ML16341G475
| ML16341G475 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 02/20/1992 |
| From: | Cillis M, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16341G476 | List: |
| References | |
| 50-275-92-04, 50-275-92-4, 50-323-92-04, 50-323-92-4, NUDOCS 9203060059 | |
| Download: ML16341G475 (20) | |
See also: IR 05000275/1992004
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos.
50-275/92-04
and 50-323/92-04
License
Nos.
and
Licensee:
Pacific Gas
8 Electric Company
77 Beale Street,
Room 1451
San Francisco,
94106
Facility Name:
Diablo Canyon Units 1 and
2
Inspection at:
Diablo Canyon Site,
San Luis Obispo County, California
Inspection
conducted:
February 3-7,
1992
Inspection
by:
,4
>s,
en>o
a )a
>on
pecla )s
ae
lge
Approved by:
~Summer:
~AI
td:
u as,
ie
Reactor Radiological Protection
Branch
P ZB
a
e
gne
Routine,
unannounced
inspection of followup items, radioactive waste
systems,
radiological environmental
monitoring, solid radioactive waste
management
and
transportation
of radioactive materials,
and
a tour of the licensee
s
facility.
Inspection
modules
92701,
92702,
84750 and 86750 were addressed.
Results:
Strengths
were noted in licensee activities associated
with the performance
quality control surveillances,
implementation of the radiological
environmental
monitoring program,
and in the minimization and transportation
of radioactive
waste.
The licensee's
programs
appeared fully capable of meeting their safety
objectives,
No violations or deviations
were identified.
()2030~0059
920220
- ADQCK 05000275
G
1.
Persons
Contacted
DETAILS
a.
b.
Licensee
- J. Townsend,
Vice President,
Diablo Canyon Operations
8 Plant
Manager
"D. Hiklush,
Manager,
Operations
Services
R. Gray, D)rector, Radiation Protection
J.
Holden, Director,
I8C
~H. Sommerville, Radiation Protection,
Senior Engineer
T. Grebel, Supervisor,
Regulatory Compliance
D. Taggart, Director, equality
Performance
and Assessment
J. Warrick, Supervising Biologist, Nuclear Operations
Support
- "J. Griffin, Sr.
Engineer,
Regulat'ory Compliance
~T. Irwing, Radwaste
Foreman
J. Knight, Radiation protection
Foreman
R. Flohaug,
equality Assurance
(QA)/Senior gA Supervisor
V. Jensen,
equality Control
(gC) Inspector
C.
Hansen,
Training Instructor
A. Allison, IBC Foreman,
Acting
NRC
H.
Wong,
Seni or Resi dent Inspector
"M. Hiller, Resident
Inspector
'*Denotes those individuals present at the exit interview conducted
on
February 7, 1992.
Additional discussions
were held with other members of the
licensee's
staff.
2.
Followu
of Previous
Ins ection Findin s (92701 and 92702
a.
Followu
Items
Item 50-275/91-29-01
(Closed):
This
item concerned
weaknesses
in
t e
licensee
s c emsca
con rol program involving the control
and
identification (i.e., labeling) of consumable
material
such
as
lubricants
and other
hazardous
materials.
The inspector
reviewed
corrective actions
taken
by the licensee to resolve the weaknesses.
The inspection disclosed that the licensee's
staff conducted
a
surveillance
to further determine
the scope of the problem.
The
licensee'
surveillance
confirmed the problems
noted in inspection
reports
50-275/91-29
and 50-323/91-29.
Applicable procedures
for the control of hazardous
materials
were
enhanced
and all personnel
were provided with traininq in hazardous
communications.
The
NRC inspector attended
the training course
2
during the inspection period.
The corrective actions
appeared
to be
satisfactory.
This matter is closed.
b.
Followu
on Corrective Action for Previous Violations
Item 50-275/91-29-,02,
50-323/91-29-02,
50-275/91-29-03,
and 50-
323/91-29-03
(Closed):
These violations involved the discovery of
two containers
aving greater
than
Appendix= C
quantities of licensed radioactive material that were not labeled in
accordance
and the discovery of three
separate
radiation areas that were not posted in accordance
requirements.
