IR 05000285/1982004
| ML20050B112 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 03/24/1982 |
| From: | Randy Hall, Holley W, Murray B, Wilborn L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20050B107 | List: |
| References | |
| 50-285-82-04, 50-285-82-4, NUDOCS 8204050012 | |
| Download: ML20050B112 (10) | |
Text
.
.
APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
,
Report:
50-285/82-04 License:
Docket:
50-285
,
l Licensee: Omaha Public Power District (0 PPD)
l 1623 Harney Street Omaha, NE 68102 Facility: Fort Calhoun (FC)
Inspection Conducted:
February 22-26, 1982
,
Inspectors:
/
.
b
82_
'
Lorenzo W, orn, Radiation Specialist Date
-
ak
.
ok/rt
'
We'slef L. glley, Radiation ecialist Date '
'
Reviewed: eq,
~
'
R.E. Hall,gief,ReactorProjectSectionC Date Approved:
b ()[rAMillid4I 2k8D Blaine Murray, Chipf, Facilities Radiation
[ Tate /
Protection Section l
Inspection Summary Inspection on February 22-26, 1982 (Report 50-285/82-04)
Areas Inspected:
Routine, unannounced inspection of the licensee's radioactive waste systems including liquid and gaseous effluent releases; records and reports of radioactive effluents; procedures for controlling effluent releases; testing of air cleaning systems; reactor coolant water quality; training and qualifications of radiochemistry personnel; radiochemistry sampling and analyses procedures; and audits performed by the licensee. The inspection involved 66 onsite hours by two NRC inspectors.
Results: No violations or deviations were identified.
8204050012 820325 PDR ADOCK 05000285 G
>
,
-
,
DETAILS 1.
Persons Contacted a.
- W. C. Jones, Division Manager, Production Operations
- R. W. Short, Licensing Engineer
- S. C. Stevens, Manager, Fort Calhoun Station
- F. A. Thurtell, Division Manager, Corporate Quality Assurance
- F. F. Franco, Manager, Rad Health and Emergency Planning
- K. J. Morris, Manager, Administrative Services
- R. L. Jaworski, Section Manager, Technical Services A. Richard, Plant Engineer B. J. Hickle, Chemistry and Radiation Protection (C/RP) Supervisor G. Roach, Plant Chemist M. Hale, C/RP Technician I C. Mallory, C/RP Technican II/ Training Coordinator J. Zelfel, Operations Quality Assurance Inspector The inspectors also interviewed several other plant personnel during the inspection.
b.
NRC
- R. E. Hall, Chief, Reactor Project Section C
- J. P. Jaudon, Reactor Inspector
- E. H. Johnson, Reactor Inspector
- Denotes those present during the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Open Item 78-05:
Samaling Procedures.
This item was discussed in Inspection Reports 50-285/73-05 and 50-285/79-14 and involved the lack of sample collection procedures for certain samples.
Procedures to cover all samples have been written, reviewed by the Plant Review Committee (PRC) and appreved by the Manager, Fort Calhoun Station. The licensee has a system where certain procedures are reviewed periodically such that each procedure is reviewed and updated as appropriate on a frequency of once every two years. These procedures are included in the Chemistry Manual Procedures (CMP)-2, " Sample Collection." This item is considered closed.
(0 pen)OpenItem78-05: Containment Sampler. This item was discussed in Inspection Reports 50-285/78-05 and 50-285/79-14 and involved installation of a remote containment air sampling system.
The licensee installed a system in 1979. However, the sampling system did not operate properly in order to satisfy its intended design.
Based on an evaluation of sampling requirements, the decision was made to include the containment sampling system as part of the post accident sampling
m c
s
.
,
'
'
,,
s.
t
\\
,
%
_
'
'
.
.
,
.
'
' '
s
'
.
s
'
'
d
'
,
>
,'
}
'
-
,
,
'
'
'
q s
s s
s
,
,
\\
'
-
, r
.
~
,
s
,
g
,
program.
