ML18038B616
| ML18038B616 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/12/1996 |
| From: | Peebles T NRC Office of Inspection & Enforcement (IE Region II) |
| To: | Kingsley O Tennessee Valley Authority |
| References | |
| NUDOCS 9602210183 | |
| Download: ML18038B616 (12) | |
See also: IR 05000259/1996300
Text
February
12,
1996
Valley Authority
ATTN:
Hr. Oliver D. Kingsley, Jr.
President,
TVA Nuclear
and
Chief Nuclear Officer
6A Lookout Place
1101 Harket Street
Chattanooga,
TN
37402-.2801
Gentlemen:
SUBJECT.:
REACTOR OPERATOR
AND SENIOR
REACTOR OPERATOR LICENSING EXAMINATIONS
EXAMINATION REPORT
NOS. 50-259/96-300,
50-260/96-300,
AND
50-296/96-300
The purpose'of this letter i's to confirm arrangements
made in
a telephone
conversation
on February
7,
1996,
between
Hr. Dale Hill, Manager,
Operations
Training,
and Mr..Jim Moorman,
License
Examiner,
NRC Reg'i'on II Operator
Licensing
and
Human Performance
Branch, for the administration of licensing
examinations
at the
Browns Ferry Nuclear Plant.
The examination preparation
visit is scheduled for June 3-7,
1996.
The written examinations
are scheduled
for June
14,
1996,
and the operating
examinations
are scheduled for
June
17-21,
1996.
Your staff will be given
an opportunity to review the
licensing examinations
in accordance
with the guidelines in Revision
7 of
"Operator Licensing Examiner Standards,"
(ES-201,
Attachment
4)
during the week of Hay .27,
1996.
C
To prepare
the examinations
and meet the above schedule, it will be necessary
for your staff to furnish the reference materials specified in the enclosed
List of Reference
Materials
by March 15,
1996'ny delay in receiving
approved
and indexed reference
material
or the submittal of inadequate
or
.incomplete reference
material
may result in the examinations
being
rescheduled.
The
NRC will prepare
and administer the written examinations
in accordance
with ES-401
and
ES-402 of 'NUREG-1021.
In order to conduct the requested
examinations, it will be necessary
for, your staff to provide adequate
space
and accommodations
on the date
noted
above.
The NRC's guidelines for
administering
the written examinations
are described
in ES-402,
Attachment
1.
The
NRC will prepare
and administer the operating tests
in accordance
with
and
ES-302 of NUREG-1021.
In order to conduct the requested
operating
tests, it will be necessary
for your staff to make the simulation facility
available
on the dates
noted
above.
Your staff should retain the original
simulator performance
data (e.g.,
system pressures,
temperatures,
and levels)
generated
during the dynamic operating tests until the examination results
are
final.
Attachment
2,
and ES-302,
Attachment
1, contain
a number of NRC
.policies
and guidelines that will be in effect while the written examination
and operating tests
are being. administered.
2iOj.08
9602210183
'P602i6
ADOCK 05000259
V
II
0'gy;
Your staff should submit preliminary reactor operator
and senior reactor
operator license applications
and waiver requests
at least
30 days before the
first examination
date
so that the
NRC will be able to review the applications
and the medical certifications
and evaluate
any requested
waivers.
If the
applications
are not .received
at least
30 days before the examination date,
a
postponement
may be necessary.
Final, signed applications certifying that all
training has
been
completed
should
be submitted at least
14 days before the
first examination date.
This request
is covered
by Office of Management
and Budget
(OHB) Clearance
Number 3150-0101,
which expires April 30,. 1997.
The estimated
average
burden
is 7.7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> per response,
including gathering,
xeroxing,
and mailing the
required material.
Send
comments
regarding this burden estimate
or any other
aspect of this collection of information, including suggestions
for reducing
this burden,
to the Information and Records
Management
Branch,
T-6 F33,
Division of Information Support Services,
Office of Information Resources
Hanagement,
U. S. Nuclear Regulatory
Commission,
D.