Immediate action was taken
by the
licensee's
staff to label the containers
and post the three
radiation areas.
The inspector verified that the corrective actions
described
in the
licensee's
timely response
of December
30, 1991,
and in
Nonconformance
Report
(NCR),
No.
DC0-91-TC-N093,
had been completed
in a timely manner.
The inspector
concluded that the corrective
actions to prevent
a recurrence
were satisfactory.
This
matter is closed.
3.
Radioactive
Waste Treatment
and Effluent and Environmental Monitorin
An examination of the licensee's
radiological environmental
monitoring
program
(REMP),
Process
Control
Program
as discussed
and in
Section 4, below,
and the meteorological
instrumentation
surveillance
program was performed to determine if the programs
were being effectively
implemented in accordance
with the following Technical Specifications
(TS)
requirements:
o
3.3.3.4,
"Meteorological Instrumentation"
o
3/4. 12, "Radiological Environmental Monitoring"
o
6.5.3.8,
"Audits'
6.9. 1.5,
"Annual Radiological
Environmental
Operating Report"
o
6. 13, "Process
Control
Program"
o
6. 15, "Major Changes
to Liquid, Gaseous,
and Solid Radwaste
Treatment
Systems"
The examination included discussions
with the licensee
s staff, tours of
the licensee
s facilities, and
a review of the following procedures
and
documents:
o
1990 Annual Radiological
Environmental
Operating
Report
o
Technical
and Ecological Services
procedures:
2. 1, "Graded equality
Programs"
A-la, "Biological Sampling
Schedule-DCPP"
A-2a, "Air Monitoring Schedule-DCPP"
A-7, "Environmental
Radiological
Environmental
Monitoring
Procedure-DCPP
(Normal Operations)"
A-12, "Land Use Census"
MA-l, "Equi pment
Ca 1 ibrati on Schedul e"
0
MA-4, "iIuality Control Procedure"
MB-la, 'amma-Ray
Spectrometry
System (I.G.)"
MB-lb, "Gamma-Ray Spectrometry
System (NaI}"
MC-4, "Preparation of Environmental
Samples"
MD-3, "Calibration of Air Samplers"
Results of the environmental
monitoring sampling program
Results
obtained
from the
1990 and
1991
Land Use Census
Equipment calibration records
Final Safety Analysis Report (FSAR), Chapter ll
Audits and
A
raisals
The following audits
and surveillances
performed
by the licensee's
equality Assurance
(gA) and equality Control (gC} departments
were
reviewed:
(1)
gA Audit Report
No. 9103?I, "Radiological Environmental
.
Monitoring Program,"
dated January
16, '1992.
The audit was
performed pursuant to TS 6. 5. 3.8. h.
One equality Evaluation-
Audit Finding Report
(gE-AFR) involving a missed
element
calibration factor for environmental
Thermoluminescent
Dosimeters
(TLD) and six Action Requests
(AR) involving
recommendations
for improvements
and identification of minor
deficiencies
were issued.
Overall the auditors
found that the
REMP was being effectively implemented
by the licensee's
staff.
The inspector
concluded that th'e quality of the audit was
excellent
and covered all aspects
of the
REMP in great detail.
(2)
gA Audit Report 89815T, "Radioactive Material, Management,"
dated
October
13,
1989,
and
gA Audit Report 91034I,
"Radioactive Materials Management,"
dated
September
10, 1991,
which were performed to satisfy
TS 6.5 ~ 3.8. j requirements.
TS '6.5.3.8.j.
requires that audits
encompass
the Process
Control
Program
(PCP)
and implementing. procedures
for
processing
and packaging of radioactive wastes at least
once
every twenty-four months.
The inspector
noted it could not be
determined
from reading the audit reports if the audit team
had
examined the
PCP for compliance with the
TS and implementing
procedures.
A subsequent
review of the inspection plans
used
by the auditors disclosed that only a cursory audit of the
had been performed.
The inspection plans indicated that
the scope of the audit only verified that established
implementing procedures
were consistent with TS requirements.
The audit d)d not appear to verify if the
PCP procedures
were
implemented or if the
TS survei llances
were performed.
The
inspector concluded that
a performance
based audit of the
program
had not been conducted.
