ML17157A319
| ML17157A319 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/06/1990 |
| From: | Bores R, Joseph Furia NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17157A317 | List: |
| References | |
| 50-387-90-16, 50-388-90-16, NUDOCS 9009240172 | |
| Download: ML17157A319 (9) | |
See also: IR 05000387/1990016
Text
U.S.
NUCLEAR REGULATORY COMMISSION
REGION I
50-387/90-16
tt tt.
~t-
-tt
50-387
Docket No.
50-388
License
No.
Licensee:
Penns
lvania
Power
& Li ht
Com an
2 North Ninth Street
Allentown
Penns lvania
18101
Facility Name:
Sus
uehanna
Steam Electric Station
Units
1
& 2
Inspection At:
Berwick
Penns lvania
Inspection
Conducted:
Au ust 13-17
1990
Inspector:
J.
uria, Radiation Speci,
Eff1
nts
Radiation Protection
Se
'on
(ERPS), Facilities
Radiological
Safety
and Safeguards
Branch
(FRSSB),
Division of Radiation Safety
and Safeguards
(DRSS)
r
g/d/5'o
date
Approved by:
R, Bores,
Chief,
ERPS,
FR
,
DRSS
e/a/po
date
Inspection
Summary:
Ins ection
on Au ust 13-17
1990
Combined
Ins ection
Re ort Nos.
50-387 90-16
50-388 90-16
Areas
Ins ected:
Routine,
unannounced
inspection of the transportation
and
solid radioactive
waste programs'ncluding:
management
controls; audits;
quality assurance;
and implementation of the above
programs.
Results;
Within the areas
inspected,
one violation in radwaste
(scaling
factors)
was identified (See Section
3. 1).
SOOS24OCWZ
SonS Or
ADOCK 05000387
1.
Personnel
Contacted
DETAILS
1.1
Licensee
ersonnel
G. Appel, Chemist
J. Fritzen, Radiological
Operations
Supervisor
- D. Hagan,
Radiation Protection Supervisor
- F. Jaeger,
Health Physics
Radwaste
Foreman
J.
Lex, Nuclear General
Training Supervisor
- R. Prego, guality Assurance
Supervisor
- Operations
D. Rarick, guality Control Inspector
H. Riley, Health Physics Supervisor
- N. Sawicki,
Radwaste
Operations
Engineer
J. Schmidt,
Nuclear guality Assurance Analyst
- H. Stanley,
Superintendent
of Plant
G. Walker, Health Physics Technician
R. Wehry,
Compliance
Engineer
V. Zukauskas,
Assistant
Health Physics
Radwaste
Foreman
1.2
Commonwealth of Penns lvani
- D. Ney, Department of Environmental
Resources,
Bureau of Radiation
Protection
1.3
NRC Personnel
- S. Barber,
Senior Resident
Inspector
- J. Stair,
Resident
Inspector
- Denotes
those present
at the exit interview on August 17,
1990.
2.
~Per ose
The purpose of this routine inspection
was to review the licensee's
program for the preparation,
packaging
and transportation of radioactive
materials.
3.
Trans ortation
and
Radwaste
The licensee's
program for the packaging
and transportation
of
radioactive materials,
including solid radwaste,
was conducted jointly
by the Operations
and Health Physics
Departments.
Spent resins
and
filters were processed
and placed in liners by the Operations
Department,
with shipping casks
procured
and shipping documentation
prepared
by the Health Physics
Department.
Dry Active Waste
(DAW) was
collected
and sorted
by contractor personnel
under the direction of the
Health Physics
Department.
Radwaste
The licensee
produced
waste
streams of solid radwaste,
spent
resins,
spent filters and
DAW.
Resins
were typically dewatered
in
High Integrity Container s (HICs) utilizing a dewatering
system
supplied
and operated
by Scientific Ecology Group
(SEG).
SEG also
provided filtration services
which allowed the licensee to bypass
the existing radwaste
evaporator
systems.
DAW was shipped for
segregation
and disposal
to SEG.
In addition, the licensee
had
an
extensive
system for the analysis
and sorting of "clean" trash
removed
from the radiation controlled areas, utilizing a Hydro
Nuclear sorting,
shredding
and monitoring system,
to ensure that
no radioactive materials
were improperly released
from the site.