C.
20555;
and
to the Paperwork Reduction Project
(3150-0101),
Office of Information and
Regulatory Affairs, NEOB-10202, Office of Management
and Budget,
D.
C.
20503
'rom
the requested
reference
materials identified in the enclosure,
we would
appreciate
retaining your
and
AOPs for reference
use in our Incident
Response
Center.
If you have
any concerns
about this proposed
use,
please
contact
me.
Thank you for your cooperation
in this matter.
Hr. Hill has
been
advised of
the policies
and guidelines
referenced
in this letter.
If you have
any
questions
regarding the NRC's examination
procedures
and guidelines,
please
contact
me at (404) 331-5541.
Sincerely,
ORIGINAL SIGNED
BY T. A.
PEEBLES
Thomas
A. Peebles,
Chief
Operator Licensing
and
Human
Performance
Branch
Division of 'Reactor Safety
Docket Nos.
50-259,
50-260,
50-296
License
Nos.
Enclosure:
List of. Reference
Materials
cc w/encl:
(See
page
3)
cc w/encl:
Hr. 0. Zeringue,
Sr Vice President
Nuclear Operations
Valley Authority
3B Lookout Place
1101 Market Street
Chattanooga,
TN
37402-2801
Dr. Mark 0. Medford, Vice President
Engineering
and Technical
Services
Valley, Authority
3B Lookout Place
1101 Harket Street
Chattanooga,
TN
37402-2801
Hr.
D.
E.. Nunn, Vice President
New Plant Completion
Valley Authority
38 Lookout Place
1101 Market Street
Chattanooga,
TN
37402-2801
Mr. P.
P. Carier,
Manager
Corporate
Licensing
Valley Authority
4G, Blue Ridge
1101 Market Street
Chattanooga,
TN 37402-2801
Hr. T.
D. Shriver,
Hanager
Nuclear Assurance
and Licensing
Browns Ferry Nuclear 'Plant
Valley Authority
P. 0.
Box 2000
Decatur,
35602
Mr. Pedro Salas,, Site Licensing Mgr
Browns Ferry Nuclear Plant
Valley Authority
P. 0.
Box 2000
Decatur,
35602
Chairman
Limestone
County Commission
310 West Washington Street
Athens,
35611
Mr.'. Machon, Site Vice President
Browns Ferry Nuclear Plant
Valley Authority
P. 0.
Box '2000
.Decatur,
35602
TVA Representative
Valley Authority
11921 Rockville Pike
Suite
402
Rockville,
HD
20852
General
Counsel
Valley Authority
ET llH
400 West Summit Hill Drive
Knoxville, TN
37902
State
Health Officer
Alabama Department of Public Health
434 Monroe Street
Montgomery,
36130-1701
Hr. C. T. Dexter, Training Manager
Browns Ferry Nuclear Plant
P. 0.
Box 2000
Decatur,
35609-2000
Hr. L. B. Durham
.Nuclear Training Manager
5F Lookout Place
1101 Market Street
Chattanooga,
TN 37402-2801
Distribution w encl:
E.
W. Merschoff, RII
J.
F. Williams,
F. J.
Hebdon,
S.
H. Shaeffer,
RII
G. T. HacDonald,
RII
G. A. Hallstrom, RII
L. Wert,
Browns Ferry SRI
DATE
02/
/96
OFFICE
RII:DRS
SIGNATURE
NAME
JMo rm
ihm/fr
RII:DRS
Lesser
02/.g /96
RI:DRS
02/ 496
02/
/96
02 /
/ 96
02 /
/ 96
YES
N
COPY'S
NO
E
NO
.
YES
NO
OFFICIAL RECORO
CUIIEIIT IIAHE:
- KLAKBROKI30090DA.JHM
YES
NO
YES
NO
0
0
0"
List of Reference
Materi al s
Page
1 of 3 pages
1.
