IR 05000263/1975004
| ML20024G076 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/31/1975 |
| From: | Fisher W, Hueter L, Miller D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G074 | List: |
| References | |
| 50-263-75-04, 50-263-75-4, NUDOCS 9102070510 | |
| Download: ML20024G076 (9) | |
Text
_
_ _ _ _ _ - _. _ _ -.
.
_
.. _
_ _ _ _ _ _
_
_.
....
,
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCNNENT
,
<
REGION III
Report of Operatinual Radwante Inspection IE Inspection Report No. 050-263/75-04 Licenseel Northern States Power Company Nicollet Mall Minneapolis, Minnesota 55401 Monticello Nuclear Cencrating Plant License No. DPR-22
-
Monticello, Minnesota Category:
C Type of Licensec:
l'VR-(GE) 545 Mwe Type of Inspection:
Unannounced, Waste Management Systems Dates of. Inspection:
FebruaryJ6-21e1975
. s-
,
Date of Previous Inspection:
February 7, 1975 (Operations)
Av'[ [
Principal Inspector:phoren llueter 3 * 3/~ 7>,
.
(Date)
ho,1 'h$bv Accompanying Inspector:
Don Miller 3 - 31 -7 #
(Da t e')
Other Accompanying Personnel:
Nonc
> r
s.
Reviewed By:
W. L.' Finher Senior 11ealth Physicist 3-3/-77 racilitics Radiological Protection Section (Da t e )
,
,
)
l l
l l
9102070510 750402 PDR ADOCK 05000263
,
O PDR vj f
.
_
.
.
_ _ _
_
.. -
.-_
. _. -_
- -.
___
_
. _. _
_
.
%
.
.
SUMMARY OF TINDINGS
-
Enforcement Action None Licensee Action on Previously Identified Enforcement Matters A.
During a previous inspection the licensee was found in apparent violatio regarding adequate calibration of the liquid ef fluent monitor.pj Licensee action since that inspection along with a commitment received during the current inspection results in our having no f urther questions at this time regarding the matter.
(Paragraph 3)
The licensee has completed corrective action yelated to an apparent B.
violation noted during a previous inspection 2 involving frequency of counting vent filter cartridges when specific gross beta-gamma activitiy release rates were exceeded.
(Paragraph 8)
U_nusual occurrences None Other Significant Findings e> %* A.
Corrent Findings
.we
.,,e
.,
.
.
The licensee was at power during the inspection having ended an outage about 2 weeks prior to the inspection.
B.
Unresolved Items None C.
Status of Previously Reported Unresolved Items None reported Management Interview
'The inspectors conducted an interview with Messrs. Larson (Plant Manager),
Clarity (Superintendent-Plant Engineering and Radiation Protection) and Fey (Ascistant Radiation Protection Engineer) at the conclusion of the inspection on February 21, 1975.
The f ollowing mat ters were discussed.
,
1/
ROhospectionRptNo. 050-263/74-04.
- 1/
RO InspectionjRpt No. 050-263/74-01.
,
-2-
.- -
,. _
. _
. _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
.
se
'
,
A.
The inspectors stated that corrective action yelated to an apparent
,.
violation noted during a previous inspection-along with a commitment received during this inspection results in our having no further i
questions at this time rega: ding calibration of the 11guld cf fluent monitor.
(Paragraph 3)
B.
The inspectors acknowledged the corrective action taken g garding an apparent violation noted during a previous inspection-involving the frequency of changing and counting vent filter cartridges when specific gross beta-gamma activity release rates were exceeded, and that we have no further questions at this time regarding the matter.
(Paragraph 8)
C.
Potential problemo with the mobile vaste solidification system were discussed. The inspectors gave favorabic comment on the licensee's comprehensive radwaste records system.
(Paragraph 7)
~
f-wa m -
m, cs,
,,
,,.
,,, _
.
.
.
%
.
.
3/
ROInspection3pt,No.050-263/74-04.
4_/
RO Inspection r.pt No. 050-263/74-01.
(.l.
- 3 --
,
!
,
_
.
_
-
. -_
i
- -
.
.
.
REPORT DETAILS 1.
Persons Contacted i
C. Larson, Plant Manager H. Clarity, Superintendent. Plant Engineering and Radiation Protection L. Eliason, Radiation Protection Engineer F. Fey, Assistant Radiation Protection Engineer R. Jacobson Chemist D. Anthony, Plant Engineer, Operations
.
2.
Liquid Radwaste System
.
The licensee continues to operate the ic.11ty without release of liquid radwaste.