This was confirmed by
discussions
held with individuals that were assigned
the
responsibility for implementation of the
PCP at the time the
audits
were performed.
The inspector brought the above observation to the attention
of the licensee's
staff during the inspection
and at the exit
interview.
The Director of equality Assurance
and Assessment
and Senior Supervisor,
equality
Performance
and Assessment
acknowledged
the inspectors'bservation.
The Director of
equality Assurance
and Assessment
stated that
a performance
-based audit of the
PCP would be rescheduled
within the next
three to six months.
(3)
equality Control
(gC) Surveillance
Reports
91-0055,
"PCP
Test Sample-Mixed
Bead Resins"
and
SR 91-0067,
"Radiation Set
Point Control."
In addition, the inspector
reviewed nineteen
SRs involving the
survei llances
made
by the
gC staff prior to shipping radioactive
materials offsite and nine
SRs involving survei llances
made prior
.to the shipment of radioactive waste to U.S.
Ecology.
The
inspector
noted that licensee's
gC staff were in the process
of
conducting
an in depth surveillance of the licensee's
radioactive waste
and materials
shipping program at the time of
this inspection.
Although some deficient conditions were observed
during the audit
and survei llances,
no violations of regulatory requirements
had
been
identified.
The deficiencies
were documented
as Action Request
or
Nonconformance
Reports.
Corrective actions
taken were normally
addressed
in a timely manner.
The survei llances
appeared
to cover
a broad
scope of radiation
protection activities.
The surveillance
performed,
examined
each
area in great detail.
The inspector
concluded that the licensee's
audit/surveillance
program provided the licensee with a viable tool
for measuring their performance.
The licensee
maintained its
previous level of performance
in this area,
and the
audit/surveillance
program
was adequate
in meeting the
recommendations
of ANSI/ANS-3.2/18.7, "Administrative Controls
and
equality Assurance for the Operational
Phase of Nuclear
Power
Plants."
b.
~Chan
ea
No major changes
had occurred since this functional area
was
previously reviewed.
C.
Neteorolo ical Honitorin
Pro
ram
The inspector
examined this program area
by reviewing completed
records of surveillance test procedures
(STPs),
interviewing
cognizant personnel
and touring the meteorological
station.
On
February 4, 1992, the inspector
noted that the licensee's
staff were
in the process
of performing
a routine surveillance of the meteorological
instrumentation
channels
pursuant to TS 4.3.3.4.
requirements.
Previous surveillance
had been accomplished
at the frequencies
specified in the TS.
Discussions
with the licensee's
staff revealed that one of the
tower's air temperature (i.e.,
Nominal Elevation 150'-25')
was not
functioning properly.
The staff also reported that the primary
tower's
computer
system failed on Sunday,
Febru'ary 2, 1992.
The
licensee's
staff reset the computer, initiated an Action Request
(No. A0257633)
on February
2nd,
and declared
the meteorological
tower to be inoperable
even though the tower's chart recorder
system
and the two wind speed
channels,
two wind direction channels,
and
one of two air temperature
channels
appeared
to be functioning
properly.
Subsequently,
on February 5, 1992, the
I8C staff, reported
that both air temperature
channels failed.
The I8C staff performing the surveillance
reported that the licensee
was considering the need to replace the tower because
of increased
maintenance
needed to combat the'ffects
from continued
exposure to
the ocean salt air environment
and other weather conditions.
The licensee
reported that as of Friday, February 7, 1992, they had
to return the meteorological
tower to an operable status within 48
hours or follow the provisions provided in the
TS 3.3.3.4 Action
statement
which requires
a special
report
be submitted to the
Commission pursuant to TS 6.9.2 within 10 days outlining the cause
of the malfunction and restoring the channels
to an operable state.
The inspector
informed the licensee that the Region
V resident
inspectors staff would continue to follow the progress
in restoring
the meteorological
tower to an operability status.
Environmental Monitorin
Pro
ram
Im 1ementation
The licensee's
REMP is conducted
by the Health Physics Unit of.
Pacific Gas
8 Electric Company's
Technical
and Ecological Services
(TES).
