ML18152A542
| ML18152A542 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/10/1995 |
| From: | Blake J, Kleinsorge W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152A543 | List: |
| References | |
| 50-280-95-04, 50-280-95-4, 50-281-95-04, 50-281-95-4, NUDOCS 9503200221 | |
| Download: ML18152A542 (16) | |
See also: IR 05000280/1995004
Text
Report Nos. :
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, N.W., SUITE 2900
ATLANTA, GEORGIA 30323-0199
50-280/95-04 and 50-281/95-04
Licensee:
Virginia Electric and Power Company
Glen Allen, VA
23060
Docket Nos.:
50-280 and 50-281
License Nos.:
Facility Name:
Surry Power Station Units 1 and 2
y 13-17, and 21-24, 1995
- .,,,,, 1, ,~
Date Signed
Safety
SUMMARY
Scope:
This routine, unannounced inspection was conducted in the areas of Inservice
Inspection (ISI), Flow Accelerated Corrosion (FAC), and feedwater heater
replacement.
Results:
ISI procedures were well written and appropriate for their intended
application.
ISI examinations were performed satisfactorily.
ISI records
support the conclusion that examinations were conducted in accordance with
applicable procedures and regulatory commitments.
The licensee has
established and continues to implement an effective program to maintain high
energy carbon steel piping systems within acceptable wall thickness limits.
The Design control package for the Feedwater heater replacement was appropri-
ate to the circumstances.
Welding associated with the Feedwater heater
replacement was accomplished by properly qualified and certified welders in
accordance with properly qualified welding procedures using appropriately
certified welding filler material.
In the areas inspected, no violations or deviations were identified.
9503200221 6~866~80
~DR
ADOCK
Enclosure
1.
2.
Persons Contacted
Licensee Employees
REPORT DETAILS
- J. Grace, Management Safety Review Committee
- D. Grady, Inservice Inspection (ISI)/Nondestructive Testing &
Engineering Programs
- T. Huber, ISI Engineer
- M. Kacmarcik, Licensing Engineer
- J. McCarthy, Assistant Station Manager
- J. Price, Assistant Station Manager
- C. Robinson Jr., Manager Inservice Inspection/Nondestructive Testing
- E. Smith, Quality Assurance (QA) Manager
Other licensee employees contacted during this inspection included
craftsmen, engineers, mechanics, security force members, technicians, and
administrative personnel.
NRC Resident Inspectors
- M. Branch, Senior Resident Inspector
L. Garner, Project Engineer
D. Karn, Resident Inspector
S. Tingen, Resident Inspector
- Attended exit interview
Acronyms and initial isms used throughout this report are listed in the
last paragraph.
Inservice Inspection (ISI) (73051)
The inspector reviewed documents and records, and observed activities, as
indicated below, to determine whether ISI was being conducted in accor-
dance with applicable procedures, regulatory requirements, and licensee
commitments.
The applicable code for ISI, for Unit 1 is the ASME B&PV
Code,Section XI, 1989 Edition with no Addenda (89NA).
The applicable
code for ISI, for Unit 2 is the ASME B&PV Code,Section XI, 1980 Edition
with Winter 1980 Addenda (80W80) for the second ISI interval and the ASME
B&PV Code,Section XI, 89NA for the third ISI interval.
Unit 1 is
operating in fuel cycle 13, and the first, 40-month period; of the third,
ten-year interval (Pl,13) ending October 14, 2003.
Unit 2 is in
refueling outage (RFD) 12; the second outage of the third 40-month period
of the second ten-year interval ending June 19, 1995, (02,P3,I2) and
first outage of the first, 40-month period, of the third, ten-year
interval (Ol,Pl,I3) starting June 10 1994 and ending June 10, 2004.
The
licensee extended the second ten-year ISI interval for both Units 1 and 2
by 296 and 374 days respectively.
The licensee notified the NRC of these
changes in VEPCO letters91-551 dated October 1, 1991, and 91-338 dated
July 11, 1991.
The dates of the third ten-year ISI intervals, for both
2
units, remain the same as originally scheduled.
The preceding explains
the dual interval status for Unit 2 during this outage.
Unit 1 was
granted a construction permit June 25, 1968, received its Operating
License May 25, 1972, and commenced commercial operations on December 22,
1972.
Unit 2 was granted a construction permit June 25, 1968, received
its Operating License on January 29, 1973, and commenced commercial
operations on May 1, 1973.
The licensee's nondestructive examination (NOE) personnel, augmented by
contract personnel from Virginia Corporation of Richmond (VCR) were
performing liquid penetrant (PT), magnetic particle (MT), and ultrasonic
(UT) examinations under the umbrella of the VEPCO Quality Assurance (QA)
Program.
