ML17229A275
| ML17229A275 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 03/25/1997 |
| From: | Gallo R NRC (Affiliation Not Assigned) |
| To: | Plunkett T FLORIDA POWER & LIGHT CO. |
| Shared Package | |
| ML17229A276 | List: |
| References | |
| FACA, NUDOCS 9703280231 | |
| Download: ML17229A275 (7) | |
See also: IR 05000335/1996201
Text
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UNITED'STATES
NUCLEAR REGULATORY
COMMISSION'ASHINGTON,
D.C. 20555-0001
Ihrch 25,
1997
Mr. T.
F. Plunkett
President
Nuclear Division
Florida Power
and Light Company
Juno
Beach,
FL
33408-0420
SUBJECT:
ST.
LUCIE NUCLEAR PLANTS UNITS
1
AND 2'DESIGN
INSPECTION
(NRC
~ -
INSPECTION
REPORT
NOS; 50-335/96-201
AND 50-389/96-201)
Dear Mr. Plunkett:
a
I
During the period from November
18,
1996 through January
10,
1997 the U.S.
Nuclear Regulatory Commission's'NRCs)
Office of Nuclear Reactor Regulation
(NRR) performed
a design
inspection of the St. Lucie Unit
1 Au'xiliary
System
(AFW) and the Unit 2 Component
Cooling Water
(CCW) System.
The purpose of the inspection
was to evaluate
the capability of the systems
to
perform safety functions required
by their design. basis,
adherence
to the
design
and licensing basis,
and consistency of the as-built configuration with
the Updated Final Saftey Analysis Report.
The results of this. inspection
are contained
in the attached
inspection
report.
Overall, the team found the design of the two selected
systems
to be
good, with adequate
design margins.
Your staff's understanding
of the design.
basis
was good,
as
was their inspection preparation
and ability to resolve
team identified concerns.
The implementation of the design
was found to be
adequate
with some concerns
noted.
While none of the team's
findings resulted
in system inoperability,
some
error's
made during the original plant design
have reduced
system operating
margins.
Of specific concern
are the calculations
which support operation of .
the component cooling water system.
The current calculations for determining
. 'the temperature limit for the seawater
intake to the component cooling water
heat
exchangers
are non-conservative.
Your interim actions to establish
a
82 'F temperature limit on intake'cooling water are adequate
for the short
term, but plant operation
could
be chal,lengel
by higher intake cooling water
temperatures
that'occur during the warmer'onths
of the year.
A few of the team's
findings were attributed to weaknesses
in testing or
surveillance activities, including an issue identi,fied by your staff JUst
prior to the inspection
concerning
a lack of operating
procedures
and testing
of certain safety related
DC circuit br'eakers.
A review of troubleshooting
activities related to the above circuit breakers
revealed that written'.
documentation
was inadequate
to ensure
an appropriate
level of plant
an'd
personnel
safety.
The team noted that your staff has
implemented corrective action for many of
the specific findings identified in the report.
Please
provide
a schedule,
within 60 days of the date of this letter, for completion of your corrective
actions for the items listed in Attachment
1 to the enclosed
report,
so
that'e
can plan for re-inspection of these
items.
'yI703280231
970325
ADQCK 05000335
8
Hr. T. F. Plunkett
As with all
NRC inspections,
we expect that you will evaluate
the r'esults of
this inspection,
and where applicable,
apply the specific findings to other
systems
and components.
In accordance
with 10 CFR 2.790 of the Commission's
regulations,
a copy of
this letter and inspection report will be placed in the
NRC Public Document
Room.
Any enforcement
action resulting form this inspection will be issued
by
the
NRC Region II office via a. separat'e
correspondence.
Should you have
any
'uestions
concerning
the attached
inspection report,
please
contact the
inspection
team leader Hr..Jeffrey B. Jacobson
at (301) 415-2977.
Sincerely,
Enclosure:
Inspection
and 50-389/96-201
cc:
See next page
Robert
H. Gallo, Chief
Special
Inspection
Branch
Division of .Inspection.and
Support.
Programs.
Office of Nuclear Reactor Regulation
Report
No. 50-335/96-201
0
Mr. T. F. Plunkett
Florida Power
and Light Company
ST.
LUCIE PLANT
CC:
Senior Resident
Inspector
St.
Lucie Plant
U.S. Nuc'lear Regulat
~ Commission
7585 S.
Hwy A1A
Jensen
Beach,
34957
Joe Myers, Director
Division of Emergency
Preparedness
Department of Community Affairs
2740 Centerview Drive
Tallahassee,
Florida 32399-2100
M. S.
Ross,
Attorney
Florida Power
5 Light
11770
US Highway
1
North .Palm Beach,
FL
33408
John T. Butler, Esqu're
Steel,
Hector
and Davis
4000 Southeast
Financial
Center'iami,
3313.1-2398
Mr. Thomas
R.L. Kindred
County Administrator
St.
Lucie County
2300 Virginia Avenue
Fort Pierce,
Florida 34982
Mr. Bill Passetti
Office of Radiation Control
Department of Health
and
'Rehabilitati've Services
1317 Winewood Blvd.
Tallahassee,
32399-0700
Regional Administrator
Region II
U.S. Nuclear Regulatory
Commission
101 Marietta Street,
NW. Suite
2900
Atlanta, Georgia
30323
H.
N. Paduano,
Manager
Licensi'ng
8 Special
Programs
Florida Power
and Light Company
P.O.
Box 14000
Juno
Beach,
Florida 33408-0420
J.
A. Stall, Site Vice President
St. Lucie Nuclear Plant
6351, South
Ocean Drive
Jensen
Beach,
34957
Mr. J. Scarola
'Plant General
Manager
St.
Lucie Nuclear Plant
6351 South
Ocean Drive
Jensen
Beach,
34957
Mr. Caudle Julian
U.S. Nuclear Regulatory
Commission
101 Marietta Street',
N.W. Suite
29'00.
Atlanta, Georgia 30323-0199
E. J.
Weinkam
Licensing Manager
St. Lucie Nuclear Plant
6351 South
Ocean Drive
Jensen'each,
34957
Distribution:
Docket Files 50-335
and 50-389
PSIB R/F
ACThadani,
FPGillespie,
RMGallo,
DPNorkin,
CERossi,
SAVarga,
FJHebdon,
LAWiens,'NRR
ETDunnington,
HChristensen,
RII
MGMiller, RII
KClark, RII
Regional Administrators
Regional Division Directors
Inspection
Team
PUBLIC
ACRS (3)
OGC (3)
IS Distribution
0