ML17223B414
| ML17223B414 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie, North Anna  |
| Issue date: | 01/08/1992 |
| From: | Blake J, Coley J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17223B412 | List: |
| References | |
| 50-335-91-24, 50-389-91-24, GL-89-08, GL-89-8, NUDOCS 9201280143 | |
| Download: ML17223B414 (21) | |
See also: IR 05000335/1991024
Text
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, N.W.
ATLANTA,GEORGIA 30323
Report Nos.:
50-'335/91-24
and 50-389/91-24
Licensee:
Florida Power and Light Company
9250 West Flagler Street
Miami, FL
33102
Docket Nos.:
50-335
and 50-389
Facil,ity Name:
St. Lucie
1 and
2
License Nos.:
DPR-67 and
Inspection
Conducted:
December 2-6,
1991
Inspector:
r
ate
>gne
Approved by:
a e,
hie
M
er als
and Processes
Section
Engineering
Branch
Division of Reactor Safety
ate
)gne
SUMMARY.
Scope:
This routine,
unannounced
inspection
was
conducted
in the areas
of inservice
inspection
-
data
review
and
evaluation
and
review of nondestructive
examination procedures,
review of radiographic film for safety related welding,
and
review of Florida
Power
and Light ,(FPSL)
long-term erosion/corrosion
program (Generic Letter 89-08).
Results:"
In the .areas
inspected,
one violation
was identified:
50-335/91-24-01,
"Failure to Follow Procedure
for Properly Identifying Radiographic
Film and
Documentation
of Associated
Records",
paragraph
5.
No deviations
were
identified.
Licensee
management
involvement
and the licensees
technical staff
assure
that technical
issues
are resolved for a conservative
standpoint.
The
licensee
appears
to
be very sensitive
to
NRC initiatives
and their
responses
to
these
initiatives
have
good
technical
basis,
inservice
inspection
( ISI) and erosion/corrosion
(E/C) records
were excellent
and indicated that the
nondestructive
examinations
(NDE) have
been conservatively
performed.
9201280143
920113
ADDCK 05000335
8
REPORT DETAILS
Persons
Contacted
Licensee
Employees
- G. Alexander,
ISI Specialist
- G. Boissy, Plant Manager
- F. Carr, Supervisor of Inspections
- K. Crosby, Supervisor, guality Control
(gC)
- B. Dawson,
Maintenance
Manager
- J. Dyer, Supervisor
Maintenance
(gC)
- E. Englmeier, Site guality Manager
- J. Geiger,
Vice President,
Nuclear Assurance
- T. Geiseinger,
Construction
gC Supervisor
- K. Hayhew,
ISI Coordinator
- L. McLaughlin, Plant Licensing,
Manager
- L. Rogers, Electrical Maintenance
Supervisor
- D. Sager,
Plant Vice President
- D. West, Technical
Department
Supervisor
Other
licensee
employees
contacted
during this
inspection
included
engineers,
technicians,
and administrative
personnel.
NRC Resident
Inspector
. *M. Scott
2.
- Attended exit interview
ISI Data Review and Evaluation Unit I (73755)
The inspector
reviewed
the records
described
below to determine
whether
the reported
data covered the scope of the examinations
required during the
current inspection
period of the inspection interval
as described
in the
applicable
ASME Code
and the inservice inspection
program accepted
by the
NRC.
In addition,
the records
were reviewed to ascertain
whether the ISI
data files
were
complete
and
the
data
were within the
previously
established
acceptance
criteria,
and to determine
whether the
license'isposition
of adverse
findings
and
subsequent
re-examinations
were
consistent with regulatory requirements.
St. Lucie Unit I is presently in the first refueling outage,
of the second
period,
of
the
second
ISI interval.
The
second
interval
began
February
11,
1988
and will end
on February
10,
1998.
The applicable
code
for this inspection interval is American Society of Mechanical
Engineers
(ASME) Boiler and Pressure
Vessel
(BLPV) Code,
1983 edition with addenda
through
Summer
1983.
Ebasco
Services
Inc.
provided
the qualified
examination
personnel
to conduct the
NDE services.