The last liquid radwaste release was in January 1972.
Waste liquids are processed and reused with the exception of chemical The high conductivity of chemical wastes is the major factor
-
vastes.
affecting feasibility of the reclamation of these wastes. The liquid chemical wastes are used in processing solid wastes (refer to paragraph 7 for furthet details). All contaminated laundry is sent to an out-of-state licensed laundry f acility, minimizing the licensee's handling of liquid wastes having high conductivity.
The valve for releasing to the discharge canal was observed to be chained and locked to prevent inadvertent releases.
[
%F
. w,,
es s.
'
r
"'
3.
Calibration of Liquid System Radiation Monitorn During a previous inspection / the licensee was cited against Technical
Specification 4.8.C.) in that functional tests and pu'se g(nerator
'
tests performed on the liquid radwaste effluent monitos did not constitute a calibration as defined in Technical Specific 0 tion 1.F.
As noted above, this monitor has not been used to monitor actual radwaste releases for over three years in that the last relet:n of this type was made in January 1972. The licensee established a
'
revised quarterly procedure approved by management on July 22, 1974 and first used on August 30, 1974. This procedure involves an ciectronic
" calibration" (including trip functions) of the entire unit exclusive of the detector.
Linearity of the detector's response using an acceptance criteria of + 20% is then determined using three similar cobalt 60 sources of differing activitics.
Further, the licensee agreed to correlate monitor response to the actual radwaste prior to subsequent release by using an netual analyzed sample of the sparged liquid radwaste in a limited length of the piping.
-
5/
RO Inspection Rpt No. 050-263/74-04.
-4-
,-
k.)
.
_
.
-
..
.
- -.
.
.
. _,_ _ _ _ _._. __ _ _ _ _
. _ ___
____m.
._ _
.
~'
.
.
Functional tests continue to be perf ormed monthly on the liquid radwaste effluent monitor.
Records were reviewed of routine electronic tests (monthly) and response to a solid nource of given activity (c.uarterly) performed for both the service water ef fluent monitor and the discharge canal monitor.
4.
Radioactive Liquid Sto,rg e
" Liquid Radwnste StoraEe Activity" surveillance records were reviewed for December 1974 and January 1975.
These records show that sampics were taken from the Waste Sample, Floor Drain Sample, Waste Surge and Condensate Storage Tanks every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during the period.
These samples were analysed for gross beta-gamma activity and recorded as required. The maximum total activity (excluding tritium and dissolved nobic gases) during this period was 1.84 curies. Technical Specifications surveillance requirements stipulate actions to be taken to reduce the radioactivity when the total in the tanks exceeds 30 curies.
.
5.
Reactor Coolant Quality Records show that required konthly isotopic analysis of reactor coolant water have been performed throughout 19<4.
A detailed review of December 1974 records shows that rtactor coolant was sampled at 1 cast every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and analyzed for gross beta activ'ty and also for total iodine concentration.
The gross beta concentration did not exceed 6.6 microcuries per milliliter and tot al f odine concentration did not exceed 4.6 microcuries per milliliter.
The later is well within the Limiting
,
p Condition of Operation of 20 microcuries per milliliter of t'otal
'
iodine in Technical Specification 3.6.C.1.
The December records also shows that every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> a sample of reactor coolant was analyzed for conductivity and chloride ion content. The conductivity did not exceed 0.19 micronho per centimeter (applicahic
- ehnical Specification limit of 10) and the chloride ion content did not exceed 0.01 parts per million (applicable Technical Specification
-
limi of 1.0).
A cursory review of records for Hovember 1974 and January 1975 showed that four hour testing frequency requirements had been met during reactor startup, shutdown, or testing.
6.
Review for potential Unmonitored_ Liquid Release path There are no cold (nonradioactive) sumps in the reactor building or Radwaste 11uilding.
The turbine building has a cold sump having two surnp pumps (one an backup to the other) which operate automatically based on water level in the sump.
The cold sump collects only f rom floor
,
drains in the turbine building.
Ilowever, most of the floor drains in the Turbine Building are scaled closed.
Other sumps are also located
.
.
)
'
-5-
,
,
(
.
. _... _.
t
_.. - _, _ _ _...
..
_
_,. _
. _ _ _
_.
. _ _
_. _ _._.
_
_
_
__
__.
.
,
,
l j
.
.
.
.
'
[
on the lower icvel of the Turbine Building which drain to radvaste systems. These sumps are located on a sub level of the lower level of the Turbine Building which is about 4 feet lower than the, level of the clean sump. The area of the sub-level is quite large such that to overflow it would take a very large volume of water.
