ML16340B994
| ML16340B994 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/12/1981 |
| From: | Book H, North H, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML16340B995 | List: |
| References | |
| 50-275-81-16, NUDOCS 8109090186 | |
| Download: ML16340B994 (26) | |
See also: IR 05000275/1981016
Text
Report
No ~
50-275/81-16
U. S.
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
Docket No.
License
No
CPPR-39
Pacific Gas
and Electric Company
Safeguards
Group
P.
0.
Box 7442
San Francisco,
94106
FaciIity Name:
Diablo Canyon Unit
1
San Luis Obispo County, California
Inspection conduct d:
July 20-24~
1981
Inspectors:
- H. S. North, Radiation Specialist
Date Signed
Date Signed
Approved by:
Approved By:
F. A.
enslawsk
Chief, Reactor Radiation Protection
Section
H.
E. Book, Chief, Radiological Safety Branch
ate
igned
Date
igned
Summary;
Ins ection on Jul
20-24,
1981
Re ort No. 50-275/81-16
Areas
Ins ected:
Radiation protection,, organization, staffing and training,
general
emp oyee training in radiation protection
and emergency
response,
waste
management
procedures,
instrument calibration,
IE Circular followup,
preoperational
testing,
and fuel loading prerequisites.
This inspection
involved 37 inspector-hours
on site by one inspector.,
Results
Of the ten areas
inspected
no items of noncompliance
or deviations
were 1weent~fied.
810909018b
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ADDCK 05000275'.
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DETAILS
1.
Persons
Contacted
Station Staff
- R. Thornberry, Plant Manager
- W. Kaefer,
Technical Assistant to the Plant Manager
- J. Boots, Supervisor,
Chemistry
and Radiation Protection
(C&RP)
- W. O'ara,
Senior
C&RP Engineer
(E)
H. Fong,
C&RPE
M. Peterson,
C&RPE
- A. Taylor,
C&RPE
M. Mak,
C&RP Systems Analyst
R. Johnstone,
C&RP Technician
(T)
W. Scott,
Power Production Engineer
(PPE) - Bulletins and Circulars
R. Bliss, PPE-Training
W. Keyworth, Senior,
PPE-Emergency
Planning
and Licensing
- R. Twiddy, gA Supervisor
General
Construction
2.
W. Coley, Construction-Startup
Engineer
D. Shelley, Startup Engineer
Cor orate Office
- R. Howe - Nuclear Generation
Engineer
Contractor Personnel
J. Williford, Chem
Rad
(*Denotes those present at the exit interview.)
Chemistr
and Radiation Protection - Or anization, Staffin
and Trainin
IE Inspection Report No. 50-275/81-05,
described
the Chemistry
and
Radiation Protection
(C&RP) organization.
A revised organization
was
authorized effective July 20,
1981 .
The
new or gani zati on with
authorized
and existing staffing level is compared with that
previously described.
U
Position
Authorized'taf fin
New
Positions
presently
not'filled
Supervisor
C&RP
Senior
C&RP Engineer
(E)
C&RPE
L
C&RP Foreman
C&RP Systems
Analyst
C&RP Technicians
(T)
/
Ik
TOTAL
1,
2
t3 I
- 2 '
0
21
29,.
1
2
5
3
1
~25
37
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1
1
1
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SUPERVISOR
CSRP
SENIOR CSRP'E
EVACANT)
SENIOR CCRPE
RAOIATIOV PROTECTION
CHEHISTRY
CSRPE
TRAINING
CSRPE
CRAPE
CCRP
SYSTEHS ANALYST
CERP
TOREPAN
CCRP fCREPAN
CCRPE
RAG I ATION
IOI IVOR ING
SY4IEHS
CSRP
TECHNICIANS
CCRP fOREHAN
'EVACANT)
CERPE
HATER HANAGEHENT
{VACAlll)
The licensee
has concluded
a union agreement with the
C&RPTs which
provides for shift staffing consisting of two C&RPT's per shift, one
of which is ANSI 18.1 qualified.
The
C&RPT staff presently includes
nine ANSI/ANS 18.1 qualified (experience)
individuals and
seven which
do not meet the experience
requirements
of ANSI/ANS 18.1.
Since the last inspection,
previously referenced,
a total of six
C&RPTs and two C&RP Foreman
have
had four weeks
on the job experience
at Trojan during refueling operations.
One of the
C&RPEs attended
a one week reactor simulator training course.
