ML19250A627
| ML19250A627 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/20/1979 |
| From: | Greger L, Hiatt J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19250A611 | List: |
| References | |
| 50-010-79-15, 50-10-79-15, 50-237-79-19, 50-249-79-17, NUDOCS 7910240089 | |
| Download: ML19250A627 (8) | |
See also: IR 05000010/1979015
Text
.
U.S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-10/79-15; 50-237/79-19; 50-249/79-17
Docket No. 50-10; 50-237; 50-249
License No. DPR-2; DPR-19; DPR-25
Licensee:
Commonwealth Edison Company
Post Office Box 767
Chicago, IL 60690
Facility Name: Dresden Nuclear Power Station, Units 1, 2 and 3
Inspection At: Dresden Site, Morris, IL
Inspection Conducted: August 28-31, 1979
i
.U kW
Inspector:
3. W. Hiatt
9IJ0/ Pl
Approved By:
L. R. G
f
f 74' M
Fuel Facility Projects and
Radiation Support Section
Inspection Summary
Inspection on August 28-31, 1979 (Report No. 50-10/79-15; 50-237/79-19;
50-249/79-17)
Areas Inspected: Routine, unannounced inspection of reactor coolant radio-
chemistry, Unit I decontamination, and liquid and solid radioactive waste
systems, including:
effluent releases; records and reports of effluents;
effluent control instrumentation; procedures for controlling releases;
onsite storage; licensee event reports; and licensee action on previously
identified enforcement items. The inspection involved 34 inspector-hours
onsite by one NRC inspector.
Results: Of the seven areas inspected, no items of noncompliance or devi-
ations were found in six areas; one item of noncompliance was found in the
remaining area (Infraction - Failure to have an approved calibration pro-
cedure for the Units 2/3 liquid effluent monitor - Paragraph 8).
791024008
1202 247
.
DETAILS
1.
Persons Contacted
- D. Adam, Waste Systems Engineer
- J. Barker, USNRC
G. Bergan, Chemist
J. Brunner, Engineer
T. Gillman, Health Physicist
M. Granas, Health Physicist
F. Jones, Health Physicist
- W. McNeil, Engineer, Detroit Edison Company
- J. Parry, Radiation Chemistry Supervisor
R. Ragan, Assistant Superintendent, Operations
D. Sharper, Radwaste Foreman
T. Schneider, Chemist
- B. Shelton, Assistant Superintendent, Administrative
- E. Wilmere, Q.A. Coordinator
The inspector also contacted other licensee employees, including
radwaste operators and radiation chemistry technicians.
- Denotes those present at the exit interview.
2.
General
This inspection, which began at 8:15 a.m. on August 28, 1979, was
conducted to examine the licensee's liquid and solid radwaste activ-
ities for compliance with NRC requirements. During the inspection,
tours were made in the Unit I and Unit 2/3 radwaste areas and the
Unit I chemical cleaning facility. The inspector also examined the
Stock waste solidification system (See Paragraph 11).
3.
Licensee Action on Previous Inspection Findings
(Closed) Noncompliance (50-10/78-23, 50-237/78-21, 50-249/78-23):
Failure to meet FSAR commitment for monitoring liquid radwaste
effluents from Units 2 and 3.
The offline effluent monitoring
system was restored to operation in Ncvember 1978, calibrated, and
has been used during all liquid discharges from the Unit 2/3 liquid
radwaste system since that time.
4.
Organization
On August 27, 1979, the Radiation Chemistry, Tecnnical Staff, and
Quality Control Departments began reporting directly to the Assistant
Plant Superintendent, Administrative. Previously, the Radiation
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1202
248
.
Chemistry Supervisor had reported to the Technical Engineer. The
Chemistry Supervisor will continue reporting to the Technical Engineer.
5.
Radioactive Liquid Releases
Theliceasee'sliggdradwastetreatmentwasdescribedinaprevious
inspection report.-
In November 1978 the licensee replaced the
conventional laundry system with two dry cleaning units, reducing
the discharges from Unit 1 to water used for washing respirators.
In September 1979 the licensee plans to test a respirator dry
cleaning unit and a closed cycle respirator wash unit.
