ML18033A847
| ML18033A847 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/18/1989 |
| From: | Wilson B Office of Nuclear Reactor Regulation |
| To: | Kingsley O Tennessee Valley Authority |
| References | |
| NUDOCS 8908010174 | |
| Download: ML18033A847 (6) | |
See also: IR 05000259/1989010
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
CCESSION NBR:8908010174
DOC.DATE: 89/07/18
NOTARIZED: NO
DOCKET
g
FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee
05000259
50-260
Browns Ferry Nuclear Power Station, Unit 2, Tennessee
05000260
50-296
Browns Ferry Nuclear Power Station, Unit 3, Tennessee
05000296
AUTH.NAME
AUTHOR AFFILIATION
WILSON,B.A.
Assistant Director for Inspection
Programs
RECIP.NAME
RECIPIENT AFFILIATION
KXNGSLEY,O.D.
Valley Authority
SUBJECT:
Ack receipt of 890614 ltr informing NRC of steps
taken to
correct violations noted in IRs 50-259,260
& 296/89-10.
DISTRIBUTXON CODE:
IE01D
COPIES
RECEIVED:LTR
ENCL
SIZE:
TITLE: General
(50 Dkt)-Insp Rept/Notice of Violation Response
NOTES:1
R.
1
R.
1
R.
Copy each to: B.Wilson,D.M.Crutchfield,B.D.Liaw,S.Black
Pierson,
Copy each to: S.Black,D.M.Crutchfield,B.D.Liaw,
Pierson,B.Wilson
Copy each to:
S. Black,D.M.Crutchfield,B.D.Liaw,
Pierson,B.Wilson
05000259
05000260
05000296
D
RECIPIENT
ID CODE/NAME
ERNAL: ACRS
AEOD/DEIIB
DEDRO
NRR/DEST DIR
NRR/DOEA DIR 11
NRR/DREP/RPB
10
NUDOCS-ABSTRACT
OGC/HDS2
RES MORISSEAU,D
EXTERNAL: LPDR
NOTES:
COPIES
LTTR ENCL
1
1
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1
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2
2
1
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5
5
RECIPIENT
ID CODE/NAME
GEARS",G
AEOD/TPAD
NRR SHANKMAN,S
NRR/DLPQ/PEB
NRR/DREP/EPB
10
NRR/PMAS/ILRB12
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FILE
01
NRC PDR
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D
S
Docket Nos.
50-259,
50-260,
50-296
License
Nos.
Mr. Oliver D. Kingsley, Jr.
Senior Vice President,
Nuclear
Power
Valley Authority
6N 38A Lookout Place
1101 Market Street
Chattanooga,
TN
37402-2801
Dear Mr. Kingsley:
'UBJECT:
NRC
INSPECTION
REPORT
NOS. 50-259/89-10,
50-260/89-10,
and
50-296/89-10
This is in reference
to your
response
of June
14,
1989,
to our Notice of
Violation issued
on
May
15,
1989,
concerning
activities
conducted
at your
Browns
Ferry facility.
In that letter,
you responded
to two violations cited
in Inspection
Report
Numbers 50-259/89-10,
50-260/89-10,
and 50-296/89-10 that
resulted
from the discovery of non-seismically qualified buried yard piping.
You admitted to Violation B,
and denied Violation A.
We
have
evaluated
your response
to Violation
B and
found that it meets
the
requirements
of
We will examine
the
implementation
of your
corrective actions during future inspections.
After careful
consideration
of the
bases
for your denial
of Violation A,
we
have
concluded for the
reasons
presented
in the enclosure
to the letter, that
the violation occurred
as
stated
in the Notice of Violation.
Therefore,
in
accordance
with 10 CFR 2.201(a),
please
submit to this office within 30 days
of the date
of this letter
a written statement
describing
steps
which
have
been
taken to avoid further violations,
and the date
when full compliance will
be achieved.
