ML16341B128
| ML16341B128 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/09/1978 |
| From: | Troup G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML16341B130 | List: |
| References | |
| 50-324-78-23, 50-325-78-23, NUDOCS 7812210155 | |
| Download: ML16341B128 (14) | |
See also: IR 05000324/1978023
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
230 PEACHTREE STREET, N. W. SUITE 1217
ATLANTA,GEORGIA 30303
NOV OS
>gee
Repor t Nos.:
50-324/78-23
and
50-325/78-23
Docket Nos.:
50-324
and
50-325
License Nos.:
and
DPR-7l
Licensee:
Carolina
Power
and Light Company
336 Fayetteville Street
Raleigh,
27602
Facility Name:
Brunswick Steam Electric Plant,
Units
1 and
2
Inspection at:
Brunswick site,
Southport,
Inspection
Conducted:
October 2-6,
1978
>>
Inspector:
G. L. Troup
Reviewed by:
A.
F.
Gibson
Chief
1
Radiation
Support
Section
Fuel Facility and Materials Safety
Branch
Date
Ins ection
Summa rv
Ins ection
on October 2-6,
1978
(Re ort Nos.
50-324/78-23
and
50-325/78-23)
Areas
Ins ected:
Routine,
unannounced
inspection of radiation
protection
and radioactive
waste
management
program including
health
physics
instruments
and <<quipment,
health physics survey>>,
notifications
and reports, liquid effluent releases,
effluent
records
and reports,
reactor
coolant chemistry, solid waste
shipm<<nts,
followup on previous
inspection findings.
and revi<<w
of Liccnsie Fv<<nt Reports.
Th<< inspection
invnlv<<d
34 inspLctor
hours
on sit(
by on<<
NRC insp<<c tor.
R<<su) ts:
'Lilt)1in th( ar(a>> inspi( t<<d,
nn it<<ms
o." noncotIP) i.lnvt
or
d< v )at ions
wi ri ident i f i<<d.
7 8 12 2
1. 0 15'
E
RII Rpt.
No. 50-324/78-23,
and 50-325/78-20
DETAILS I
Prepared
by:
G. L. Troup,
R diation Specialist
Radiation Support Section
Fuel Facility and Materials Safety
Branch
Date
Dates of Inspectio
Octo
r 2-6,
1978
Reviewed by:
A. F. Gibson,
C ief
Radiation Support Section
Fuel Facility and Materials Safety
Branch
Date
1.
Individuals Contacted
""A. C.
-M.
M.
-"L. F.
- L. A.
R.
P.
"J. L.
R.
D.
J.
B.
"J. L.
Tollison, Jr., Plant
Manager
Tucker, Superintendent,
Technical
and Administrative
Tripp, Environmental
and Radiation Control Supervisor
(Acting)
Rogers,
Regulatory Coordinator
Cross,
Plant Engineer
McKnight, RCPT Foreman
Pasteur,
RCPT Foreman
Cook,
RCPT Foreman
Kiser, Jr. Plant Engineer
The inspector
also talked with and interviewed other licensee
employees,
including engineering
technicians,
RC6T technicians,
shift supervisors
and plant operators.
I
"Denotes
those present
at the exit interview.
2.
Licensee Action on Previous
Ins ection Findin
s
(Open)
Noncompliance
(78-05-01).
Testing
of Standby
Gas
Treatment
System Filters
and
Absorbers.
The surveillance
tests
of the
system
have
not
been
performed.
A licensee
representative
stated
that
a
tentative
date
had
been
established
for performing
the test, which is
within the
technical~ specifications
time limit.
This
item
remains
open.
(Open)
Open
Item (78-18-02).
Replacement
of Temporary
Doors to High
Radiation
Areas.
The
temporary
doors
have
not
been
replaced.
A
licensee
representative
st.ated
that the necessary
material is on order
and
some
has arrived on-site;
replacement
of the
temporary
doors wi)1
proceed
as material
becomes available.
This item remains
open.
RII Rpt.
No. 50-324/78-23,
and 50-325/78-20
I-2
(Closed)
Open
Item (78-18-03).
Maintenance
of Respiratory
Protection
Training Records.
The inspector
observed
that
records
of respiratory
training are being placed in the individual's exposure history file for
individuals
who recently
completed
the training.
A licensee
repre-
sentative
showed the inspector
the
new training record
form and stated
that
in the
future
when training/retraining
is
completed
for each
individual, the form will be placed in the individual's exposure file.
This item is closed.
(Closed)
Open
Item
(78-18-04).
Survey
Records
of
Respiratory
Protection
Equipment..
The inspector
reviewed
selected
survey
records
for
the
period
September-October
1978,
and
determined
that direct
radiation
results
were
being
included
and that
when
survey results
exceeded
action levels,
an explanation
regarding additional cleaning or
survey was included.
This item is closed.
(Open).
Open
Item
(78-18-05).
Modifications to Off-Gas
System.
A
licensee
representative
informed the inspector that installation of the
modification to the Off-Gas System
and the installation of
a
combustible
gas
detection
system
in the off-gas filter house
were
incomplete.