Installation of tM post adcident sampling system is presently underway. This iten vemejis open pending completion of the post accident
,
sampling _ system, sometime byfore the'end of 1982.
4 (Closed) Open Item 79-14:
Training Records'
This item was discussed in
.
Inspection Report 79-14 and involved training records that were not up-to-date for several tect'nicians assigned to work in the Radiochemistry Labora tory. The inspectors verified that training records for
.,
radiochemistry personnel were up-to-date.
This item-is considered closed.
o s
,
The inspectors expressed concern for the extended periods that open items
~'
had remained open.
The licensee stated tha,t the remaining open item has been included as a part of the post accident sampling evaluation which..has a high priority and should be completed before the end of 1982.
.
.
l
<
.
3.
Scope of Inspe_ctico
,
The purpose of this inspection was to review the licensee's Radioactive
Waste Systems for the period August 29, 1979, through February 25, 198,2.
'
'
4.
Organization and Staff.
s The following chart shows the OPPD C/RP organizatiW us it' existed at the time of this inspection:
,j
Plant Manageb
-)
S. C. Stevens ~
'
-
,
,?'
I
,
,
l
'
-
s
'
C/RP Supervisor C/RP Tect'nician and B. J. Ilickle Training Co6rdinator l
C. Mallory I
a Plant Chemist Plant Health Physicist
'
,
Gary Roach y
Vacant
I
Chemist 6/RP Technicians Kent Irwin L/eg Crawford i
Al Bilau C/RP Technician 1 Joe Mattice Mike llale Effective March 1, 1982, Fred Smith III replaces Gary Roach as Plant Chemist and Gary Roach fills the vacancy as Plant llealtb1 Physicist.
i The inspectors reviewed training and qualifications Jor toe radiochemistry staff.
The inspectors also reviewed training records for radiochemistry personnel and noted that training records were up-to-date.
(
The radiochemistry staff purportedly is only sufficient to meet duties associated with compliance with Technical Specifications which poses a
,
problem concerning improvements of radiochemistry activities in keeping
.,
with the philosophy of maintaining exposures As Low As Is Reasonably
.
,
-.
,
,
,
'
.
,
'
.
,
j
Achievable.' Station management had recognized this as a significant
. problem and has addressed it in the proposed reorganization which includes
'
additional staffing of the C/RP department.
,
,
No violations or deviations were identified.
'
.
.
5.'
Radioactive Effluent Releases
,
a.
Liquid
t
' '
The inspectore examined the licensee's liquid effluent releases to determine compliance with the Technical Specifications 2.9.(1),
,
'
3.12.(1), and Table 3-11.
'
The following procedures and forms were included in the licensee's liquid radioactive waste program:
-Standing Order No. T-2, " Waste Liquid Release"
-Standing Order No. G-23, " Surveillance Test Program"
-Surveillance Test, ST-CHEM-1, " Chemical and Radiological Sampling" Section F.1, " Weekly"
,
Section F.2, " Monthly"
'
Section F.3, " Quarterly"
,
-Form FC-211, " Waste Liquid Release Permit"
-Form FC-222, " Waste Release Batch Summary"
-Form FC-276, " Waste Concentrate Batch Analysis"
-Form FC-287, " Steam Generator Weekly Release"
-Fcem FC-330, " Steam Generator Blowdown and Secondary Releases-Weekly Composite"
-Form FC-341, " Steam Generator Blowdown and Secondary Relea ws-Monthly Composite"
-Form FC-339, " Monitor Tank Monthly Composite"
-Form FC-326, " Monitor Tank Releases Tech. Specs."
-Form FC-327, " Steam Generator Release Tech. Specs."
The inspectors reviewed selected releases made during 1980 and 1981.
No violations or deviations were identified, s
b.
Gaseous The inspectors examined the licensee's gaseous releases to determine compliance with the Technical Specifications 2.9.(21
'.12.(2),and Table 3-12.
E#
The following procedures and forms were included in the licensee's gaseous waste program:
.
v
.
,i
.