4
In order to perform the review of the ISI records
the inspector
had to
review, the following programmatic
documents:
FPEL's ISI current
Outage
Plan
(Document
No. ISI-PSL-100-40-2) for Unit I, the long term (10-year)
Inser vice
Inspection
Plan
(ISI-PSL-100-Rev. 3),
Relief
Request,
the,
licensee
implementation
of
Code
Case
408,
"Alternative
Rules
for
'xamination
of Class
2 Piping", and Combustion Engineering's
(CE) Document
No. CE-NPDS-579
(Combustion Engineering
Owners
Group Task 8626 dated
1990)
"Evaluation of Thermal Stresses
in Piping Connected
to
CE Designed
Reactor
Coolant
Systems
in Response
to
NRC Bulletin 88-08 Supplement
3".
The
inspector
also held discussions
and reviewed data with the ISI specialist
concerning
the implementation
and status of augmented
examinations.
The records
listed
below for .the various
NDE methods
were
reviewed
to
determine
whether
the
records
contained
or provided
reference
to the
following documents.
Examination results
and data
sheets
Examination equipment data
Calibration data sheets
Examination evaluation
data
Records
on extent of examination
Records
on deviation from program
and procedures
including
justification for deviation
Records
and disposition of findings
Re-examination
data after repairwork
Identification of NDE materials
such
a penetrant,
penetrant
cleaner,
couplant, films, tapes,
etc.
In addition, the records
were reviewed technically for the following:
The method,
extent,
and
technique
of examination
comply with the
licensee's
ISI program and applicable
NDE procedure.
The examination
data
are within the acceptance
criteria
as outlined
in the applicable
NDE procedure
and applicable
Code requirements.
The recording,
evaluating,
and dispositioning of findings
are in
compliance
with the applicable
NDE procedure
and applicable
Code
requirements.
Inservice
NDE results
are
compared
w'ith the recorded results of prior
Section
XI examinations.
The method
used for NDE was sufficient to determine
the full extent
of the indication or acceptance.
a.
Visual Examination
Data Reviewed
VT-1 Examination Procedure
NDE 4. 1 Rev.
4
Data Sheet
No.
D
~Ss tern
4.1.004
- 4.1.005
01-005
01-005
Pressurizer
Pressurizer
- Augmented inspection
on the header
- 4.1.008
- Augmented inspection
on
4.1.001
01-021A
-
Loop 1A2SI
elbow between
RC-151-FW-1
and RC-151-1-SW-1
01-22A
Loop 1A2SI
- Augmented inspection
on elbow between
RC-154-FW-1
and RC-154-1-SW-1
4.1.012
01-023
Loop 1BlSI
". Augmented inspection
on fitting between
RC-152-1-SW-1
and
RC-152-1-SW-2.
4.1.021
4.1.027
4.1.023
4.1.024
4.1.025
4.1.026
01-038
01-113-B
01-039-A
01-039-A
01-030-C
01-040-C
Pressurizer
Relief Line
V-1402
Auxi1iary Feedwater
.Combined SI Piping
Loops lA1 and
1A2
Combined
SI Piping
Loops
1A1 and
1A2
Combined
SI Piping
Loops 1Al and
1A2
Combined
SI Piping
Loops 1Al and
1B2
VT-3 Examination Procedure
NDE 4.3 Rev.
3
Date Sheet
No.
4,3,001
4.3.010
Examination Areas
AK-01,02,03,040N-1EA,AND ON-1E-B
Hechanical
and Welded Attachments
Comments
Reactor
Vessel
Internals
Pressurizer
Date Sheet
No.