The
C&RP Systems Analyst
received 3-4 weeks of training at Hewlett-Packard
(HP} on the
HP1000
computer.
A HP1000 computer is located in the
C&RP office area.
With the exception of one recently hired
C&RPT all (15) of the
C&RPTs have essentially
completed
(98-100K complete)
the
training required
by the licensees
Administrative Procedure
B-250,
Radiation
and Process
Monitor Trainin
.
The use of the title, Chemistry
an
Ra sat>on Protection Technician, is recent at this facility.
C&RPTs were formerly called Radiation
and Process
Monitors.
The
training requirements
contained in Procedure
B-250 were detailed in
IE Inspection Report No. 50-275/81-05,
paragraph
3.
Training
records of four randomly selected
C&RPTs were examined.
No further questions
or unresolved
items remain in this area.
No items of noncompliance
were identified.
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IE Inspection Report No."50-275/81-05,
paragraph
3, discussed
'the
requirements
of Administrative Procedure,No.
B-2'General
Re uirements
for Trainin
of On-Site Personnel
and.described
the training required
for individuals other than operators
and
C8RP personnel.
The status
of general
employee training in the areas
of radiation protection
and
emergency
planning was examined.
The radiation protection training
is provided in several
courses of varying level
and duration
as outlined
below.
RC
UIREO FAR ACCESS
COURSE
NO.
TITLE
COMIENTS
LENGTII
NOURS
ESCORTEO
UNESCORTEO
FROIEC
0
AREA
N ROLL 0
AREt1
RPAIOO
Radiation Protection for Engineers
(Exam-70'A passing)
(Nigher Technical Level)
22
RPA200/
RPOIOO
RP0650
Radiation Control Standards
and Procedures
(Exam-70% passing)
( Includes Respiratory Protection)
(Incl'uded in RP0300
and RPA420)
RPA300
Radiation Protection for Radiation Worker Supervisors
and Engineers
(Exam-70% passing)
(iligher Technical
Level-No practical factors)
20
RP0300
Introduction to Radiation Protection
(No Exam)
1-2
RPA400
Radiation Protection for Unescorted Radiation Workers
Exam-70K passing)
Hay be combined with respiratory protection
and
RPC700)
18
RPA420
Radiation Protection for Escorted Radiation Workers
(not applicable to plant staff personnel)
12
RPC700
Oressing
Procedure
(No Exam)
(Practical
Factors)
At the time of the inspection
a total of ]29 individuals
had not
completed all the required initial training and
17 had not completed
required retraining.
Of the training remaining in this area approximately
65K can
be accomplished with two or less
hours of class
time.
In the area of emergency
planning the licensee
provides three
classroom training courses for the plant staff.
EPD350 - Maintenance
and
Re air Under Radiolo ical
Emer enc
Condition-
3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />
Training of maintenance
personnel
is complete.
EPD500 - Preview of Diablo Can
on
Emer enc
Plan
and Procedures
- (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s}
EPD600 - Basic Actions in the Event of an Emer'enc
On-Site -
'(1 hour}
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In addition
a one hour,
non classroom,
presentation
identified as,
EPD 650-
Emer enc
Re ortin 'nd Si nal
Res onse,
is provided to all
plant staff personnel.
total of 78 members of the plant staff have
not completed
the required classroom training.
Of this number
24 require only one hours training.
The remaining
54 are principally
auxiliary operators
who are scheduled
to attend
the
EPD-500 course.
The licensee
plans to establish
a restricted
area which is larger
than the protected area.
As a result
PGRE General
Construction
(GC)
and contractor personnel will be required"to enter the restricted
area to gain access
to the protected
area in which Unit 2 is located.
Units
1 and
2 are physically~:separated
by barriers inplant and
fences outside the plant.
>, Trai,ning" to satisfy'he
requirements
of
10 CFR 19. 12 and response,'o,emer'gencies
wi,ll be provided,-'to such
individuals by GC or contractor supervisory.personnel
in, accordance
with guidance
provided by -the -plant staff.~',GC or contractor personnel
requiring access
to Unit l,will"be "required to satisfy the )nit
1
training requirements
app'ropr'iate for,.the category of access prior
to entry into Unit l.,; ". ';~," .', "
At the time of the inspection': the, licensee'>was
preparj.ng
and the
inspector
reviewed
a draft copy of:,a procedure,":.General,
Procedure for
Diablo Can
on Power'Plant~Site
Access', "his,procedure
spec>>es
that
access
to any area will be.;den1ed
if,the<prerequisi,te,;training
has
not been satisfactorily comp1eted.