Also, include in your corrective action the root cause
of your
initial incorrect
10 CFR 50.59 interpretation.
The response
directed
by this letter is not subject to the clearance
procedure
of the Office of Management
and
Budget
issued
under
the
Paperwork
Reduction
Act,
PL 96-511.
We appreciate
your cooperation
in this matter.
Sincerely,
Bruce A. Wilson, Assistant Director
for Inspection
Programs
TVA Projects Division
Office of Nuclear
Reactor Regulation
Enclosure:
(See
Page
2)
0
JUL 18
1989
0
Mr. Oliver D. Kingsley, Jr.
Enclosure:
Staff Comments
on Denial of Violation
cc w/encl:
F.
L. Moreadith,
Vice President,
Nuclear Engineering
M. 0. Medford, Vice President
and
Nuclear Technical Director
Chairman,
Limestone
County
Commission
Dr. Henry Myers, Science Advisor
0. J. Zeringue,
Site Director
Browns Ferry Nuclear Plant
Manager,
Nuclear Licensing
and Regulatory Affairs
P. Carier; Site Licensing Manager
G. Campbell,
Plant Manager
TVA Representative,
Rockvi lie Office
General
Counsel,
State of Alabama
bcc w/encl
D.
M. Crutchfield,
B.
D. Liaw,
S.
C. Black,
R.
C. Pierson,
G.
E. Gears,
D. Moran,
W.
S. Little, NRR/RII
A. H. Johnson,
NRR/RII
A.
R.
Long, NRR/RII
J.
Rutberg,
NRC Resident
Inspector
NRC Document Control
Desk
RII/NRR
~'w",CPatterson: vyg
7/(q /89
J
ENCLOSURE
STAFF
COMMENTS
ON DENIAL OF VIOLATION
After
a careful
review of your June
14,
1989
response
to the violation of
Technical Specification 3.5.A.5
and the review of your records,
we disagree
with your conclusion that this violation did not occur.
Based
on the reasons
provided below,
we conclude that
a violation did indeed occur
as stated
in the
Notice of Violation issued
on May 15,
1989.
The licensee's
position is. that
a violation of 'Techni'cal Specification 3.5.A.5
did not occur since after the February 8,
1989 decision to declare
the Unit 2
Core
Spray
System
and
Standby
Coolant
Supply
a
subsequent
engineering
evaluation
was
performed
which concluded that
EECW design-flow
would
be maintained
through
the discharge
paths for the affected
components
following a postulated
seismic
event.
The
licensee
further stated
their
position that
since
the
required
design
flow would
be avai lable to the
affected
components
included the Unit 2 Shutdown
Board
Room Coolers,
then the
design
cooling function for the
C and
D 4KV and Unit 2A and
2B 480V Shutdown
Boards
would
be maintained.
As
a result,
the
power supplies
to the Unit 2
Residual
Heat
Removal
(RHR)
and
Standby
Coolant Supply motor operated
valves
and
pumps,
which are
located
in those
shutdown
board
rooms,
would be
cooled
per
design
requirements
following
a
postulated
seismic
event;
therefore,
the operability of Standby Coolant Supply and Core Spray
as defined
by Technical Specification
3. 5. A.5 would not be affected.
It is
the staff's
position that this
does
not
change
the fact that the
licensee
failed to take
prompt actions
required
by Technical Specification 3.5.A.5
once
licensee
personnel
became
aware
of
the
condition
on
January ll, 1989.
This failure is in consideration
of the existing
design
basis,
i.e.
at that time the three affected
EECW discharge
flow paths
were
required
to be seismically qualified.
The
NRC is very concerned
that the
EECW system
had been reviewed
and declared
prior to
commencing
fuel
loading
on
January
3,
1989 without
identifying this issue
and that
once that information was discovered
by the
licensee
on January ll, 1989,
fuel loading activities were allowed to resume
on January
16,
1989 without plant management
being
made aware of the condition.
0
0