IR 05000348/1978031
| ML19305A147 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/05/1978 |
| From: | Gibson A, Hosey C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305A144 | List: |
| References | |
| 50-348-78-31, NUDOCS 7901040190 | |
| Download: ML19305A147 (6) | |
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Report No.:
50-348/78-31 Docket No.
50-348 License No.: NPF-2 Licensee: Alabama Power Company
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Post Office Box 2641 Birmingham, Alabama 35291 Facility Name: Farley Unit 1 Inspected at:
Farley Site, Ashford, Alabama Inspection conducted: November 13-17, 1978 Inspector:
C. M. Hosey W 5/ [
Reviewed by:
A. F. Gibson, Chief Date Radiation Support Section Fuel Facility and Materials Safety Branch Inspection Summary Inspection on November 13-17, 1978 (Report No. 50-348/78-31)
Areas Inspected: Routine, unannounced inspection of radioactive waste management program, including radioactive effluent release monitoring and records and reactor coolant water quality; review of IE Circulars and Bulletins and follow-up on previously identified items. The inspection involved 36 inspector-hours on-site by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
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RII Rpt. No. 50-348/78-31 I-1 DETAll.S I Prepared by:_
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N C. M. Hosey, Radiat ion Specialist Date Radiation Support S ection Fuel Facility and Materials Safety Branch Dates of Inspection:
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- 13-17, i978
/d, N Reviewed by:
I A. F. Gibson, Chief
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Date Radiation Support Section Fuel Facility and Materials Safety Branch 1.
_Indivi?.2als Contacted
- W. G. Hairston, Plant Manager
- J. Woodard, Assistant Plant Manager
- C. D. Nesbitt, Chemistry and Health Physics Supervisor
- M. W. Mitchell, Assistant C&HP Supervisor
- P. E. Farnsworth, C&hP Foreman
- J. Walden, C&HP Foreman
- R. Bayne, C&HP Foreman J. Thomas, I&C Supervisor
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2.
Licensee Action on Previous Inspection Findings (Closed) Open Item (50-348/78-18-01, Personnel a.
Neutron Dosimetry The inspector reviewed the status of providing a device to measure personnel neutron doses rather than estimating doses by using time in the area and neutron exposure rates.
The licensee has elected to have the commercial 71.D service used by the licensee evaluate the TLD's for neutron exposure in addition to gama exposure.
Positive neutron indications neutron response is greater than 10 percent of gamma response) (will be reported to the licensee as neutron response in counts.
The neutron response must be multiplied by a calibration factor to obtain a dose equivalent value.
A licensee representative stated that the plant will be determining the appropriate calibration factor within the next few weeks.
The licensee representative also stated the use of this personnel neutron dosimetry system would begin during the first quarter of 1979.
The inspector had no further questions.
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RII Rpt. No. 50-348/78-31 I-2 l
b.
(Closed) Open Item (50-348/78-18-02), Recording Actual Periods of Exposure on Form NRC-5 The inspector reviewed the monthly dosimetry report (Form NRC-5 equivalent) and verified that the actual periods of exposure are being entered on the report.
The inspector had no further questions.
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c.
(Closed) Open Item (50-348/78-26-06), Discrepancy in Volume of Liquid Radioactive Waste Released as Determined by Flow Totalizer During a review of this item, the inspector was informed by a licensee representative that the value recorded on the liquid waste release form as " gallons released by totalizer" was not actually gallons released.
Tb recorded value should be multiplied by a conversion factor of 20.
When this conversion factor was applied to the net totalizer reading recorded on several liquid waste release permits, good agreement between gallons released as determined by change in tank volume and flow totalizer was obtained. The inspector had no further questions.
d.
(Closed) Open Item (50-348/~8-26-05), Errors in Semi-Annual Radioactive Effluent Release Report The inspector reviewed a ievised semi-annual Radioactive Ef fluent Release Report for the period of January 1 through June 30, 1978.
The revised report was sent to the NRC on November 2, 1978. The errors in the original report had been corrected. The inspector had no further questions.
e.
(Closed) Unresolved Item (50-348/78-26-03), Records of Prerequisite Tests of Air Filtration Systems The inspector reviewed the records of testing of air filtration systems. This item is discussed further in Paragraph 3.
3.
Testing of Air Filtration Systems This ites was originally discussed in IE Report 50-348/78-26 and concerns the testing of air filtration systems. The inspector reviewed the documentation for in place testing and the appropriate prerequisite testing for the control room recirculation filter units, control room filter units, i"ntrol room pressurization filter units and the penetration room filtration system.