As part of this inspection,
the following procedures
were
reviewed.
AD-gA-IOO, Rev 7, "Station Organization
and Responsibilities"
AD-gA-311, Rev 9, "Solid Radioactive
Waste
Process
Control
Program"
Rev 1, "Solid Radwaste
10 CFR 61 Correlation Factor
Determination"
HP-TP-800,
Rev 14,,"Shipment of Radioactive
Waste Material"
HP-TP-801,
Rev 9,
"General
Shipment of Radioactive Material"
HP-TP-804,
Rev 10,
"Shipment of Contaminated
Laundry Via Exclusive
Use 'Vehicle"
HP-TP-807,
Rev 5, "Specific Site Criteria for Radwaste
Shipment to
the Chem-Nuclear
Systems,
Inc. Barnwell, South Carolina Disposal
Site"
HP-TP-851,
Rev 10,
"Radwaste
Curie Calculations"
HP-TP-852,
Rev 1,
"Use of the HN-215H Shipping Package"
HP-TP-860,
Rev 5, "Transfer of Radioactive Material to the
Low
Level
Radwaste
Holding Facility (LLRWHF)"
HP-TP-862,
Rev 2,
"LLRWHF Container Inspection"
HP-TP-880,
Rev 0, "Operation
and
Use of the Wastetr ak Code"
OP-068-121,
Rev 3, "Transfer and Dewatering
Bead Resin In Radlock
Containers to Less
Than
1% Free Water"
3.2
All procedures
were found to be complete
and to accurately reflect
existing plant processes,
with the exception of AD-(A-100, which
has not been
updated to reflect major changes
to the Health
Physics
Department organizational
structural.
The licensee
submitted plant samples to SAIC, Inc. for analysis of
isotopic content every
9 to
12 months.
Results of these
analyses
were then entered
into the Wastetrak
computer data
base for
development of waste
stream specific scaling factors.
Beginning
in 1984,
the licensee
began dewatering
some spent resin
streams
instead of the previously utilized solidification process.
However, the licensee
continued to sample the wet waste
stream
and
base their radiochemical
analyses
on
a wet waste
stream,
resulting
in under reporting the activities of most isotopes
in these
radwaste
shipments.
In addition, the licensee
in February
1989
began utilizing a new resin in the Reactor
Water Clean-Up
System.
A, liner containing
a mixture of this new resin
and the previously
utilized resin
was shipped without first analyzing
and developing
a scaling factor for this waste stream.
This is
an apparent
violation of 10 CFR 61.55(a)(8)
which permits the utilization of
scaling factors if they can
be directly correlated
to actual
plant
conditions
(50-387/90-16-01;
50-388/90-16-01).
Although the
licensee
did identify this violation in May, 1990, there
was
available guidance
from both the
NRC and the industry on the
appropriate
development of scaling factors which could have
prevented
the licensee
from improperly quantifying the wastes.
In June,
1990, the licensee
discovered that anaerobic microbial
organisms
were in the liquid radwaste
spent resin
system,
causing
the generation of methane
gas in dewatered
HICs.
At the time of
this inspection,
the licensee
had
suspended
shipments of this type
of spent resin,
and were investigating various methods for
treating this waste
stream to prevent
gas generation.
This item
remains
unresolved
pending licensee
actions
(50-387/90-16-02;
50-
, 388/90-16-02).
Trans ortation
Shipment of radioactive materials
was the responsibility of the
Health Physics
Department.
The Radwaste
Section
prepared all
shipping manifests
through the utilization of the Impell
Corporation's
Wastetrak
computer code.
As part of this inspection,
the following 21 waste
shipment
records
were reviewed.