Materials
used
by the facility licensee to ensure operator
competency:
'a ~
The following types of materials
used to train applicants for
initial
RO and
SRO licensing should
be provided.
The material
should
be complete, .comprehensive,
and of sufficient detai1
.to
support the deve1opment
of accurate
and val:id examinations
without
being redundant.
learning objectives,
student
handouts,
and'esson
plans
system descriptions
of all operationally relevant flow paths,
components,
controls,
and instrumentation
material
used to clarify and strengthen
understanding
of
abnormal,
abnormal,
and emergency
operating
procedures
complete,
operationally useful descriptions of all safety
system interactions,and,
where available,
balance-of-plant
,system interactions
under emergency
and abnormal
conditions,
including consequences
of: anticipated
operator errors,
maintenance
errors,
and equipment failures
b.
guestions
and
answers specific to the facility training program that
may be used in the written examinations
or operating tests
(voluntary by facility licensee).
c.
. Copies of facility-generated
simulator scenarios
that expose
the
applicants to abnormal
and emergency
conditions,
including. degraded
pressure
control, degraded
heat
removal capabil.ity, and'ontainment
challenges,
during all modes of operation,
including low power
conditions.
A description of the-scenarios
used for the training
'class
may also
be provided (voluntary by facility licensee).
d.
All job performance
measures
(JPMs)
used to ascertain
the competen'ce
of the operators
in performing tasks within the control
room complex
and outside the control
room (i.e., local operations)
as identified
in the facil'ity JTA.
JPMs should-evaluate
operator responsibilities
during normal,
abnormal,
and emergency conditions
and events
and
during all modes
o'f operation,
including cold shutdown,
low, and
full power.
2.
Complete
index of procedures
(incl.uding all categories
sent).
3.
All administrative
procedures
applicable to reactor operation or safety.
4.
All integrated plant procedures
(normal or general
operating
procedures).
5.
All emergency
procedures
(emergency instructions,
abnormal
or special
procedures).
Enclosure
0
List of Reference
Materials
Page
2 of 3 pages
6.
7.
Standing orders
(important orders that are safety-related
and
may modify
the regular procedures).
Surveillance
procedures
that are run frequently (i.e., weekly) or that
can
be run on the simulator.
8.
Fuel handling
and core loading .procedures (if SRO appl-icants will be
examined).
9.
All annunciator
and alarm procedures.
10.
Radiation protection
manual
(radiation control
manual
or procedures.
11.
Emergency plan implementing procedures.
12.
Technical Specifications
(and interpretations,
-if available) for all
units for which licenses
are sought.
(If merits Tech Specs,
include all
removed
programs
such
as
ODCH, etc.)
13.
System operating
procedures.
14.
Technical
data
book,
and plant curve information as
used
by operators,
and facility precautions,
limitations,
and set points document.
15.
The following, information pertaining to the simulation facility:
a.
List of all initial conditions.
b.
List of all'alfunctions with identification numbers.
C.
Malfunction cause
and effect information and
a concise description
of the expected result or range of results that will occur
upon
initiation, including an indication of which annunciators will be
actuated.
d.
A description of the simulator's failure capabilities for valves,
breakers,
indicators,
and alarms.
e.
The range of severity of each variable malfunction (e.g.,
the size
of a reactor coolant or steam leak or the rate of a component
failure such
as
a feed
pump, turbine generator,
or major valve).
g.
A list of modeling conditions (e.g., simplifications,
assumptions,
and limits) and problems that may affect the examination.
A list of any
known performance test discrepancies
not yet
corrected.
Enclosure
l
l
A
II
I
List of Reference
Materi al s
Page
3 of 3 pages
h.
A list of differences
between
the simulator
and the reference
plant's control room.
Simulator instructors'anual.
16.
Any'additional plant-specific material that has
been requested
by the
examiners
to develop examinations that meet the guidelines of these
Standards
and the regulations.
Enclosure
Cl
0