The
REMP program was designed to identify and quantify
ambient radioactivity concentrations
in the environs surrounding
DCPP and to determine
whether there are any significant increases
in
concentrations
of radionuclides attributable to plant operations,
in
the critical dose pathways.
The environmental
media sampled in 1991
was consistent with TS Table 3:12-1.
Reporting levels
and detection
capabilities
for the environmental
sampling analysis
performed were
found to be consistent with TS Tables
3. 12-2 and 4. 12-1.
The
inspector
noted that the sampling frequencies
met or exceeded
the
frequencies
specified in the TS.
The inspector
noted that
a routine quality assurance/control
program, consistent with Regulatory Guide (R.G) 4. 15, "equality
Assurance
for Radiological Monitoring Programs(Normal
Operations)
-Effluent and Environment",
had=been
included in the
REMP to ensure
the accuracy of the equipment
and procedures
used in determining the
results.
In addition,
TES participates
in the
EPA Environmental
Radioactivity Laboratory Intercomparison
Studies
Program,
the State
of California cross-check
program,
and Pacific Gas
8 Electric's
intracompany cross-check
program.
The licensee's
intr acomparison
cross-checks
were found to be in good agreement with other
participants.
No discrepancies
were found.
Environmental
monitoring data
from the preoperational
years
has
been
routinely used
by the licensee for comparisons
with the.REHP data
from the 1990 and 1991 operational
years.
A review of the data
indicated that there. had been
no increasinq trend from the sampling
analysis results
obtained (e.g.,
ambient direct radiation levels,
airborne concentrations,
water samples
such
as surface water,
drinking water,
seawater,
and outfall water,
sediment,
or vegetable
crops harvested
during the growing season
and milk samples)
showed
that there
was
no impact on the environs
from plant operations.
However,
some marine biological samples
were found to contain plant
related nuclides with concentrations that'ere
well below the
reporting level.
The licensee
determined that the 'concentrations
of
activity did not have
any significant impact on the critical dose
pathway to man.
The inspector confirmed that the data obtained
from the
REHP
sampling performed
and reported in the 1990 Annual Radiological
Environmental
Operating
Report
had not changed
from the
REHP
sampling that was performed in 1991.
The inspector also reviewed
the results
obtained
from the land use
census that were performed in
1990 and 1991 pursuant to TS 3. 12.2.
No new changes
were identified
as a'esult of performing the land use census.
The inspector. concluded that the licensee
was maintaininq its previous
level of performance
in this program area
and that the l>censee's
REHP
was fully capable of meeting its safety objectives.
No violations or
deviations
were identified.
4.
Solid Radioactive
Waste
Mana ement
and Trans ortation of Radioactive
a erl a
The licensee's
solid radioactive waste
management
and radioactive
material transportation
programs
were examined to determine
compliance
with TS 3.11.3,
6.13, 6.15,
61, 71,
and Department
of Transportation
(DOT) regulations
contained
49
CFR Parts
170-189.
The
examination
included
an inspection of the licensee's
radwaste
system,
discussions
with the responsible
personnel,
review of records
associated
with the processing
and shipping
and receipt of radioactive materials,-
review of training programs
and records for personnel
involved in the
processing,
packaging
and transportation
or shipping of radwaste
and
radioactive materials,
and the review o'f the following procedures:
o
AP C-253,
"Process
Control Program"
o
AP C-253S1,
"Dewatering Control Program"
o
AP C-256, "Radioactive Waste Classification
Program"
o
AP-C-257,
"Hobile Service Operating
Procedures
For Low-level
Radioactive
Waste Processing"
o
RW-3, "Radioactive
Waste Isotope Fractions
and Correlation
Factor Determination"
.
o
RW-4, "Solid Radioactive
Waste Shipment"
'
0
0
e
0
a.
RW-7, "Burial Site Disposal Criteria and Classification of
Radwaste"
RW-S, "Radioactive Maste Curie Content Calculations"
Science
Ecology Group,
Procedure
SS-042,
"Process
Control
Program
for Radwaste Solidification Service at Diablo Canyon
Power Plant"
Audits and
ualit
Control Surveillance
The inspector
noted that the licensee
maintains
an active
gC
program consistent with 10 CFR Part 61.