~Shi ment
90-040
90-043
90-044
Activit
Ci
7.13E-01
2. 76E+01
2.34E-05
Volume
cu ft
195.2
114.9
0.5
~Te
Resin
Filters
Samples
~Shi
ment
~ii ii
Ci
~V1
fi
T~
90-046
90-048
90-051
90-054
90-055
90-056
90-057
90-059
90-060
90-061
90-062
90-063
90-064
90-065
90-066
90-067
90-068
90-071
2.42E-01
2.13E-04
4.18E-02
3.87E-01
1.35E-05
1.35E-05
1.18E+00
2. 71E-01
1.04E-03
1.02E-01
6.01E-02
4.34E-04
1.98E+00
2.91E-01
1.60E-05
1.60E-05
3.06E+00
3.62E-01
195.4
132.0
720.0
177.3
0.5
0.5
1280.0
195.2
0.5
720.0
224.0
0.5
195.2
195.2
0.5
0.5
195.2
2560.0
Resin
RHR Motor
Laundry
Resin
Samples
Samples
Resin
Samples
Laundry
Equipment
Samples
Resin
Resin
Samples
Samples
Resin
3.3
3.4
All shipments
were determined to meet the requirements
of 10
CFR
and
49 CFR.
Interim Radwaste
Stora
e
As part of this inspection,
the licensee's
plans for the storage
of radioactive wastes
on site were examined.
Currently the
licensee
has
access
to the three low-level waste disposal
sites
until January,
1993.
The licensee
is located within the
Appalachian
Compact,
which is not scheduled
to have
a disposal
site open until 1996.
In preparation for the loss of offsite
disposal,
the licensee
had constructed
a
Low Level
Radwaste
Holding Facility (LLRWHF), designed to hold up to five years of
plant generated
radwaste.
Based
upon current generation
rates,
the licensee
has
more than sufficient storage
capacity in the
LLRWHF.
The licensee
has
by procedure
HP-TP-860 prohibited the
storage of dewatered
wastes
in the
LLRWHF.
Dewatering of spent
resins is currently utilized extensively
by the licensee.
The
issue of dewatered
spent resin storage
was raised with the
licensee
during the previous inspection of this area in July,
1989.
This item remains
unresolved
awaiting licensee
analysis
and
potential
changes
to the safety analysis report
and procedures
associated
with the
LLRWHF (50-387/90-16-03;
50-388/90-16-03).
ualit
Assurance
1
The licensee's
program for the assurance
of quality in the
radwaste
area involved four sections of the Nuclear guality
Assurance
(NgA) Department.
Staff Auditing was responsible for
conducting periodic audits of the in plant radwaste
program
and of
principle vendors supplying services
and materials
in support of
the radwaste
program.
Procurement guality was tasked with
ensuring that materials
involved in the radwaste
program arriving
at the plant met the terms
and conditions of the various contracts
in place.
guality Surveillance
conducted periodic surveillances
of various radwaste evolutions.
guality Control inspected all
shipments of radioactive material prior to leaving the plant.
As part of this inspection,
the most recent audits of the plant
radwaste
program
and of the principle vendors for this program
listed below were reviewed.
3.5
Audit 89-027,
December
21,
1989, Subject:
Solid Radioactive
Waste
Process
Control
Program
Audit 88-032,
Hay 5,
1988, Subject:
- Hittman
Nuclear,
Inc.
Audit 88-087,
December
28,
1988, Subject:
Scientific Ecology
Group, Inc.
Audit 88-022,
Hay 18,
1988, Subject:
Chem-Nuclear
Systems,
Inc.
There were
no findings as
a result of these audits.
The scope
and
technical
depth of the audits
was determined to be excellent.
Two surveillances
conducted
in the radwaste
area during 1990 were
examined
as part of this inspection.
guality Assurance
Surveillance
Report
(gASR)90-001
was
a general
review of radwaste
operations
while gASR 90-025 included
a surveillance of the
processing
of contaminated
waste oil by a vendor.
The technical
depth of these surveillances
was determined to be very good.
Overall, the program for the assurance
of quality in the radwaste
area
was determined to be
a notable strength.
~Trainin
The licensee's
training program for radwaste
personnel
continues
to be one of excellent training quality,
and meets
or exceeds
the
requirements
of NRC IE Bulletin 79-19.
At the time of this
inspection,
the licensee
was revising procedure
NTP-(A-42.3,
"Radwaste
Worker Training", to expand
and clarify the listing of
those
personnel
required to take at least
one of the training
modules or approved off-site training courses
offered
by the
Training Department.
With this clarification, the licensee
has
improved the assurance
that all personnel
involved in the radwaste
program receive
appropriate training.
~
~
~
4.
Exit Interview
The inspector
met with the licensee representatives
denoted in Section
1
at the conclusion of the inspection
on August 17,
1990.
The inspector
summarized
the purpose,
scope
and findings of the inspection.