cont'd)
4.3.015
4.3.018
4.3.027
4.3.035
4.3.036
4.3.039
4.3.054
4.3.056
Examination Areas
Mechanical
and Welded Attachment
Safety Injection Restraint
Mechanical
and Welded Attachments
Pump
1A and
1B Discharge
Support
Base
Pump
1A and
1B Rigid Sway Strut
Assembly
Pump .1A and
1B Discharge
Strut Assembly
Sa fety Injecti on Tank
1B1 Ri gid Sway
Support
Pump
1A to Header
1A Base
Support
Comments
Safety Injection
SI-968-6212
CH"143-11
SI"H-83
SI-H-174A
SI-678-32
SI-972-6242
S I-H-172-V
4.3.057
4.3.060
4.3.064
Main Steam/Spring
Can
LPSI/HPSI/CS
Pumps
Loop A
Spring Hanger
MSH-7A
SI-676-9405
Pump
1A to Header
1A Spring
Can
SI-H-172
4.3.068
4.3.072
HXlA To
HX1A Inlet Rigid
Sway Strut
CS-678-179
CC"20-1A
4.3.073
4.3.077
4.3.091
4.3.099
4.3.106
4.3.108
HX1A Inlet Restraint
HX1A Inlet
CCW Spring Support
CC"20-4
CC-H-114
YPH-181
Circulating Water Intake/Integral
Attachment
ISH-17-1
Circulating Water Inlet/Rod and Clamp
YPH-7
Circulating Water Inlet/Box Restraint
ISH-10
4.3.113
Aux. Feedwater/Rigid
Restraint
BF-1005-307
Date Sheet
No.
Examination Areas
Comments
cont d)
4.3.114
4.3.121
4.3.127
Aux. Feedwater/Sliding
Base Support
BF-1005-557
Circulating Water Inlet/Rod and Clamp
YPH-7
Condensate
Suction to Aux. Feed/
Spring
Base
Assy
4.3.131
4.3.132
CCW Rigid Strut
Safety Injection Tank 1B1/Rigid
Sway Strut
CC-25-7A
S I-972-6243A
4.3.136
CCW - Rigid Sway Strut Assembly
1868-6224
4.3 '45
CCW-Box Restraint
1868"6233
4.3.146
CCW-Rigid Sway Strut Assembly
CC184-6225
Records
selected
for review
above
were
records
primarily with
documented
inspection findings.
The records
included detail
sketches
or
photographs
of
the
discrepancies
and
these
findings'ere
documented
on Customer Notification Reports
(CNR's).
The inspector
reviewed the
CNR's listed below for the above
components
to determine
if the disposition
of the discrepancies
were adequate.
The following
visual examination
NCR's were reviewed:
CNRs Reviewed
91-1-045
91-1-025
91-1-029
91-1-057
91-1-030
91-1-028
YPH-181
YPH-7
BF-1005-307
S I-972-6243A
CC-1848-6225
CNRs Reviewed
91-1-024
91-1-040
91-1-043
91-1-042
91-1-041
91-1-CCH-114
ISH-10
IS H-17-1
91-1-031
CC-25-7A
1868-6224
1868-6233
CNRs Reviewed
91-1-023
91-P-058
91-1-067
91-1-075
91-1-076
91-1-077
91-1-079
91-1-021
91-1-022
b.
Ultrasonic Examination
Data
Review
Examination
Procedure
NDE 5.1 Rev.
6
Data Sheet
No.
Weld ID
~Com anent
Examination
Scans
5.1.001
5.1.001
PR7-L-3
PRZ-C-2
Pressurizer
Pressurizer
0
45
and
60
S
0
45
and
60
S
Examination
Procedure
NDE 5.2.
Rev".
5
Data Sheet
5.2.001
5.2.002
5.3.003
5.2.004
5.2.005
5.2.005
5.2.006
5.2.007,
5.2.008
5.2.008
5.2.008
5.2.009
5.2.010
5.2.011
5.2.012
5.2.013
5.2.014
5.2.014
5.2.014
5.2.015
5.2.015
5.2.016
5.2.017
No.
Weld ID
MS-1- FW-1
MS-1-SW-18
MS-3-1-SW-18
MS-1"SWPl
MS-1-SW-P 1-LS-A
MS-I-FW-LS-A
MS-29-1-SW-1-LS-A
MS-29-1 "SW-1"LS"A
NS"29-FW-6-LR
MS-29-FW-6-SR
MS-29-FW-SLS-A
MS-1-FW-2
BF-14- FW-6
NS-29-FW-6
BF"14-2-SW-1
MS-28-FW"1
MS"28-1-SW-4- LR
MS-28-1-SW-4-SR
MS"28-1"FW-1"LS-A
MS-33" FW-1
NS-33- FW-1-LS-A
MS-29-1-SW-1
BF-14"FW-2
~corn onent
MS Line 1A1
MS Line 1A1
MS Line 181
MS Line 1A1
MS Line lA1
MS Line 1Al
MS Line 181
MS Line 181
MS Line. 181
MS Line 181
MS Line 181
FW to SG-1A1
. MS Line 181
FW to SG-1A1
MS Line 1Al
MS Line 1Al
NS Line 1A1
MS Line 1A1
NS Line 181
Examination
45
and 60'
450 and
60o
S
45~ and
60~
S
45'nd 60'
45'nd
60O
S
45
and
60
S
45~ and
60~
S
45'nd
60
S
45o and
60o
S
45'nd
60o
S
45'nd 60'
45O and
60~
S
45'nd 60'
45
and
60
S
'45
and 60'
45~ and
600
S
45o and
60o
S
45
and
60
S
45'nd
60
S
45'nd 60'
45
and
60
S
450
and
60o
S
45
and 60'
Examination
Procedure
NDE-5.3.