Qe draft procedure'ddresses
security,
owner, controlled', protected
and vi'tal areas,
radiological
restricted,
controlled and'irborne radioactivity areas.
At the
exit interview the inspector
expressed
concern regarding
the status
of general
employee training.
The inspector
commented that after
license
issuance
and the establishment
of,.the restricted
area,
the
failure to complete required training ~prior. to~ permitting access
could result in noncompliance.
The 'Plant Manager stated that on
license
issuance
and the establishment
of the restricted
area,
access
to the restricted
and protected
areas will be denied to any individual
who has not completed the prerequiste training.
Based
on the Plant Manager's
commitment
no further questions
or
unresolved
items remain in this area.
No i tems of noncompl iance were identi fied.
Procedures-Waste
Mana ement
IE Inspection
Reports
Nos. 50-275/80-04,
paragraph
6 and 50;275/81-05,
paragraph
7, identified various procedures
which were incomplete.
The following procedures
which have
been
completed
and approved
by
the Plant Staff Review Committee
(PSRC) were examined
by the insjectpr.
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A-5, Li uid Radwaste
Dischar
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A-8, Offsite Dose Calculations ."
E-4, Outfall
Sam lin
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PSRC approval of Procedure,<A-6,
"Gaseous
Radwas'te
Dischar
e'-Mana ement,
which was reviewed
by the ipspec'tor;- .is reauired for low power testing.
Procedures,
A-4, Chemistr
Laborator
,',Calibration Schedule.and
G-ll,
Packa in , Stora
e and Inve'ntor
of Solid Radioactive
Waste',
which
have not been
completed
and approved are 'Iiot',-,required for fuel loading
or low power testing.
No remaining procedures
selected.:for
review prior
to fuel loading remain outstanding.
t.
No items of noncompliance
were identified.
Area, Process
and Effluent Monitor Cal,ibration,
IE Inspection Report No. 50-275/81-05,
paragraph
8, identified previous
IE Inspection
Reports in which instrument calibration
had
been discussed
and described
the licensees
planned
methods of calibration.
The
calibration of the
FSAR identified area,
process
and effluent monitoring
instruments is substantially
complete.
During the calibration process
the licensee
found it necessary
to modify some instrument
systems
to achieve the design
response,
stability and reliability, e.g.
all Westinghouse
gamma scintillation detectors
required the addition
of a licensee fabricated preamplifier to permit operation of the
detectors at the moderate voltage necessary
to provide reasonable
photomultiplier life.
The licensee
performed rigorous calibrations
of the various
systems
using the techniques
described
in IE Inspection
Report No. 50-275/81-05,
paragraph
8.
The initial calibration included
establishing
the statistical
variance of the detectors
in the installed
systems
and available spares
where sufficient detectors
were available.
The licensee
confirmed independently that the variance in the
detectors
tested
was essentially identical with the variance stated
by the manufacturer which had
been established
on
a significantly larger
sample.
Acceptance criteria for detector
response
during subsequent
calibrations is based
on the performance of the detector during the
initial calibration and further requires that the detector
response
fall within the statictical
range established for the specific detector
type.
The licensee
was preparing individual surveillance test
procedures for each specific monitor.
Copies of draft procedures
were
examined
by the inspector at the time of the inspection.
The draft procedures
included the following informatiog;
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Responsibility:
C&RPE (Test Director)
Shift Foreman
Instrument
and Control Supervisor
Frequency:
l'ech.
Spec.. -,18 months or on
detector,'reamplif'ier,
or major+component
replacement
'-.
Functional test. performed concurrently'.
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Scope:
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Acceptance CriteI;ia':, -",
Prerequsites:
.
Precautions
"and. Limitations
Pretest
alignment
Operation - step
by step~ ~
.
'eferences:
Manuals
Attachments:
Circuit diagrams
The following FSAR identified monitoring systems
have
been cali,brated
and procedures
prepared:
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Area
Gas
Desi nation
0-R-1
1-R-2
1-R-4
1-R-5
1-R-6
1-R-7
0-R-8
1-R-9
0-R-10
1-R-12
1-R-14
A&B
1-R-15
1-R-22
1-R-27
Location
S stem
Control
Room
Containment
Charging
Pump
Room
Spent
Fuel Building
Sampling
Room
Incore Instrumentation
Drumming Station
New Fuel Storage
Auxiliary Building Control
Board
Containment Radioactive
Gas
Plant Vent Gas
and
Backup
Condenser
Air Ejector
Gas
Decay Tank Discharge
Steam
Gen.