-Standing Order No. T-3, " Waste Gas Release-Gas Decay Tank"
'
-Standing Order No. T-12. " Containment Purge Release"
-Standing Order No. G-23 " Surveillance Test Program" i
-
-
J
.
.
-Surveillance Test, ST-CHEM-1, " Chemical and Radiological Sampling" Section F.1, " Weekly" Section F.2, " Monthly" Section F.3, " Quarterly"
-Form FC-212, " Containment Purge Release Permit"
-Form FC-213, " Waste Gas Release Permit-Gas Decay Tank"
-Form FC-293, " Weekly RM-060 Tech. Specs."
-Form FC-240, "RM-060 Weekly Log"
-Form FC-237, "RM-060 Monthly Tech. Specs."
-Form FC-261, "RM-057 Monthly Tech. Specs."
-Form FC-263, "RM-062 Quarterly Tech. Specs."
-Form FC-252, " Gas Releases Tech. Specs."
-Form FC-303, " Waste Gas Release Sumary-Gas Decay Tank"
-Form FC-300, " Continuous Gas Release Summary-RM-060"
-Form FC-302, " Waste Gas Release Summary-Containment" The inspectors reviewed selected releases made during 1980 and 1981.
No violations or deviations were identified.
6.
Records and Reports of Radioactive Effluents The inspectors reviewed records and reports to determine compliance with the requirements of 10 CFR 50.36a(a)(2) and Technical Specifications 5.9.3.f, 5.9.4 and 5.10.2.e.
The inspectors noted that the licensee's semiannual reports conformed to the format recommended in Regulatory Guide 1.21 as specified in Technical Specification 5.9.4.a.
No violations or deviations were identified.
7.
Procedures for Controlling Liquid and Gaseous Effluent Releases The inspectors reviewed release procedures to determine compliance with Technical Specifications 2.9.(1), 2.9.(2), 3.12.(1), 3.12.(2), and 5.8.1.
The following procedures were reviewed:
-Standing Order No. T-2, " Waste Liquid Release"
-Procedure CMP-4.4, " Waste Liquid Release Permit"
-Standing Order No. T-3, " Waste Gas Release-Gas Decay Tank"
-Procedure CMP-4.6, " Waste Gas Release Permit-Gas Decay Tank"
-Standing Order No. T-12, " Containment Purge Release"
-Procedure CMP-4.5, " Containment Purge Release Permit" The above procedures are designed to record such data as:
s
-
.
-Radioactive and Chemical Analyses results-Technical Specification requirements and limits-Functional test of liquid or gas monitors-Functional test of isolation valve-Maximum or allowable release rate-Dilutio.; Flow Rate-Total Volume Released-Total Activity Released-Proper valve line-up-Authorization signatures No violations or deviations were identified.
8.
Reactor Coolant Water Quality The inspectors reviewed the test results of reactor coolant water quality to determine compliance with Technical Specifications 2.1.3, 2.1.5, 3.2, and Table 3-4.
The following procedures and forms were used for the test results:
-Standing Order No. G-23, " Surveillance Test Program"
-Surveillance Test, ST-CHEM-1, " Chemical and Radiological Sampling"
-Surveillance Test, ST-CHEM-2, " Chemical Sampling"
-Procedure, CMP 4.4, " Waste Liquid Release Permit"
-Procedure, CMP 4.5, " Containment Purge Release Permit"
-Procedure, CMP 4.6, " Waste Gas Release Permit-Gas Decay Tank"
-Form FC-214, " Reactor Coolant Summary Report"
-Form FC-251, " Reactor Coolant Total Gamma Activity"
-Form FC-336, " Reactor Coolant Iodine Activity"
-Form FC-340, " Reactor Coolant Gaseous Activity"
-Form FC-287, " Steam Generator I-131 concentration"
-Form FC-287, " Secondary Plant Blowdown and Leakage Releases-Isotopic Activity Analysis"
-Form FC-222, " Waste Release Batch Summary"
-Form FC-254, " Monthly Chemical Analysis"
-Form FC-215, " Secondary Chemistry Summary Report" No violations or deviations were identified.