Rev.
4
Data Sheet
No.
We1d ID
~Com onent
Examination
5.3.001
5.3.001
5.3.001
5.3.002
5.3 '02
5.3.002
5.3.002
5.3.003
5.3.003
RC"115-6-503
RC"115-FM-3-500F
RC-115-6-'503
RC"115-6-503-LS-A
RC-115-6-503-LS-8
RC-115-3"503-LS-A
RC"115-3-503-LS" 8
RC-115-FW-1-500K
lA"1-112-8
RC Loop A
RC Loop A
RC Loop A
RC Loop A
RC Loop A
RC Loop A
RC Loop A
RC Loop A
RC Loop A
45~
45~
45~
45~
45
45
450
45~
45
RL
RL
RL
and
60~
S
and 60'
and 60'
and
60~
S
and
60
S
and 60'
Examination
Procedure
NDE 5.4 Rev.
8
Data Sheet
No.
Weld ID
~Com onent
Exami nati on
5.4.001
5.4.001
5.4.001
S I-113-FW-7
SI-113-6-SW-3
SI"113-6-Sh'"2
Loop 1A2-SI
Loop 1A2-SI
Loop 1A2-SI
45
45
450
and
60
and
60~
and
600
RL
RL
RL
Data Sheet
No.
cont d)
Weld ID
~Com onent
Examination
5.4.001
5.4.002
5.4.003
5.4.003
5.4.003
5.4.004
5.4.004
5.4.004
5.4.005
5.4.005
5.4.006
5.4;006
5.4.006
5.4.007
'5.4.008
5.4.008
5.4.'016
5.4.031
SI-113-6-SW-1
SI-113-FW"8
SI-113-12-SW-2
S I-113-12-SW-3
SI-113-12-FW-12
SI-113"11-SW"1
S I-113-FW-1 lA
SI"113"FW-11
SI-113-FW-13
S I-113- FW-1
S I-113-9-SM" 1
SI-113-FM-10
SI-113-8-SM-1
SI-149-2-SW-1
S I-151- FW-2
Fitting ¹4
Fitting ¹3
SI"151" FW-1
Loop'1A2-SI
Loop lA2-SI
Loop lA2-SI.
Loop 1A2-SI
Loop 1A2-SI
Loop 1A2-SI
Loop 1A2-SI
Loop 1A2-SI
Loop 1A2"SI
Loop lA2-SI
Lo'op 1A2-SI
Loop 1A2-SI
Loop 1A2-SI
Loop 1A2-SI
Loop 1B2-SI
Loop 1B2"SI
Loo'p 1B2-SI
Loop 1B2-SI
45~ and
45'nd
45~ and
45~ and
45
and
'5~ and
45~ and
45
and
45~ and
45
and
45'nd
45
and
45~ and
45'nd
450 and
45~ and
450
and
45
. and
45
and
60~
RL
60~
RL
60~
RL
60~
RL
60~
RL
60~
RL
60~
RL
60O
RL
60~
RL
60~
RL
60~
RL
600
RL
60~
RL'0~
RL
600
RL
600
RL
600
RL
60~
RL
60
S
The inspectors'eviewed
of FP5L's
NDE Procedure
5.4 Rev.
8 and the
above
examination
records
revealed" that this licensee
uses
450
and
60~ refracted
longitudinal
wave transducers
on all stainless
steel
piping welds.
This inspection
technique
is the
best
method
for
ensuring
100% coverage
and defect detection
in austentic
stainless
steel.