Therefore, entry of potentially contaminated water into this cold sump from the hot sumps is highly improbable.
Samples of liquid from this cold sump have been taken and analyzed periodically for
,
evidence of radioactivity with negative results.
7.
Solid Radwante The licensee's basic solid radvaste system describedinapreviousinspectionreport.9ndproceduresareas
However, the licensee has had increasing maintenance difficulties with the cement handling components of the solidification system. This maintenance has resulted
in significant personal exposure.
Cement has hardened in one of the augers rendering the final stages of the solidification system inoperabic.
As a result, the licensee has obtained the services of a licensed firm, Chem Nuclear, to perform solidification onsite using a patented process housed in a tractor trailer parked at the solid radwaste
'
loading dock. Wasten containing about 80% liquid are transferred by a positive displacement pump through a high pressure hose to the trailer where it in mixed in a given ratio with a chemical compound in a shielded container.
A catalyst is added just prior to entering the steel ifnern which are placed in shipping car.ks.
Although no activity is, expected, the displaced air when the. liner I~
is being filled is vented by tubing back to the Radwaste Building.
A closed circuit TV system provides viewing of the filling operation.
Shipments were made in the f all of 1974 through Chem Suelear and more shipments were in progress at the time of the inspection.
Use of the system has resulted in large reduction in exposure of plant personnel per t;hipment.
Further. Operating personnel of Chem Nucicar are reportedly not receiving significant perronnel exposures.
The licensee's solid waste shipment records were reviewed in detail for the first six months of 1974, with respect to disposition, approximate volume, activity and labeling.
No discrepancies were noted between the licensee's records and that reported by the licensee in the semiannual report pertaining to disposition, volume and activity.
The licensee has established and is utilizing a comprehensive set of procedures for cont rolling shipments of radio-active material.
These procedures cover the stages from original request through stages of approval, analysis, surveys, etc. and a follow-up to assure that each shipment arrives at its planned
,
destination.
.
6/
R0 Inspection pt No. 050-263/73-06.
-
_6
.
p
~., _
.
f
_ --.-_- _ _ _ ___ _
_ - - _ _ _ _ _ _ _ _ _ - - _
- - - - _ - - _ _
_ _ _ _ _ _ _ _ _ _ - - - -
_ - - -
.
,
.
.
8.
Cascous Radwante System The technical specification requirement for recording the gross _ stack release rate on'an hourly basis is fulfilled by a continuous recording chart.
Records reviewed for the three month period from October through December, 1974 show that off-gas was sampled, gross ratio of long-lived to short-lived activity determined and isotopic analysin performed at frequencies meeting the technical specifications.
The inspectors reviewed the licensee's records of releases of gaseous waste for the month of June, 1974.
These records vere in agreement with that reported by the licensee in the semiannual report. Turther, it was concluded from the review that the licensee used propcr data reduction techniques to obtain identity, quantity, release rate and percent of technical specification limits of nobic gases, halogens and particulates.
At the time of a previous inspection 7/ the licensee was cited against the surveillance requirements of Technical Specification 4.8.A.2 in that some filter cartridges were not counted daily as required when grose beta-gam:aa activity exceeded 25% of the annual average release rate of specification 3.8.A.1.
A review of records during this inspection showed that since the referenced inspection the licensee has counted both stack filter cartridges and vent filter cartridges daily when required due to measured gr cs beta-gamma activity.
,
Since the last radwaste management inspectien, the licensce has in the interest or reducing gaseous radwaste releases to "as low ac practicable" installed a demister and charcoal filter in the exhaust line which vents tanks and processing equipment in the Radwaste Pacility to the reactor building vent.
For the short time this filter r.ystem has been in operation, the licensee judges that it has been effective in reducing the iodine 131 releases from the reactor building vent by a factor of 2-3.
9.
Off-cas Monitor Records show that at 1 cast twice wechly during reactor operations one point calibrations are perf ormed by comparing the of f-gas monitor reading with isotopic analyis of an actual of f-gas sample.
Proper functional tests have been performed every three months using a built in current source and each refueling outage with a known external source to assure reasonably linear response. An acceptance criteria has been
,
established for the tolerance of measured response by the monitor compared to the known activity with instructions to notify the Rad
,
l Pro,tection Engineer if response falls outside the established tolerance.
.
}
,
7/
KO Inspection Rpt No. 050-263/74-01.
'-
-7-
.