9.
Air Cleaning Systems The inspectors examined the test results for the air cleaning systems to determine compliance with Technical Specifications 3.6.(5) and items 10.a, 10.b, and 10.c of Table 3-5.
.
-
O
,
The tests were conducted during the April 1980 and August 1981 refueling cutages.
The following surveillance test forms were used to record the test results:
a.
Control Room-ST-CRV-1.F.1, " Filter Circuit Operation-VA-46A and VA-46B"
-ST-CRV-1.F.2, " Filter Circuit Operation"
-ST-CRV-1.F.3, " Control Room Ventilation"
-ST-FIL-2.F.2, " Control Room HEPA Filter, VA-64 00P Test"
-ST-FIL-2.F.3, " Control Room Charcoal Filter, VA-64 Freon Test"
-ST-FIL-2.F.5, " Pressure Drop Across Control Room Filter
>
Banks VA-64"
-ST-IR-1.F.4, " Charcoal Filter Iodine Removal Efficiency for Filtering Units VA-6A, VA-6B, VA-26A, VA-26B, VA-66 and VA-64"
-ST-VA-4.F.6, " Auxiliary Building Air Filtering Unit VA-64" l
b.
Spent Fuel Facility-ST-FIL-2.F.4, " Spent Fuel Area Charcoal Filters (VA-66) Freon Test"
-ST-IR-1.F.2, " Charcoal Filters Iodine Removal Efficiency for
Filtering Units VA-6A, VA-6B, VA-26A, VA-26B, VA-66 and VA-64"
'
-ST-VA-4.F.3, " Filter Circuit Operation, Spent Fuel Pool Area"
-ST-VA-4.F.5, " Auxiliary Building Air Filtering Unit VA-66"
-ST-VA-4.F.8, " Spent Fuel Pool Area Operability Check" c.
Safety Injection Pump Room-ST-FIL-2.F.1, " Safety Injection Pump Room Charcoal Filters VA-26A and VA-26B Freon Test"
-ST-IR-1.F.1, " Safety Injection Pump Room Charcoal Filters VA-26A and VA-26B Elemental Iodine Removal Efficiency Test"
-ST-VA-4.F.2, " Safety Injection Pump Room Filter Operability Check"
-ST-VA-4.F.4, " Filter Circuit Operation, Safety Injection Pump Room"
-ST-VA-4.F.7, " Auxiliary Building Air Filtering Units VA-26A, VA-26B and VA-66" d.
Containment-ST-FIL-1.F.1, " Containment HEPA Filter Banks VA-5A and B Inspection"
-ST-FIL-1.F.2, Containment Charcoal Filter Banks VA-6A and VA-6B Inspection" J
-
.
1-ST-FIL-1.F.3, " Containment Filter Train Pressure Drop VA-5A, VA-5B, VA-6A and VA-6B"
-ST-IR-1.F.3, " Containment Charcoal Filter VA-6A and B Methyl Iodine Removal Efficiency Test"
-ST-VA-1.F.2, "Fil ter Ci rcuit Operation"
-ST-VA-1.F.3, " Fan and Remote Operation Damper Check"
-ST-VA-1.F.4, " System Flow Measurement"
-ST-VA-1.F.5, " Containment Air Cooling and Filtering a No violations or deviations were identified.
10. Calibration and Quality Control Program The inspectors reviewed the licensee's calibration and Quality Control Program associated with the laboratory counting instrumentation.