These
modifications
were identified
by the licensee
as
supplemental
actions
resulting
from
This
item
remains open.
3.
Unresolved
Items
No new unresolved
items were identifeid during this inspection.
Control of Hi h Radiation Areas
In IE Report
Nos.
50-324/78-18,
50-325/78-18,
an item of noncom-
pliance
was identified concerning
the control of high radiation
areas
in accordance
with Technical Specifications Section 6.12.2.
At the
time of this inspection,
the licensee's
reply to the item
of noncompliance
had not been submitted.
During tours of the plant.
areas
on October
2
and October 5,
the
inspector
found
two instances
where
the
doors
to posted
high
radiation areas
were not locked, although
the postings
and surveys
indicated that
the radiation levels
were greater
than
1,000
mrem
per hour.
The inspector informed licensee
management
representatives
that these
were additional examples of the item previously identified.
Licensee
management
representatives
discussed
several
actions
which were being taken
on this problem and stated
that these vill
be included in the response
to the item of noncompliance.
RII Rpt.
No. 50-324/78-23,
and 50-325/78-20
I-3
5.
Radiolo ical Environmental
Event
Re ort
a
~
By letter serial:
GD-78-2270
of August 20,
1978,
the
licensee
reported'a
situation
where
an unplanned
release
had been
made
from
the liquid radioactive
waste
system.
This
was
the result of an
improper
valve
line-up
which permitted
the discharge
of
a tank
which
was not planned
rather
than
the discharge
of
a tank which
was planned
and approved.
The letter also contained
actions which
were being taken to prevent further occurrences,
including revision
of the liquid release permit.
The
inspector
discussed
the situation with licensee
representa-
tives and reviewed the effluent records to verify>that the discharge
permit
and
records
reflected
the
actual
release.
A licensee
representative
informed the inspector that the discharge
procedure
and discharge
permit revision
was not yet complete;
the inspector
stated that this would be reviewed later (324/325/78-23-01).
~
~
~
6.
Reactor
Coolant Chemist
and Radiochemistr
Control
a
~
Technical Specifications Section 3.4.4
speci fies
the Limiting
Conditions for Operation
(LCO) for coolant chemistry under various
operating
conditions.
Technical Specification Section 4.4.4
specifies
the
surveillance
requirements
for
implementing
the
LCO's.
Parameters
to be monitored
are conductivity
and chloride
ion concentration.
The
inspector
reviewed
the plant
chemistry
records
for Units
1
and
2 for the
months
of June
and
September
1978, to verify that samples
were taken at the required frequencies,
results
were
acceptable
or appropriate
corrective
actions
were
taken
and that special
or more frequent
measurements
were
taken
when required for changes in operating conditions.
During the start-up
of Unit
2
on September
22-23,
the coolant
conductivity went
above limit of
2
umho/cm with the
temperature
above
212
degrees
Fahrenheit.
The
inspector
reviewed
the
chemistry
and
operator's
logs,
which
showed
that
the
maximum
conductivity
reached
was
10.62
umho/cm
and that
the limit of
2
umho/cm
was
exceeded
for approximately
26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />.
The operator's
log indicated that the start-up
was secured
when the conductivity
exceeded
ten
umho/cm
and
was held until the conductivity was less
than
two umho/cm.
The actions
taken during the start-up
appeared
to
be consistent
with.Technical Specifications Section 3.4.4.A.2.
A licensee
management
representative
informed the inspector that
a
Licensee
Event
Report'ould
be
submitted
as
the
conductivity
exceeded
the two umho/cm limit for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The inspector
had
no
further questions.
RII Rpt.
No. 50-324/78-23,
and 50-325/78-20
I-4
Technical
Specifications
Table
4.4.5-1
specifies
the
reactor
coolant
radiochemistry
analysis
requirements.
The
inspector
reviewed
the
chemistry
records
for
the
months
of
June
and
September
1978
and the
semi-annual
analyses
performed in May and
verified that
the results
were within the limits specified
in
Technical Specifications Section 3.4.5.
The
inspector
also
performed
the
calculations
for
dose
equivalent
for
three
sets
of isotopic data
and
confirmed the licensee's
results
and that
the results
were within limits.
The inspector
had
no
further questions.
7.
Li uid Radioactive
Waste Releases
Environmental
Technical Specifications
(ETS) Section
2.5.1 lists
the
specifications
for liquid waste
effluents.
Environmental
Technical Specifications Section 3.5.1 lists the specifications
for liquid waste
sampling
and monitoring.
The inspector
reviewed
twelve liquid waste
release
permits
and verified that
the
requirements
for average
concentrations,
cumulative releases,
use
of
waste
processing
equipment,
plant
records,
sampling
and
monitoring were
met.
The inspector also reviewed the semi-annual
effluent report for the first half,
1978 and verified compliance
with the
ETS limits for amounts
of activity discharged
in
a
quarter,
average
concentration,
and
special
reports.
The
inspector also performed calculations
on selected
liquid discharge
permits
to verify the results.
The
inspector
had
no further
questions.
b.
The
inspector
reviewed
completed
copies
of the waste
discharge
procedures
and verified that they were initiated off as
completed
and
were
attached
to
the discharge
permit.