Blowdown Vent
Air Particulate
1-R-11
1-R-13
0-R-21
1-R-28
A&B
Containment Air Particulate
RHR Exhaust
Duct Air Particulate
Control
Room Air Particulate
Plant Vent Air Pa-rticulate
and
Backup
H
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Liquid
1-R-17
ASB
0-R-18
1-R-19
0-R-20
1-R-23
Component Cooling Liquid and Backup
Waste
System Discharge Liquid
Steam Generator Liquid Sample
Eqpt. Drain Receivers
Recirculation
Steam
Gen.
Blowdown to Discharge
Tunnel
The following FSAR identified monitoring systems
had not been calibrated
at the time of the inspection.
b.
Area
Desi nation
1-R-24
1-R-25
1-R-26
Location/S stem
Plant Vent Iodine
Control
Room Ventilation Intake
Control
Room Ventilation Intake
The following monitoring systems
not identified in the
FSAR have
been
calibrated
and procedures
prepared.
c ~
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Liquid
Descri tion
RE-3
Location
S stem
Oily Water Separator
Discharge
The following monitoring systems
not identified in the
FSAR have not
been calibrated or procedures
prepared.
The majority of these monitors
are associated
with post accident monitoring.
Area
Desi nation
RE-30,31
RE-34
RE-35
RE-36
RE-41
RE-42
RE-43
RE-48
RE-60
RE-61
RE-62
RE-63
RE-64
RE-65
RE-71-74
Location
S stem
Status-foot
note
Containment
Area Monitor (High
Range ion chamber
(1)
Plant Vent Monitor ALARA Area
Honitor (1)
Plant Vent Iodine Sampler
ALARA Area
Monitor (1)
Iodine Grab
Sample
(FHB) Area Monitor (1)
Gas
Decay
Tank Area Monitor (1, 2-1) (2)
Gas
Decay
Tank Area Monitor (1, 2-2) (2)
Gas 'Decay
Tank Area Monitor (1, 2-3} (2)
Post Accident Sampling
Room (Sentry
System)
(3)
TSC. Office Area Monitor (4)
TSC Ops Center/RMS Area Monitor (4)
TSC Computation
Center Area Monitor (4)
NRC Office Area Monitor (4)
HVAC Equipment-..Room
Area Monitor (4}
TSC Laboratory,'Area, Monitor (4)
Hain Stea'm Line Monitors (3}
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Gas
RE-29
RE-33
RE-51-54
RE-67
RE-69
Air Particulate
RE-66
RE-68
Plant Vent Gross
Gamma Monitor (1)
Plant Vent Noble Gas.Monitor (1)
Control
Room Ventilation Intake
Air Monitors (1)
(Control
Room Pressurization
System)
TSC Noble
Gas Monitor (1)
TSC Laboratory Noble Gas Monitor (1}
TSC Air Particulate
Monitor (1)
TSC Laboratory Air Particulate Monitor (1)
Iodine-
Liquid
RE-32
RE-16
Plant Vent Iodine Monitor (1)
Condensate
Demineralizer
Regenerant
Solution Effluent Monitor (3)
(1) Installed - Not released
by construction
(2) Installed - released
by construction
(3) Not Installed
(4) Installed - status
not determined
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The inspector
examined and,discussed
with licensee
personnel
calibration records
and, pro>>ced6res for selected
calibrated
.
monitors which were typical, of- the monitoring systems installed,
see sections
a.
and c. above%
The, specific records
examined
were for
the following monitors:
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. Area Monitor, ", o; ~;, ',-$-,.6-- -'", ~--,:,-->>'ampling'oom
Radiogas
Monitor~,---; > '1-R;14'&B j,',
', .Plant Veldt'Gas
and Backup
Radiogas in Liquid
" ', i;
'onitor
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'~ .,
1,.-R-27, ),
" '-'
Steam'e'n.:Blowdown
Vent
Air Particulate
Monitor
.,;",-'0-R-21 +";:::,
":
Control 'Room Air Particulate
Liquid Monitor
'l; " O-R-18,
<",
Haste
System Discharge Liquid
Liquid Monitor
1-R-19 " ".'team
Generator
Liquid Sample
Radiogas
Monitor
1-R-22
Gas
Decay
Tank
Gas Discharge
Sources
used in the calibrations, included in. each
case
a calibrated
source supplied
by the instrument,ma'nufacturer.
which was used to
verify that the monitoring system performed as'escribed
in the vendors
initial calibration.