,
-
.
.
o
.
10.
Stack Gan Monitor Sensor checks, monthly functional checks and quarterly calibrations have been performed adequately and at required' frequencies for the stack gas monitor as evidenced by surveillance records.
11.
Reactor Building Ventilation plenum Monitor
" Reactor Building Ventilation Plenum Monitor Test and Calibration Procedure" surveillance secords show that the plenum monitors have been functionally tested and calibrated (in terms of exposure rate in mil 11 roentgen per hour) as required by specification for reactor building isolation purposes.
As noted during previous inspections a continuous air monitor (CAM) is utilized in lieu of the reactor building vent monitor to measure the f or use is demonstrating compliance yith reactor building vent ef fluent the time of a previous inspectiong specification release rates. At the licensee agreed to expedite calibration of this CAM with known concentrations of noble gases.
The licensee has established and implemented test and calibration procedures involving:
(1) an annual calibratton with a known mixture of noble gases of plant origin (air ejector of f-gas); (2) a semiannual calibration check (within i 15% of annual calibration response) utilizing a krypton 85 standard and xenon 133 of plant origin; and (3) a quarterly three point linearity check (within i 20%) using an external source and the inverse square relationship t o distance with the detector r~'
removed from its shield. The annual calibration is performed..
,
,"
concurrently with a quarterly linearity check.
The CAM calibration f actor determined during the Nover.ber 1974 calibration while using known concentrations of a mixture of xenon 133, xenon 135 and g
krypton 85 from the air ejector off-gas was 3.1 x 10 microcuries per milliliter per count per minute.
It is noted that this factor is somewhat more conservative than the factor previously used which was based on response curves supplied by the instrument vendor, llowever if one were to i,sume this same calibration factor should have applied in the past the percent of speciffention limits for total caseous releases in the past vould not have been altered even when considering the more rostrictive limits placed on the vent as compared to the stack at. insignificant quantities of noblr gases are released by the reactor building vent.
12.
Standby Gas Treatment System Filter Lfficiency Tests Records show that required tests of charcoal filtern by using freon
and tests of high efficiency particulate air filters using diocty1phthalate
,
8/
RO Inspectio Rpt No. 050-263/74e01.
-.
-8-
4
_~_
_ _
_
-.,
. -. _ _. _.....
- - - - -
- _ _ _ _ _ _ _ _ _ _
....
.
.
were performed at required frequencies in 1974 and early 1975.
All filters tested in the standby gas treatment system met the acceptance criteria. The latest tests were performed on January 8, 1975.
The inlet heater output and prersute drop across the combined high-ef ficiency and charcoal filters were tested in March 1974 and f ound to meet specifications.
The pressute drop across the filters was again tested in mid May 1974 due to a charcoal filter change.
.
=
.
t
)
-9-
.-
- - - - - _ _ _ _.. - - - _ _ _ _ _ _ _ - - _ _ _ _ _ _ _. _. _ _ _. -. -.
___
UNif!D ST AttS
.
NUCtEAR REGULATORY COMf 4tSSION
,
,
OFFICE OF INSPECTION ASD F.SFORCEMENT RtGION til 799 pooLLvt LT ROAD GL E N E LL Y N, ILLINoin 6013 7
,
IEInspegtfor[ReportNo.
0-263/ W O4 A.
Trancmittal Date
April 2, 1975
,
Distribution:
Distribution:
IE Chief. FS&EB IE Chief, FSLEB IE:HQ (5)
IE:llQ (4)
DR Central Filen L:D/D for Fuels 6 Materiait, Regulatory Standards (3)
DR Central Files Licensing (13)
IE Files IE Files IE Chief, MLFPB L:D/D for Reactor Project B.
IE Inquiry Report No.
__
,
Transmi*.tal Date
'
Distribution:
Dist ribut f or.:
1E Chief, TS&EE IE Chief, FSLEB
/
IElllQ (5)
IE:llQ DR Central Files DR Central Files Regulatory Standards (3)
IE Filer.
Licensing (13)
IE Files
.
C.
Incident Notification From:
(Licensec & Docket St. (or 1.icense No.)
Transmittal Date
_
_
__
Distribution:
Distribution:
IE Chief, FS$Eh IE Chief, i'C NEl!
IE:llQ (4)
IEillQ (4)
Licensing (4)
L:D/D for Fuels & P.aterials DR Central Files DR Central Files IE Files IE Files
.
.
$' 0t.01so4,%e
j
>
h N
t,
., :.
f l
a, s u',p
We.#
b 4