The test data was
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RII Rpt. No. 50-348/78-31 I-3 organized as specified in ANSI N510-1975, Testing of Nuclear Air-Cleaning Systems".
During the review, it was noted that the prerequisite tests required by Steps 8.3.1.5, 8.3.1.6 and 9.4.4 of ANSI N510 were not performed.
The inspector discussed the prerequisite tests specified in ANSI N510-1975 with license representatives. Licensee management stated that those prerequisite tests recommended by the architectual engineer and their ventilation system consultant would be performed even thougfi the tests were not required by Technical Specifications. The inspector identified this as an open item (348/78-31-01).
4.
Effluent Release Monitoring and Records a.
Environmental Technical Specification 2.3.4 specifies the sampling and monitoring requirements for radioactive material in gaseous effluents.
The inspector observed the sampling and analysis of a gaseous sample taken from the containment purge effluent stream and verified that the sample was taken and analyzed in accordance with plant procedures and Technical Specifications. The inspector reviewed selected Gaseous Waste Release Permits for 1978. Sampling and monitoring of radioactive material in gaseous effluents are apparently being performed in accordance with plant procedures and Environmental Technical Specifications.
b.
Technical Specification 4.3.3.1 requires that each radiation monitoring instrumentation channel be demonstrated operable by the performance of checks, tests and calibrations at the frequencies specified in Table 4.3-3.
The inspector rerewed the results of the channel check (For October, 1978), channel functional test (For September and October,1978) and the last two channel calibrations for plant vent gas monitors (RE-14 and RE-22)
and verified that the surveillance requirements of the Technical Specifications are being complied with. The inspector observed a check of the alarm / trip setpoints for RE-14 and RE-22 and verified that the setpoints for the plant vent gar monitors were properly set.
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c.
Environmental Technical Specification 2.3.4.f requires that the l
oxygen analyzers in the waste gas decay system be set to limit the
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concentration at the recombiner discharge to less than four
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percent by volume.
The inspector observed the readout of the analyzer and verified that the oxygen level was less than four percent by volume on November 11, 1978.
The inspector also reviewed records for the daily channel check, monthly functional
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O RII Rpt. No. 50-348/78-31 I-4 test and the quarterly calibration and verified plant procedures and Technical Specifications are being complied with.
The inspector had no further questions.
5.
Reactor Coolant Water Quality Through discussions with a licensee representative and review of records for October and November, 1978, the inspector verified that sampling and analysis frequency and the resultant data appeared to meet the requirements of Technical Specifications 4.4.7 (reactor coolant chemist ry), 4.4.8 (reactor coolant specific activity) and 4.7.1.4 (secondary coolant system specific activity).
6.
Whole Body Counting Procedures The inspector discussed with a licensee representative the frequency of performing whole body counts on individuals who have access to the radiation controlled arca. The licensee representative stated that plant policy was to perform a whole body count of individuals who have performed work where there was a potential for uptake of radioactive material. This count is performed at the conclusion of the work. In addition, counts are performed of individuals who become contaminated with radioactive material or who are exposed to airborne radioactivity.
The licensee representative stated that periodic analysis of all individuals who have access to the controlled area will be added to plant procedures. Although the frequency has not been established, the licensee representatives stated it would probably be annually. The inspector had no further questions.
7.
IE Circulars and Bulletins a.
Bulletin 78-07, " Protection Afforded by Air-Line Respirators and Supplied-Air Hoods".
The inspector discussed Alabama Power's letter of August 8, 1978, in response to the subject bulletin.
Air-line or supplied-air respirators operated at the demand mode are not used at Farley. A MESA-NIOSH (TC-19C-70) approved sof tcap
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hood respirator unit is used. A protection factor of 2000 is used j
for this respirator. The inspector had no further questions.
b.
Bulletin 78-08, " Radiation Levels from Fuel Element Transfer Tubes".
The inspector discussed Alabama Power's letters of August 8,1978 and November 1,1978, in responsa to the subject bulletin. The access port adjacent to the fuel ttstrfer tube will be completely filled by solid concrete blocks.
In addition, a special radiation survey will be conducted during the April 1979
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i RII Rpt. No. 50-348/78-31 I-5 refueling outage to identify any streaming problems.
The inspector had no further questions.
8.
Exit Interview The inspector met with management ' representa,tives (denoted in paragraph 1) on November 17, 1978, and summarized the scope and findings of the inspection.
The plant manager agreed to review prerequisite test for air filtration systems required by ANSI N510-1975, but not performed with architectual engineer for the plant and the ventilation system consultants and either perform the test recommended or have the consultants provide technical justification for not performing the test.
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