The following procedures were reviewed:
-Standing Order No. T-13, " Quality Control Program for Chemistry and Radiation Protection Equipment"
-Procedure CMP-4.28, " Function Check-264-GM"
-Procedure CMP-4.29, " Function Check-265-IPC"
-Procedure CMP-4.33, " Function Check-274-Liquid Scintillation"
-Procedure CMP-4.30-2, " Function Check-266-TN-11"
-Procedure CMP-4.31, " Function Check-272-Wide Beta II-Prccedure CMP-4.1-2, " Function Check-200-Canberra GeLi System"
-Procedure CP-LAB-6, " Calibration Procedure-GM"
-Procedure CP-LAB-7, " Calibration Procedure-IPC"
-Procedure CP-LAB-8, " Calibration Procedure-Liquid Scintillation"
-Procedure CP-LAB-15, " Calibration Procedure-TN-11-Procedure CP-LAB-16, " Calibration Procedure-Wide Beta II"
-Procedure CP-LAB-19, " Calibration Procedure-Canberra GeLi System" In general, the above procedures require that each instrument be functionally tested daily or prior to use if the instrument is not operated on a routine basis.
Standing Order No. T-13 specifies the calibration frequencies.
The licensee stated that a problem existed regarding temperature reliability of control in the counting room which affected the GeLi system. The licensee stated that an evaluation is underway to resolve this problem by installation of an independent temperature control for the radiochemistry laboratory.
No violations or deviations were identifie.
--
11. Licensee Audits The inspectors examined the reports of audits performed by the licensee.
The licensee's records indicated that an outside vendor had-conducted an audit of radiochemistry activities during July 22 and 23,1980.
In addition, the plant quality assurance staff performs monthly audits of radiochemistry.
The _ audit reports did not identify any significant problems.
No violations or deviations were identified.
12. Plant Tour The inspectors toured the plant on February 23, 1982. Special attention was given to radwaste activities and effluent monitors. The inspectors
. visited each detector / sampler location and verified that the following monitors and recorders were in service and operating:
'
a.
Liquid Monitor Identification Radioactive Waste Disposal System RM-055A Circulating Waste Discharge Tunnel RM-056A and 056B Component Cooling Water RM-053 Waste Disposal System Auxiliary RM-059 Steam (Out of Service)
Waste Disposal System Concentrates RM-058 (Out of Service)
_
Reactor Coolant RR-214
'
(Fail Fuel Monitor)
Steam Generator Blowdown RM-054A and 054B The waste disposal system concentrate monitor, RM-058 was out of service because of problems associated with hot temperatures and the Nal
. scintillation detector. The licensee stated that an evaluation is undeneay to relocate the detector to another location, meanwhile,
concentrates are barrelled and disposed of as solid waste. 'The licensee purportedly will have RM-058 back in service within six months.
The waste disposal system auxiliary steam monitor, RM-059, was out of service because a proper calibration could not be achieved. The licensee stated that an electronic calibration has been completed, a radioactive
'
source calibration will be performed and RM-059 should be back in service j
in about one month.
In lieu of RM-059, the licensee has been analyzing weekly samples from the waste evaporator.
I No violations or deviations were identified.
l L
,
i
,
w pT*
+ = -
w a e m-
.w-em+-er
-- - -----m.
ory-ew, gr9 y mm -
3
-
-p---.e-
<
---e
---v---
m-t r-e---'iw s-
-e*w+m=mW*m--e e.m----a
- - +T v t'
i'Mri
.
.-
b.
Gaseous Monitor Identification Containment Air RM-050 and 051 Containment Air RM-052 (Backup to RM-051 and 062)
Main Stack RM-060, 061, and 062 Condenser Off-Gas RM-057 Steam Generator Blowdown RM-054A and 054B No violations or deviations were identified.
13. Miscellaneous Item As requested by the NRC Resident inspector, the inspectors reviewed a sign-out sheet, dated February 8,1982, for Radiation Work Permit-34 in which it appeared as if a contractor employee had escorted a visitor into the restricted area in which they both logged in the same pocket dosimeters. An investigation revealed that the two individuals had logged in the Model Number rather than the Serial Number of their respective pocket dosimeters.
The visitor of February 8,1982, had subsequently become a contractor employee.
The inspectors noted on February 26, 1982, that both individuals had been retrained in the proper procedures by the C/RP staff.
14.
Exit Interview The inspectors met with those individuals denoted in paragraph 1 at the conclusion of the inspection on February 26, 1982.
The inspectors reviewed the purpose and scope of the inspection and discussed the inspection findings.
-