The status
of the most
recent audits
and surveillance
are
discussed
in Section 3, above.
b.
~Chan
ea
No changes
had occurred since this functional area
was previously
reviewed.
C.
Records
and
Re orts
A total of eleven
shipments of solid radioactive waste were
made
in 1991.
In addition,
a total of 145 shipments
of radioactive
material
shipments
were
made during the
same period,
d.
Procedures
e.
Procedures
used for radwaste
processing
and transportation
and
receipt of radioactive materials
were found to be current
and
consistent with the regulations
referenced
above.
No concerns
were
identified.
~Trainin
The inspector
noted that the licensee's
training program for
radwaste
handlers
was found to be consistent with Inspection
and
Enforcement Bulletin (IEB) 79-19,
"Packaging of Low-Level
Radioactive
Waste for Transport
and Burial.
Training lessons
plans
and an written examination that were administered
at the conclusion
of the training were reviewed during the inspection.
All training
was found to be current.
f.
Waste Hanifests
Manifests for radioactive waste
shipments
made during 1991 contained
all of the information required
by the regulations
in 10 CFR Part 20. 311,
DOT requirements,
and the burial facility's license.
No
concerns
were identified.
g.
Waste
Class
Form
Characterization
Diablo Canyon normally generates
four major types of waste which
require off-site disposal
as radioactive waste.
The waste
streams
are:
(1) Dry Active Maste
(DAM}, (2) Spent Filters, (3} Spent ion
exchange filter media,
and (4) Concentrated
Liquids.
The waste
streams
are
sampled
and analyzed at least annually for establishing
0'
the proper waste
form and classification
as required
by 10
CFR Parts
61-.bb and 61.56.
The inspector concluded that the licensee's
waste
form and classifications
made in 1990 and 1991 were consistent with
and 61.56.
A total of eleven waste shipments,-
consisting of four Class
A, four Class
8,
and three Class
C
shipments
were
made during 1991.
No concerns
were identified.
h.
Recei t of Radioactive Material
The licensee
received
a total of 94 shipments
of radioactive material
in 1991.
A review of the licensee
records
disclosed that the
shipments
were processed
in accordance
with 10 CFR Part 20.205
requirements.
The licensee's
staff monitored the shipments
in a
timely manner.
No concerns
were identified.
i.
Solid Maste, Pro
ram
The inspector determined that the licensee's
solid waste
program was
consistent with TS 3/4. 11.3 and Chapter
11 of the Updated
FSAR.
The
inspector
noted that the licensee's
PCP exceeded
TS 4. 11.3
requirements
in that the licensee
procedure
requires
the analysis- of
every batch of wet radioactive wastes
be performed in lieu
of every
ten batches
specified
by the TS.
The inspector
concluded that the
licensee's
PCP for 1991
had been effectively implemented.
The inspector
concluded that the licensee's
performance
in this area
had
improved and appeared
to be fully capable of accomplishing its safety
objectives.
No violations or deviations
were identified.
5.
~tF'itttitt
5T
Tours of the licensee's facilities were conducted
during the inspection
period.
Radioactive
waste storage
areas
were included
1n the tours.
Independent
radiation measurements
were
made using
an ion chamber
survey
instrument,
Model R0-2, serial
number 4042,
due for calibration on
February 26,
1992,
and
a Model
305B Xete'x digital exposure
ratemeter,
serial
number
23370,
due for calibration
on April 8, 1992.
The following
observations
were
made:
a.
NRC Form 3 posting
and labeling practices
were consistent with 10 CFR 19. 11 and 20.203 requirements.
b.
Significant improvements
in maintaining plant cleanliness
were noted
since the previous inspection.
c.
All portable radiation survey instruments
observed
were in current
calibration.
d.
All personnel
observed in the licensee's
controlled areas
were
equipped with appropriate
dosimetric devices.
No violations or deviations
were identified.
6.
Exit Interview
The inspectors
met with the individuals denoted in paragraph
1 at the
conclusion of the inspection
on February 7, 1992.
The scope
and findings
of the inspection
were summarized.
The licensee
was informed that
no
violations or deviations
were identified.
~
'