Successful
use of these units could eliminate essentially all liquid releases
from Unit 1.
The inspector selectively reviewed che licensee's calculation and
discharge checklists (DOP 20t.0-25 and DOP 2000-28) and " Liquid
Radioactive Waste Discharge Records" for the period from July 1978
through June 1979. Most of the releases were less than 10% of the
Technical Specification limit; none exceeded the limit. The inspector
noted that releases from Unit I decreased by about 70% following the
installation of the dry cleaning units.
No items of noncompliance were identified.
6.
Radioactive Liquid Storage
Results of surveglance procedures DOS 2000-1 (Units 2/3) and DOS
2000-2 (Unit 1),-
written to assure compliance with Technical
bythelicensee,g7.,werereviewed.
Specification 3.
D
Except as previously reported
no discrepancies from the technical specification
activity or surveillance requirements were noted. DRP 1710-4 had
been amended to speci
notification levels and the storage tanks to
j
be sampled for Unit 1
No items of noncompliance were identified.
7.
Effluent Reports
The inspector reviewed the licensee's semiannual effluent reports
for 1978 (liquid and solid radwaste only). Using the licensee's
weekly discharge data, the inspector independently calculated the
liquid discharge data for selected months; no discrepancies from the
reported data were noted. The report met the requirements of Tech-
nical Specification 6.6.C.
No items of noncompliance were identified.
1/
IE Inspection Reports No. 50-10/78-23, 50-237/78-21, 50-249/78-23.
2_/
Ibid.
3/
LER 50-237/79-43.
- .
4/
IE Inspection Reports No. 90-10/78-23, 50-237/78-21, 50-249/78-23.
I!
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1202
249
8.
Effluent Control Instrumengtion
The Units 2/3 offline liquid effluent monitor was returned to service
in November 1978. No discharges were made until the first quarter
of 1979, at which time the monitor was calibrated. The calibration
method used is similar to the method used to calibrate offgas monitors.
The licensee performs a linearity check of the monitor, correlates a
gamma analysis (GeLi) of a predischarge tank sample to the monitor's
response during the release of the tank, and uses the curve generated
by the linearity check to graph release concentration (uCi/ml) versus
monitor response (eps). The licensee was aware that this calibration
method would be effective only if the relative percentages of nuclides
in liquid radwaste remained constant. A review of monthly gamma iso-
topic analyses for 1979 (through June) indicated little variance in the
percentages. Cobalt-50, Cobalt-58, and Manganese-54 were the main con-
stituents. The inspector will review the calibration method further
during a future inspection.
The inspector noted that there was no approved procedure detailing
this calibration method, which was used for the first quarter and
second quarter 1979 calibrations. This is considered an item of
noncompliance.
9.
Procedures for Controlling Releases
The inspector reviewed the following revised procedures:
DCP 1200-5
Rev. I
" Reporting Conditions for Selected
Laboratory Analyses"
DCP 1600-7
Rev. 2
" Sampling and Analysis of Radwaste Tanks"
DCP 1600-8
Rev. 3
" Composite River Sampling"
DCP 1600-11
Rev. 3
" Routine OffGas Sampling and Analysis"
DCP 2700-6
Rev. 4
" Determination of Noble Gas Release
Rate From D1 and D2/3 Chimneys Using
the Marinelli Beaker"
DCP1200-5wasrevisedtocorrecttypogragicalerrorsandtoassure
agreement with DRP 1710-4 and DCP 1400-5.-
The revisions made to
the other procedures were to add or delete the procedure from posted
procedure status.
Except for the item discussed in Paragraph 8, no problems with
procedures were noted, and no items of noncompliance were found.
5/
Ibid.
-'-
1202
250
10.
Reactor Coolant Water Quality
A
Records of radioactivity e asurements in reactor coolant water were
reviewed for the period from September 1978 through August 1979. Ne
discrepancies from technical specification surveillance or activity
requirements were noted. The inspector observed that the amount of
total iodine in the Unit 3 reactor coolant was three to four times
greater than that in Unit 2.
According to the licensee, suspected
problems with the 7 X 7 fuel in the Unit 3 core are probably respon-
sible for this difference.