The inspector
also
reviewed
the
permits
and
procedures
to verify that
action
was
taken
in accordance
with
ETS 3.5.1.c
for mixing
and with
3.5.1.d for two independent
samples
when the liquid waste monitor
was inoperable.
The inspector
had no further questions.
8.
Waste Dis osal
Re orts
Environmental
Technica1
Specifications
5.4.1
requires
that
'a
semi-
annual
environmental
and effluent report
be submitted
to the
NRC in
accordance
with
Regulatory
Guide
1.21.
Environmental
Technical Specification 2.5.3.c
requies
that reports
of radioactive solid waste
shipments
shall
be
submitted
with semi-annual
effluent report.
The
inspector
reviewed the report for the period January
through June
1978,
and verified that required data were submitted
as required.
The inspector
also
performed
calculations
based
on the
data
to spot-check
reported
values.
No computational errors were noted.
~~~
~
W ~
0
RII Rpt.
No. 50-324/78-23,
and 50-325/78-20
I-5
9.
Radiolo ical Surve
s
Technical Specifications Section 4.7.6
requires
that
sealed
radioactive
sources
containing greater
than
100
uCi beta
and/or
gamma
or
5
uCi
alpha activity shall
be
tested
for removable
contamination
every six months.
RC&T Instruction
7006 specifies
that all sources will be inventoried every six months
and licensed
sources
leak
tested.
The
inspector
reviewed
the
radioactive
source
records for licensed
and non-licensed
sources
and verified
that
the licensed
sources
were inventoried
and tested
as required
by the technical
specifications.
The inspector
noted that eight
sources
in unlicensed quantities
were not accounted
for during the
last inventory
as required
by RC&T 7006.
A licensee representative
investigated
and
informed the inspector
that
an
immediate
check
had
been
made
and
the
sources
located
at the
normal locations;
however,
since
they are installed
as
"bug" sources
on installed
instruments,
there
was
some
apparent
misunderstanding
by
the
technician
concerning
the
inventory
requirement.
The
licensee
representative
stated
the personnel
performing the inventory would
be reminded to verify the "bug" sources
as well; the inspector
had
no further questions.
b.
RC&T Instruction
7003 lists
the routine radiation
and
contami-
nation
surveys
which
are
to
be
taken
around
the plant.
The
inspector
reviewed the surveys for the weeks beginning August
14,
September
4 and September
25, and verified that the routine surveys
were being taken as required.
The inspector
had no further questions.
10.
Solid Waste Dis osal
Environmental
Technical Specifications 2.5.3.b
requires
that solid
wastes
shall
be monitored
and packaged
to assure
compliance with 10 CFR 20,
10
CFR 71,
and
49
CFR 171-178.
The inspector
reviewed the records
for shipments
and determined that the requirements for isotope identifi-
cation packaging,
surveys,
labeling and placarding
had apparently
been
met.
The inspector also determined that material shipped
as
Low Specific
Activity apparently
met the applicable
requirements
of 49
CFR and that
all materials
were transferred
to authorized
companies.
The inspector
had no further questions.
11.
Notification and
Re orts
The inspector
reviewed plant records
and discussed
topics with licensee
representatives
to determine if reports
and notifications were required
and were submitted in accordance
with the following requirements
during
calendar year 1978:
a.
Loss or theft of radioactive materials - 10 CFR 20.402
0
RII Rpt.
No. 50-324/78-23,
and 50-325/78-20
1-6
b.
Incidents - 10 CFR 20.403
c.
Based
upon this review,
the inspector
determined
that
no reports
or
notifications had been required
and had no further questions.
12.
Radiation Protection
Instruments
and
E ui ment
The inspector
reviewed calibration
and test
records
for various types
of portable
survey
instruments,
portable air monitors
and installed
area
radiation monitors
and verified that calibrations
and tests
were
performed
within the
time interval specified
in the applicable
RCPT
instructions,
that
calibration
results
met
established
acceptance
criteria,
and that the alarm set points for the area radiation monitors
were in accordance
with procedure
SD-11.
The inspector also verified
that monthly checks
of the
area
monitor alarm set points
were being
conducted
in accordance
with the
commitment
in CP&L letter NG-76-1207
of
September
13,
1976.
During tours
of plant
areas
the
inspector
observed
various
instruments
in use
or in service
and verified
that'urrent
calibration stickers
were affixed.
The inspect or noted
a minor
discrepancy
in the
data
on
several
calibration stickers;
this
was
immediately
corrected
by
licensee
representatives.
The
inspector
pointed
out
to
licensee
representatives
that this
discrepancy
was
previously
noted
in
IE Report
No. 77-28
and,
while it is minor, it
raises
questions
about
checkout of the instruments
before
use if it is
not
being identified.
This
comment
was
acknowledged
by
licensee
representatives.
The inspector
had no other questions.
13.
Exit Interview
At the conclusion
of the inspection
on October 6,
1978,
the inspector
met with licensee
representatives
(denoted in paragraph
1).
The inspector
summarized
the scope
and findings of the inspection.