Additional licensee fabricated
and calibrated
sources
were used to confirm energy
and range
response
of the
instrument.
In addition area monitors were calibrated
on the
licensees
instrument calibration range at dose rates
which were
verified using
an
NBS certified Victoreen R-meter.
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inspector,
established
that the initial area monitor ala'rm set
points were as specified in the
FSAR, confirmed that the calibration
procedures
were as described
in the
FSAR and that sensitivities of
proc'ess
and effluent monitoring systems
were specified in the
FSAR.
In addition the inspector verified that the acceptance
criteria
contained in the individual instrument calbiration procedures
requires
the verification of proper operation of any specified
action, e.g.
alarm, annunciator
or valve actuation.
lilith repect to
calibrated
systems identified in sections
a.
and c.
above
no questions
remain outstanding.
The, calibrations
and calibration
procedures for uncalibrated monitoring'y'stems
both
FSAR identified
and those not so identified, sections
b. 'and d. above, will be examined
during
a subsequent
inspection.
(81-05-02)'o
items of noncompliance 'were>,identified.
IE Bulletin Circular Foll'owu
', ',']~"-;,~~.~",
The licensee
has received," distributed,, an'd has'aken
or is taking
appropriate
action" in response
~to:-.*';-.: =~.- ":>
IE Circular No.
81-07.
",Coritrol'of'adi'oadtivel'oritaminated Material".
Responsibs
1 ity assigned,"action,not)
complete -.,'C8107" l;.
IE Circular
No. 81-09
",'-'Containment. Effluent >Jater.that
.B
asses
Radi oacti vit
Nonitor".
Review complete awaiting
PSRC review.
".(ICS]09)
,."-
'*-'-
No response
was required to'either c'ircular.
No items of noncompliance
were identified.
Preo erational
Testin
r
The inspector
was informed that the following preoperational
tests
were complete but had not been
reviewed
by
PSRC or accepted
for operations;,
Test No.
Titie
19.4
23.3
38.4
Spent Filter Transfer
System
Preop Test of Logic Controls for Auxiliary and
Fuel Handling Building Ventilation System
Radiation Monitoring System
No items of noncompliance
were identified.
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8.
Fuel Loadin
FL
and Full Power
Prere uisites
The inspector
reviewed several
Task Action Plan
(TAP) items in
accordance
with Inspection
and Enforcement
Temporary Instruction (TI}
2514/01
Revision 2.
The results of this inspection
are
as follows:
a.
TAP II.F.l, Additional Accident Monitoring Instrumentation,
(Item 1) (FL)
~Summar
TI2514/01 Revision
2 and
NUREG 0737 enclosure
2,
page 2-7, specify that procedures for accident monitoring
instrumentation
are required for fuel loading.
b.
C.
Findin
s and Conclusions:
A contractor to the licensee
was
preparing the procedure at the time of the inspection.
The
proposed;.
content of the procedure
was discussed
with the
licensee's
representative
at the time, of the inspection.
In an
August 7,
1981 telephone
conversation
a, licensee
representative
stated that the procedure will prob'ably
be submitted to the
PSRC
during the week of August 10-14,
1981.
The licensee
stated that
a copy of the approved procedure
would be maile'd 'to the inspector
for review after, approval- by the
PSRC.
This .item remains
open.
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III.A.l.l. Emergency;
Preparedness,-
Short.,Term
'(FL')'-~'Summar:
NUREG 0737, paqe'II.A.2-1, specified'that,
"Each
nuclear facility shall=upgrade its emergency
plans 'to provide
'easonable
assurance
th'atqadequate
protective measures.
can and
will be taken iq.the event-of
a radiological. emergency."
Supplement
No.. 12 to,'S'afety" EvaluatiohIaReporut,-'I, (SER).Diablo
Canyon Nuclear Power,".Pl'hnt,"-Unit'sisal'ndt2,,no'tes
on-.page III-2
and III-3 that thj'li'censee
req'u'ested
and~'was graritedelief
from items III.A.l.1~and=~IvII'.A. 2.", fourth'e'r,
"The'FEMA/NRC Steering
Committee
had previously. specifically approved
emer'gency
preparedness
at Diablo Canyon for low"power, taesting,'on
an int'crim"'basis."