No items of noncompliance or deviations were noted.
11.
Solid Radioactive Waste
The Unit 1 spent resin and sludge storage g nks and vaults were
described in a previous inspection report.-
Installation and
opera ility tests of level instrumentation and sump pumps in the
tanks and vaults were completed in April and May 1979, respectively.7j
These modifications should relieve tank overflow problems.
In February 1979, the licensee began operational tests of the Unit
2/3 Stock radwaste solidification system. About 300 drums of con-
centrated waste, filter sludge, and resin have been processed.
During the tests, capping problems, including burred threads on drums
and excessively soft gaskets, were encountered. The problems were
correcced and the licensee intends to have the system fully oper-
ational by mid-September 1979. The inspector, accompanied by licensee
personnel, toured the system and noted the following radiation
protection problems.
The design of the " labeling station" is such that considerable
streaming of radiation occurs through two openings designed for
smearing drums. The licensee stated that one of the openings will
be totally enclosed, while the other will be fitted with removable
plugs which will be used as access for remote smear handling tools.
Drums must be raised above shield walls for loading into shipping
casks and moving to the labeling station. This causes flucuations
in the radiation levels in the truck bay area.
It is likely that if
several high level drums are moved at once (using a pallet designed
for loading into casks), radiation levels may exceed 100 mR/hr. The
licensee stated that methods would be aeveloped to insure compliance
with 10 CFR 20.203 requirements for control of access to high radiation
areas. According to licensee personnel, radiation levels at the
control room viewing window have approached 90 mR/hr during drum
movement. The licensee plans to increase shielding by .'nstalling
either a leaded or water filled window.
6/
Ibid.
7/
Ibid.
1202 251
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.
~
10.
Reactor Coolant Water Quality
Records of radioactivity measurements in reactor coolant water were
reviewed for the period from September 1978 through August 1979. No
discrepancies from technical specification surveillance or activity
requirements were noted. The inspector observed that the amount of
total iodine in the Unit 3 reactor coolant was three to four times
greater than that in Unit 2.
According to the licensee, suspected
problems with the 7 X 7 fuel in the Unit 3 core are probably respon-
sible for this difference.
No items of noncompliance or deviations were noted.
11.
Solid Radioactive Waste
TheUnitIspentresinandsludgestoragegynksandvaul.tswere
described in a previous inspection report.-
Installation and
operability tests of level instrumentation and sump pumps in the
tanks and vaults were completed in April and May 1979, respectively.77
These modifications should relieve tank overflow problems.
In February 1979, the licensee began operational tests of the Unit
2/3 Stock radwaste solidification system. About 300 drums of con-
centrated waste, filter sludge, and resin have been processed.
During the tests, capping problems including burred threads on drums
and excessively soft gaskets, were encountered. The problems were
corrected and the licensee intends to have the system fully oper-
ational by mid-September 1979. The inspector, accomparted by licensee
personnel, toured the system and noted the following rauiation
protection problems.
The design of the " labeling station" is such that considerable
streaming of radiation occura through two openings designed for
smearing drums. The licensee stated that one of the openings will
be totally enclosed, while the other will be fitted with removable
plugs which will be used as access for remote smea
.ndling tools.
Drums must be raised above shield walls for loading i-
.pping
casks and moving to the labeling station. This caus
.uations
in the radiation levels in the truck bay area.
It is lixely that if
several high level drums are moved at once (using a pallet designed
for loading into casks), radiation levels may exceed 100 mR/hr. The
licensee stated that methods would be developed to insure compliance
with 10 CFR 20.203 requirements for control of access to high radiation
areas. According to licensee personnel, radiation levels at the
control room viewing window have approached 90 mR/hr during drum
movement. The licensee plans to increase shielding by installing
either a leaded or water filled window.
~6/
Ibid.
02 252
7/
Ibid.
-5-
.
These items will be reviewed during future inspections.
No items of noncompliance were identified.
12.