Licensee's
normally
do
not
perform
100%
refracted
longitudinal
wave
examination
stainless
steel
using
45
and
60
transducers
because
refracted
longitudinal
wave
transducers
are
difficult to
use
and require highly trained
examiners
to
use
them
correctly.
FPEL's commitment to safety
and excellence
over cost is
typified by enhanced
examination
techniques
such
as
this'iquid
Penetrant
Examination
Data Review
Examination
Procedure
NDE 3.3.
Rev.
3
Data Sheet
No
3.3.001
3..3.001
3.3.001
3.3.008
3.3.010
3.'3.014
3.3.014
3.3.034
3.3.034
=
3.3.034
Weld ID
S I-131-SW" 1
S I-131-SM-2
SI-215-SW-2
S I-213-FW-1
S I-213- FW"2
SI-151-FW-1
S I-131-SW-6
RC-154- FW-1
S I-149- FW-4
SI-149-3-SW-1
Data Sheet
No.
(cont'd)
3.3.034
3.3.043
3.3.050
3.3 '53
3.3.055
Weld ID
S I-149-3-SW"2
SI"151-1"SW-9
S I-208-1-SW-2
SI-475-FW-7B
S I-406- FW-1
d.,
Magnetic Particle Examination
Data Review
Examination
Procedure
NDE 2.2 Rev.
3
Data Sheet
No.
2.2.004
2.2.006
2.2.012
2.2.013
Weld ID
MS-28-5-SW-1
8 F"14"1-SW-2
BF-14-2-SW-1
~Com onent
Reactor Coolant Piping
Loop lAl
Main Feedwater
To
To
1A1
The data
reviewed for each of the
above
NDE methods
revealed
that
FPSL
has
a very technical
competent
and
conservative
ISI program.
Documentation
provided for the
above examinations
was excellent.
Certification records for the
examiners
listed below,
who
had
been
utilized for the above
examinations,
were
reviewed
by the inspector
and found to be satisfactory:
Ebasco
Services
Inc. Examiners Certifications
Name,
R.
B
M. B.
B..B.
S.
C.
P.
K.
C.
L.
R.
L.
D.
M.
P.
N.
C.
P.
R.V.'I
III
- IIII
IjjII
III
IIIII
II
NA
I
NA
II
II
Ij
II
'II
II
II
II
II
II
II
II
II
II
III
III
II
II
NA
NA
NAII VT"1
IIIIII VT-1
IIII
9/10/91
9/16/91
1/30/91
2/5/91
3/20/91
10/22/91
1/11/91
10/31/91
9/22/91
9/17/91
9/16/91
F.
C.
W.
M.
D.
N.
C.
R.
FP5L Examiner
Cer tificati on s
III
II
III
NA
III
III
NA
-
NA
III
II
NA
III
II
II
II
II
6/12/91
2/01/91
3/27/91
3/27/91
Within
the
areas
inspected,
no
violations
or deviations
were
identified.
3.
Review of ISI Procedures
Unit
1 (73755)
The inspector
reviewed
the recently
revised
procedures
listed below to
ascertain
whether
the procedures
adequately
implemented
the requirements
of the
1983
ASME Code with addenda
through
Summer
1983 which is required
for 2nd Interval
ISI examinations
on Unit 1.
The following procedures
were also
reviewed to ensure
that they adequately
covered all required
aspects
of the 'pproved
ISI program,
including licensee
commitments
to
perform certain
augmented
inspections,
proper approvals,
adequate
record
'retention,
qualification of NDE examination
personnel,
technical
content,
and methods of recording,
evaluating
and 'dispositioning findings:
Procedure
No.
and Revision
Title of Procedure
NDE-2.2, Rev.
3
NDE-3.3 Rev.
3
Magnetic Particle Examination
Examination
Using the
Solvent
Removal Vi.sible Dye Technique
NDE-5.4 Rev.
8
NDE-5.2 Rev.
5
NDE-5. 1 Rev.
6
NDE-4.3 Rev.
3
NDE-4. 1 Rev.
4
NDE-5.3 Rev.
4
NDE-5. 16 Rev.
3
NDE-5.11 Rev.
4
NDE-5.12 Rev.