The
SER statement
concludes.
~"The-'staff technical position thus
remains
that adequate
emergency
preparedne'ss
is in place for fuel load and
low-power operation."
Findin
s and Conclusions:
.The license'es-'emergency
preparedness
is adequate
to load fuel and for, low power.'testing.
This item is
considered
closed.
J
III.A.1.2.
Upgrade
Emergency Support Facilities
(FL)
~Summar
The licensee is to a establish
a Technical
Support
Center
(TSC) in the flying buttress
area of the Unit 2 turbine
building, habitable to the
same
degree
as the control
room, with
a capability to display plant status
conditions.
An Operations
Support Center
(OSC) located in the security building, is to be
provided with telephone
as well as radiocommunications
and two
evacuation kits.,=A temporary,
Emergency Operations Facility (EOF)
is to be located in a,trailer. at the'an
Luis Obispo County Sheriffs
Office with the habitability and- data display facilities
specified in NUREG'-0696.
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Findin s and Conclusions:
The licensee
has established
the
TSC,
OSC and
EOF as described.
Communications,
telephone
and radio,
exist and are operational.
The Harris computer in the
TSC, which
can retain,
and display up to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of data from the P-250
Plant Operations
Computer in either the
and operating.
This item is considered
closed.
III.D.3.3 Inplant Radiation Honitorin9 (FL)
~
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Summar
page III.B.3.3-1 requires that each
icensee
provide equipment,
procedures
and training for inplant,
post accident,
iodine sampling
and analysis.
Findin s and .Conclusions:
The licensee
has available
17,
RadeCo
model
HD-28
1 cfm , 8,
RadeCo
Model
HD-28B (2 cfm), line
operated,
4,
RadeCo
model
H09C (5 cfm) external
battery operated
and
4 RadeCo
model
H09B2 (5 cfm) internal battery operated
portable
air samplers.
The licensee
has
on hand approximately
200
silver zeolite iodine sampling cartridges.
Iodine sample analysis
capability includes
several
calibrated, intrinsic Ge detector,
multichannel
analyzer
systems
in the counting
room and
an
addition identical system,in the
TSC laboratory.
A procedure
In
lant Iodine
Sam lin
Pro ram under
Emer enc
Conditions,
was
.eing prepare
at t e time o t e inspection.
This item
is considered
closed.
II.B.3 Post Accident Sampling
(FP)
~Summar
RUREG-0737,
page 2-5, II.B.3 items
3 and
4 require
the licensee
to have procedures
by FP and have completed actions
on post accident sampling
by January
1, 1982.
Findin s and'Conclusions:
The licensee
has prepared
procedures
CAP G-2
Interim Post-LOCA'Sam lin
S stem
IPLSS
and CAP"G-l, Access
to IPLSS
rea
Post
ccident
Sam le Pre aration
Handlin
and
~Anal sis.
Between
10 and
14
C&RPT s have
been given approximately
three
hours training in each procedure.
The
IPLSS system is
essentially
complete
and was undergoing final hydro testing at
the time of the inspection.
The
IPLSS provides for purging
sampling lines and is vented to the HEPA-Charcoal filtered
auxiliary building vent system.
The system provides for the
collection of diluted liquid and gas
samples
and gas
chromatograph
sample analysis.
The licensee
has evaluated
the
time required to complete the specified analytical
procedures.
It was estimated that one technician would require approximately
three
and
one half hours to complete the series
working alone,
or two hours with two technicians
working in concert.
The
construction
and installation of the'permanent,
"Sentry", system
is well advanced.
This item remains
open pending completion of
the two systems
wPich will be examined during
a subsequent
inspection.
(81-16-01 ) .
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9.
Exit Interview
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At the conclusion of the inspec'tijn; the inspection findings were
summarized for those individuals denoted in paragraph l.
i The licensee
was advised that no items, of noncompliance
had
been identified.
The inspector expressed'oncern'or
theekel,of'general
eqployee
training (paragraph
3 of'deta'ils').
The plant 'manager stated, that
on license
issuance,
and the establishment
of a restricted area,
individuals who had not completed
the trairling requirements
would be
denied
access
to the restricted:=area.
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The inspector identified and requested
copies of a number of procedures
after their review and approval
by the
PSRC.
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