned Releases of Radioactivity.
Review of this circular by the licensee is still in progress. The f
inspector discussed.the licensee's preliminary review of the circular
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uith licensee representatives. The inspector stated that this item would remain open (348/79-42-04) pending completion of the review and followup by the inspector.
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Bulletin 79-19, Packaging'of Low-level Radioactive Waste for Transport and Burial. The inspector discussed Alabama Power Company's letter of
September.17, 1979, in response to the - subject bulletin and reviewed L
the specific actions taken by the licensee in response to the Bulletin.
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L (1) The inspector reviewed Biweekly. Corporate' Audit Report 79/17,
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-dated October 26,l1979, which reported the results of an audit of radioactive - waste control performed by theJ licensee's quality r
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-3-assurance staff between September 19, 1979 and October 12, 1979.
This audit specifically covered the areas recommended by the bulletin.
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(2) The inspector had the licensee open.one cask " ready for shipment" containing liquids solidified with urea formaldehyde and reviewed the licensee's methods of assuring that the cask contained no free liquid. The cask appeared to contain no free standing liquid or other materials that were not acceptable by the burial facility.
(3) The inspector reviewed the following procedures that had been revised to address the concerns of the bulletin:
(a) FNP-0-RCP-56, Shipment of Radioactive Material (b) FNP-0-RCP-57, Radioactive Material and Waste Handling (c) FNP-0-RCP-474, Mobile Solidification Unit Operation
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(d) FNP-0-RCP-58, Waste Management (e) FNP-0-AP-45, Training Plan
(4) The inspector selectively reviewed shipping records for radioactive material shipped out between September 1, 1979 and December 10, 1979.
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The inspector had no further questions concern 4.ng the licensee response to the bulletin.
f 10.
Licensee Action on Previous Inspector Identified Items a.
(Closed) Open Item (348/79-26-04) Temporary Shielding. Plant Procedure
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FNP-0-RCP-15 was issued on October 23, 1979, establishing the procedures for, evaluation, installation and accountability of all temporary shielding. The inspector had no further questions.
b.
(Closed) Open Item (348/79-11-04) Analysis of Breathing Air. Plant Procedure FNP-9-RCP-110, Sampling of Service Air to Meet Respiratory
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Limits, was issued on November 20, 1979. On September 18, 1979, the service air was analyzed and found to be within the limits established in RCP-110. The inspector had no further questions.
c.
(Closed) Open' Item'(348/79-21-04) Adding Self-Frisking and Dressing /
Undressing Procedures to Radiation Worker Training.
A licensee'
repretentative stated the necessary equipment and instruments had been procured and that practical exercises in self-frisking and dressing /
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removal of _ protective clothing had been used on a trial basis, and that beginning January 1, 1980, the practical exercises will.be a permanent part of - radiation worker training. The inspector had no further questions.
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d.
(Closed) Open Item (348/79-21-05) Review Procedures for Chemical Spills.
Plant Procedure FNP-0-RCP-7, Area and Material Decontami-nation, has been revised to add references, instructions, protective
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clothing requirements and cleanup methods for spills of chemicals.
The inspector had no further questions.
(Closed) Open Item (348/79-30-01) Training / Retraining of C/HP Technicians.
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Plant Procedure FNP-0-RCP-45, Training Plan, has been revised to specify the training / retraining frequency for C/HP technicians and to specify the subjects to be taught during the training. The inspector had no further questions.
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(Closed) Open Item (348/79-30-02) Hydrostatic Testing of Waste Transfer Lines. Plant Procedure FNP-0-RCP-474, Mobile Solidification Unit, has been revised to incorporate the hydrostatic testing of waste transfer lines whenever a line is disconnected an.d reconnected. The inspector had no further questions.
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(Closed) Open Item (348/79-30-05) Instrument Calibration Program. The
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licensee has received an enclosed instrument calibrator and is in the process of installing the system. This system should greatly reduce the radiation dose being received by personnel calibrating radiation survey instruments and should also improve the accuracy and precision of calibrations.
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The inspector had no further questions.
11.
Other Areas Inspected a.
The inspector reviewed an unplanned release of gaseous radioactivity which occurred on October 8,1979.
(1) Technical Specification 6.8.1 states that written procedures I
shall be established, implemented and maintained.
Plant Proce-dure FNP-1-AP-52, Equipment Status Control and Maintenance Authorizations, Paragraph 6.7 states that the releasing individual
. will review items 12 through 20 on the work request and will sign the " release for work" section only if the items are complete and ' accurate. Licensee representatives stated that the initial j
discussions between operations and maintenance concerning the repair of valve Q1G22V08SB involved the disassembly and repair of the valve. Maint mance Work Request 19749 called for the repair of the valve in accordance with FNP-0-MP-21.1.
Later in the discussions, operations informed the maintenance planners that the No. 8 Waste Gas Tank was pressurized and the valve cotld not be isolated from the tank. The scope of the work was changed to call for removal of the reach rod on the valve and to stroke the valve rather than to disassemble it. A Tagging Operations Order (establishes plant conditions) was prepared and the tank a'nd valve isolated from the remainder of the waste gas system. Tagging Operations Order No. 79-1671 issued October 4, 1979, stated that
- the purpose of the clearance was to " stroke #8 GDT inlet valve".
Immediately prior to the unplanned release, work request 19749
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-S-e was submitted to the shift foreman for review and release of the
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work request for work.
The work request was not revised and
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still called for the valve to be repaired in accordance with Plant Procedure FNP-0-MP-21.1.. The shift foreman signed the work request releasing the request for the performance of the work specified.
On October 8, 1979, while disassembling the No. 8 Waste Gas Tank inlet isolation valve (Q1G22V085B), the mechanic noticed gas being released from the valve bonnet. The bonnet was o
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retightened and the release secured. The inspector stated that
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failure of the individual releasing the work request to perform a i
thorough review of the work request to ensure that the plant conditions necessary for the work specified was in affect was in noncompliance (348/79-42-01) with Technical Specification 6.8.1.
(2) Based on an analysis of the gas in the tank and change in the tank pressure, it is estimated that, 17 millicuries of Krypton-85 were released to the building ventilation system. A review of the readout of data from the plant stack gas monitor, revealed that a small increase in count rate occurred on the monitor
during the incident, however, the count rate was only a small fraction of that which would be necessary to exceed the instant-aneous release limits specified in 10 CFR 20 for releases to an unrestricted area.
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(3) The inspector reviewed the results of air surveys taken in the auxiliary building and the results of internal monitoring for the individuals present in the ecom when the release occurred. The inspector had no questions concerning surveys taken or internal monitoring.
b.
The inspector reviewed the records of radiation and contamination L
surveys performed upon receipt of a 162 Curie Cesium-137 source in a Model 10008 Gamma Calibrator.
The plant's program for receiving
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radioactive material appears to be in compliance with 10 CFR 20.205.
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