3
Ultrasonic
Examination
of Austeni.tic
Piping Welds
Ultrasonic
Examination
of
Ferritic
Piping Welds
Ultrasonic
Examination
of
Pressure
Vessel. Welds,
Except Reactor
Vessels
Visual
Examination
VT-3/VT-'4
Visual Examination VT-1: Welds/Bolting/
Bushing/Washers
Ultra soni c
Exami nati on
of
Primary
Coolant Piping Welds
Ultrasonic
Examination
Technique
for
the Evaluation of Cracking in Feedwater
Piping
Ultrasonic
Examination
of Dissimilar
Metal Piping Welds
Manual
Ultrasonic
Examination
of
Reactor
Vessel
Flange to Shell
and Stud
Hole
Threads
(Reg.
Guide
1. 150
implemented)
10
Procedure
No.
and Revision
(cont d
Title of Procedure
NDE-5.13 Rev.
4
Ultrasonic
Examination of Nozzle Inner
Radius Areas
NDE-5. 18 Rev.'
-
. Ultrasonic Thickness
Measurements
Within the areas
examined,
no violation or deviation
was identified.
Review
and Evaluation of FP8 L's Long Term Erosion/Corrosion
(E/C) Program
For Unit-1 (NRC Generic Letter 89-08) (92701)
Background
On
May 2,
1989,
NRC
issued
which requested
that
licensees
provided
assurances
that
a
long
term
erosion/corrosion
monitoring program, consisting
of systematic
measures
to ensure
erosion/
corrosion
does
not lead to degradation
of single
phase
and two phase
high
energy carbon steel
systems.
FP&L has
had
a long established
two-phase wall thinning inspection
program
and single
phase
inspections
began
immediately at their Turkey Point Plant
following the
1986 Surry
2 event.
NRC staff reviewed
the
E/C program at
Turkey Point in August 1988 in support of NUREG-1344 and determined that
FPKL met
NUMARC guidelines for inspection
for E/C in'ingle-phase
lines.
However, the staff found that the licensee
had not implemented
formalized
procedures
or administrative
controls
to
ensure
continued
long-term
implementation
of its erosion/corrosion
monitoring program for piping and
components
within the
li'censing
basis.
FPKL's letter of response
to
dated July 21,
1989,
informed
NRC that
a corporate
procedure
was developed
to define .the responsibilities
within
FPE L for the
continuation
of
the
E/C
programs
at
Turkey Point Units 3
and
4
and
St.
Lucie Units
1 and 2.
In addition, the licensee
stated that due to the
continuing effort necessary
to ensure
the integrity of high energy,.piping
systems,
and experience
gained
from previous
inspection
program,
FPRL's
engineering
staff would
be upgrading its engineering
standard
for this
process.
The inspector
reviewed the
programmatic
and inspection
procedures
listed
below
to
ensure
that
the
licensee
had
formalized
procedures
and
administrative
controls
to
ensure
continue'd
implementation
of its
E/C
monitoring program for St.
Lucie Unit 1.
JPN-PSL-SEMP-91-031
Rev.
2,
High
Energy
Piping
Inspection
Program
Guidelines for 1991 Refueling Outage
REA-SLN-86-072-1B Rev.
2
E/C-PSL-1-001
Rev.
9 Field
Change
1,
St.
Lucie Unit 1,
Fall
1991
Refueling Outage Erosion/Corrosion
Examination
Plan
NDE 5. 18 Rev.
3 Ultrasonic Thickness
Measurements
11
The inspector's
review re'vealed that
FP&L uses
the Electric Power Research
Institutes
(EPRI)
CHEC and
CHECMATE computer programs,
industry data,
and
previous
inspection
data
as
predictive'ools
for
determining
and
prioritizing inspection locations.
FP8L Nuclear Engineering
has
inputted
St.
Lucie Unit
1 operational
and as-built piping data
into the
CHEC and
CHECMATE computer
programs.
The
CHEC
and
CHECMATE computer,
programs
predict piping
and
components
susceptible
to
E/C based
on the inputted
data for. identification
and inspection
during future refueling outages.
In estimating
E/C wear rates
the
CHECMATE program utilizes the following
parameters:
material composition,
PH and water chemistry,
temperature
and
pressure,
flow path
geometry,
flow velocity and moisture content
(two-phase
flow
only).