Radioactive Matsrials Shipments
Selected solid redwaste disposal records for the period from September
1978 through Ju'.y 1979 were reviewed. Shipments of solidified
resin, filter aludge, concentrated waste, and dry active wast _ were
made. Records reviewed indicate that shipments containing greater
than Type A quantities were made in either a DOT specification
container or a package for which an NRC certificate of compliance
had been issued. Shipments were made under license procedures DOP
2000-40 " Inspection of Radioactive Waste Shipments" Rev. I and DOP
2000-39 " Loading of Radioactive Waste Sh2pments" Rev. 1.
The inspec-
tor noted that these procedures contained instructions and data
sheets which satisfied the requirements of 10 CFR 71.54 and 71.62.
The inspector reviewed records of the licensee's onsite Quality
Assurance Department's 1978 and 1979 (through July) audits of radio-
active material shipments. The Department performed a formal audit
in May 1979 and conducted periodic spot checks of shipments. The
inspector noted that no problems with NRC requirements were found.
13.
Review of Nonroutine Events
Licensee corrective actions on the following licensee event reports
were reviewed:
LER 50-10/79-01
Radwaste leakage from condensate storage
tank (5/18/79)
LER 50-237/79-10
Blowout of Unit 2 reactor building blowout
panels (2/2/79)
LER 50-249/79-17
Failure of fuel pool area radiation monitor
(7/13/79)
LER 50-237/79-40
Leakage of contaminated water from the
Units 2/3 radwaste reboiler room (6/5/79)
LER 50-237/79-43
Excessive activity in above ground storage
tank (6/12/79)
As a result of the Unit 1 leak, about 30 tons of contaminated soil,
containing a total of 15 mci's of radioactivity, were shipped to a
licensed burial site for disposal. No workers were contaminated by
the water from the leaking line.
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1202
253
.
The licensee stated that the blowout of the reactor building blowout
panels did not cause a release of radioactivity to the atmosphere.
Air samples taken on the refueling floor before the event were in
the 10E-11 uCi/cc range; air and snow samples taken outside the
building following the event were at background levels. The inspector
reviewed the licensee's evaluation and concurred with the results.
No personal contamination resulted from leakage of water from the
radwaste reboiler room. Three 55-gallon drums of dirt, containing a
total of about 10 uCi's, were shipped to a licensed facility for
disposal. A floor drain will be installed in the reboiler room in
the fall of 1979.
The inspector noted that the excessive activity in the above ground
storage tanks was the second such event in the last 18 months (LER
50-237/78-27).
Licensee actions following discovery of the activity
were in compliance with technical specification 3.8.D.
14.
Status of Unit 1 Decontamination
The chemical decontamination of Unit 1 is now scheduled for February
'
1980. The radiation protection department has been providing health
physics support and developing health physics procedures for the
decontamination (e.g. sampling,the cleaning agent during the cleaning,
calculating the curie content of Dow solidification system drums,
effluent sampling, etc.).
No licensee radiation protection staffing
increases are planned; contract technicians will be used if additional
manpower is needed. Dow Chemical plans to provide their own health
physics technicians, who will perform independent sampling and
surveys. However, overall health physics control will be maintained
by the licensee.
During a tour of the chemical cleaning building, the inspector noted
that the Dow solidification system truck bay area may have the same
variable radiation problems during drum loading as the Stock system
(see Paragraph 11). The licensee stated that this problem will be
evaluated. This item will be reviewed further during future inspections.
15.
Exit Interview
The inspector met with licensee representatives (denoted in Paragraph
1) at the conclusion of the inspection on August 31, 1979, and
further discussed the inspection findings with Messrs. Bergan,
Parry, and Ragan on September 14, 1979. The following matters were
discussed:
The purpose and scope of the inspection.
a.
1202 254
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.
b.
The previous item of noncompliance.
(Paragraph 3)
c.
The problem with fluctuating radiation levels in the Unit 2/3
radwaste solidification system during transkrs of solidified
drums. The licensee stated that measures will be taken to
assure compliance with 10 CFR 20.203.
(Paragraph 11)
d.
The potential problem with radiation levels in the Unit I
solidification system during loading of solidified drums into
casks. The licensee acknowledged the inspector's comments and
stated that the problem will be reviewed.
(Paragraph 14)
e.
The item of noncompliance.
(Paragraph 8)
f
L
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