When
ultrasonic
examina'tions
. reveals:
component/piping
wall thickness
to
be below the established
min'imum wall
thickness
or predicted to violate that
minimum during the
next operating
cycle the components/piping
are replaced,
inspections
are also expanded to
properly bound the
E/C problem
and correct its cause.
The areas
chosen for cycle
11 E/C inspection
were .as follows:
Turbine Crossunder
piping
Moisture separator
reheater
(MSR) shell
side drain piping and fitting
between
the
MSRs and the four
LP heaters
Mainsteam inlet to. MSR "D" tubeside
MSR "A" tubeside
discharge
to drain collector tank "B"
HP Heater
5A extraction
steam piping
N
pump "A and B" to heater drain
pump "B" inlets
High pressure
heater
drain
pump discharge orifices, tees
and
LCV's
LP Heater
3 to
LP heater
2 heater drain
LCV area
Condensate
and feedwater
system orifices and tees
Steam/Generator
blowdown and feedwater piping inside containment
LP Heater
3B heater vent at condenser
One
hundred
and
sixteen
inspection
data
sheets
resulted
for .he
above
inspections
and the expanded
inspections.
The inspector
selected
the data
reports list
below for review
and
to
determine if the
licensee's
corrective actions
appeared
satisfactory:
Data Sheet
Com onent/System'tem
ID
PS L-1-EC-91-002
PS L-1-EC-91-003
Heater Drain
Heater Drain
10HD118-1- E-3-10
12
Data Sheet
cont d
Com onent/S
stem
Item ID
PS L"1"EC-91-005
PS L-1-EC-91 "010
PS L-1-EC-91-011
PS L"1"EC"91-015
PS L-1-EC-91-017
PS L-1"EC"91"021
PS L-1-EC-91-023
PS L-1-EC-91-032
PS L-1-EC-91-039
PS L-1-EC-91-042
PS L-1-EC-91-043
PS L-1-EC-91-055
PS L-1-EC-91-069
PS L"1-EC-91" 072
PSL-1-EC-91-073
PS L-1-EC-91 "079
PS L-1-EC-91-080
PS L-1-EC-91-083
Heater"'Drain
Heater Drain
14HD39-4-P-9-19
Heater Drain
14HD40-4-P-3-19
Heater Drain
14HD84"5"P"24-54
Heater Drain
Heater Drain
6HD-11-E"15-38
Heater Drain
20HD43-2-R-2-31
8MS24-3-E-6-16
Heater Drain
'MS24-3-P-,6-12
Condensate
24C50-2-P-9-20
Condensate
24C38"3"T'-1-11
Heater
Drain
Heater
Drain
14HD84-5-P-23-52A
Heater Drain
BlowDown
I-2B1-0-P-14-30
BlowDown
I-2B1-0-E-1-3
8MS26-5-E-14-42
The records for the above examinations
were excellent, detail
drawings
and
photographs
documented
the
equipment
involved
and the
areas
of concern.
Corrective action
appeared
to
be satisfactory.
The information reviewed
revealed
an aggressive
and conservative
E/C program is. presently in place
for Unit
1 and should
improve as
more data
becomes available.
In addition to the
above
internal
surface
piping/component
E/C program.
The inspe'ctor
reviewed visual
examination
data for a licensee
augmented
inspection
program initiated this inspection period for ASME Class
2 and
3
components,
piping,
and supports
located in the intake structure,
yard and
pipe
tunnel
which
are
subject
to external
corrosion
damage
caused
by
adverse
environment
conditions.
The inspector's
review of NDE procedures
identified in paragraph
3 above,
also
revealed
that these
procedures
had
requirements
for examiners
to report boric acid corrosion
on components
in
areas
where they perform their
NDE examinations.
The inspector
noted that
data
for these
inspections
was excellent.
These
boric acid inspections
are
above
and
beyond
the established
program for boric acid corrosion
required
Within the areas
examined,
no violation or deviation were identified.
5.
Review of Radiographic
Film Unit
1 (57090)
The inspector
reviewed radiographic film and thei r associated
records for
the
ASME Class
2 Plant modification welds listed below.
This review was
performed
to
determine
whether
the
radiographic
film and
associated
records
had
been
prepared,
evaluated,
and maintained
in accordance
with
the licensee's
approved
radiographic
procedures
Nos. TS-9.2
and TS-9.3. 1.
~ ~
8
v
13
Inspection
Re ort No.
N90-,1673
N90-1675
M90-1676
N90-1682
N90-1683
YI90-1684
M90-1685
Yi90-1686
,Mel d
ID No.
001K
001K
001N
014A
013A
005A
004A
013A
Support
Line No.
CH Line 0544
Comments
{1) Film
ID missing
and/or
not
legible on'film segments
(2)
Radiographer
dated
his
examination
as
September
4,
1990.
The film was
read
on
March 22,
1990 and subsequent
shots
taken
on
March 23,
1990.
Therefore,
the
Radiographer's
date is meaningless
for this record.
V
Film ID not legible and/or
incomplete
SAT
SF'T
Missing two filrIifrom package
received
from vault (film was
later found but not in vault)
Yi90-1688
N90-1690
N90-1691
M90-1692
M90-1693
N90-2673
N90-2259
N90-2743
M90-22621
014A
31A
30A
13A
012A
009R3
96
97
98
2F-1-HVS-0010
SAT
Radiographer
did not sign or date
Radiographic
Inspection
Report
{RIR) for 'radiographs
taken
on
March 24,
1991
SAT
14
Inspection
Support
~RN
.
tD II
.
Li
(cont'd)
Comments
M90-2262
M90-2263
M90-2264
99
100
101
P
Film ID on Film Interval 6-0
Has Weld No.
and Date Only.
M90-2265
102,
- SAT
103
RIR Missing Inspection
Report No.,
No. of Exposures,
and
No. of Film
The inspector's
review was only a sample of the available film for Unit 1,
and quality assurance
(gA) discrepancies
were apparent
as indicated
above.
The licensee
corrected
the above discrepancies
and committed to perform
a
review to
be
completed
by January
15,
1992 of all radiographs
and their
documentation
for the
past
two years.
However,
FPKL's
Radiographic
Procedure
¹TS 9.3 paragraph
14.F requires that,
permanent,
non
permanent
and
INFO film, shall
have
the
following identification
permanently
included
on
each film by
use of lead characters
during exposure
or
by
visible light imprinted.
- FPL-PSL No.
Unit number
- PC/M or
CWO No.
~System or Component Identification and Drawing No.,
and
Rev.
No.
Weld No. or part
number (as applicable)
"Weld Repair Report
No.
( If applicable)
"Date
In
addition,
paragraph
17.B. 1
of
radiographic
procedure
No.
requires
that,
the
radiographic
inspection
report
shall
include
as
a
minimum all of the information indicated.
This item was reported to the
licensee
as violation 50-335/91-24-01,
Failure
to
Follow Procedure
for
Properly
Identifying Radiographic
Film
and
Documentation
of Associated
Records.
The inspector's
technical
review of the
above
radiographs
to
insure discrepancies
are'roperly
dispositioned
was satisfactory.
Exit Interview
The inspection
scope
and results
were
summarized
on December
6,
1991, with
those
persons
indicated in paragraph
1.
The inspector described
the areas
0
15
inspected
and
discussed
in detail
the inspection
results
listed
below.'roprietary-
information is
not contained
in this report.
Dissenting
comments
were not received
from the licensee.
(Open)
SL-4 violation 50-335/91-24-Ol,
"Failure to Follow Procedure for
Properly Identifying Radiographic
Film and
Documentation
of Associated
Records"
paragraph
5.
Aux
BSPV
CNR
Dtd
E/C
FPSL
ID
MS
No.
NRC
PSL
REV
. SL
TS
and Initialisms
American Society of Mechanical
Auxiliary
Boiler and Pressure
Vessel
Component Cooling (later
Combustion
Engineering
Charging
Customer Notification Report,
Dated
Erosion/Corrosion
Florida Power and Light
Identification
Inservice Inspection
Low Pressure
Moisture Separator
Reheater
Magnetic Test
Nondestructive
Examination
Number
Nuclear Regulatory
Commission
Plant Saint Lucie
Test
Quality Assurance
Quality Control
Revision
Radiographic
Inspection
Report
Safety Injection
Severity Level
Technique
Sheet
Ultrasonic Test