Steam Generator (S/G) tubing eddy current (ET) examination data
acquisition and analysis and automated UT examination of the reactor
vessel, were being accomplished by the Westinghouse Company (~) under the
umbrella of the~ QA Program.
. a.
ISI Program Review, Units 1 and 2 (73051)
The inspector reviewed the following documents relating to the ISI
program to determine whether the plan had been approved by the
licensee and to assure that procedures and plans had been estab-
lished for the applicable activities.
Procedures were also reviewed
for technical content .
ID
11/17/94
11/17 /94
7/20/94
9/12/94
11/4/94
2/22/95
VPAP-0406
11/29/94
Procedures Reviewed
Rev.
Title
8
ISI Examination Plan Surry Power Station
Unit 2, Interval 2 Period 3 Items Remaining
to be Examined Sorted by Mark Number
4
ISI Examination Plan. Surry Power Station
Unit 2, Interval 3 Summary of Changes to
Plan Effective With Revision 4 To Plan
1
Surry Power Station Unit 2 Inservice
Inspection Program Interval 3
4
3
2
May 10, 1994 - May 9, 2004
Contractor:
Proficiency Training and
Examination
Surry Units 1 and 2 Inservice Testing
Program Plan Basis Document
10 Year Reactor Vessel Inservice Examination
Program Interval 2 Period 3 and Interval 3
Period 1
Consumable Material Evaluation
3
Procedures Reviewed
ID
Rev.
Title
VPAP-0701
5
Receiving and Receipt Inspection Services
1/23/95
2-NPT-RC-001
1
Inservice Inspection of Steam Generator
3/3/94
Tubes
2/2/95
Westinghouse Steam Generator Tube Eddy
Current Examination Plan
Procedures were well written and appropriate for their intended
application.
b.
Review of NOE Procedures, Units 1 and 2 (73052)
The inspector reviewed the procedures listed below to determine
whether these procedures were consistent with regulatory require-
ments and licensee commitments.
The procedures were also reviewed
for technical content.
ID
2-VIR-ISI-254
2/2/95
2-VIR-ISI-54
2/2/95
2-VIR-ISI-55
2/2/95
MRS-242 VEPl
3/5/92
NDE-6.3
10/29/93
NDE-6.4
9/22/93
NDE-6.6
10/4/93
NDE-7.2
10/4/93
Procedures Examined
Rev
Title/Subject
0
Remote Inservice Inspection for Reactor
Vessel for Surry Nuclear Power Plant
0
Manual Ultrasonic Examination for Reactor
Vessel Upper Shell to Flange Weld for
Surry Nuclear Power Plant
O
Manual Ultrasonic Examination for Reactor
Vessel Threads in Flange for Surry
Nuclear Power Plant
5
2
Eddy Current inspection of Preservice and
Inservice Heat Exchanger Tubes
Storage and Control of NDE Calibrated
Equipment, Calibration Standards &
Consumable Materials
2
Selection of Calibration Blocks for PSI
and ISI Ultrasonic Examination
O
General Requirements for Nondestructive
Examination (Third Interval)
6
General Requirements for Nondestructive
Examination (Second Interval)
4
Procedures Examined
ID
Rev
Title/Subject
NDE-MT-201
2
Magnetic Particle Examination
10/4/93
(Second Interval)
NDE-MT-202
2
Magnetic Particle Examination of Bolting
10/4/93
(Second Interval)
NDE-MT-601
0
Magnetic Particle Examination
10/4/93
(Third Interval)
NDE-MT-602
0
Magnetic Particle Examination of Bolting
10/4/93
(Third Interval)
NDE-PT-201
2
Liquid Penetrant Examination (Second
2/28/92
Interval)
NDE-PT-202
1
Liquid Penetrant Examination of Bolting
2/28/92
(Second Interval)
NDE-PT-203
0
Liquid Penetrant Examination for
2/28/92
Temperatures Less Than 60°F (Second
Interval)
NDE-PT-601
0
Liquid Penetrant Examination (Third
10/4/93
Interval)
NDE-PT-602
0
Liquid Penetrant Examination of Bolting
10/4/93
(Third Interval)
NDE-PT-603
0
Liquid Penetrant Examination for
10/4/93
Temperatures Less Than 60°F (Third
Interval)
NDE-UT-201
3
Manual Ultrasonic Examination of Piping
2/28/92
Welds (Second Interval)
NDE-UT-202
3
Ultrasonic Examination of Vessel Welds 2"
2/28/92
and Less in Thickness (Second Interval)
NDE-UT-203
3
Ultrasonic Examination of Vessel Welds
2/28/92
Greater Than 2" in Thickness (Second
Interval)
NDE-UT-204
2
Inservice Ultrasonic Examination of Class
2/28/92
1 Bolting (Second Interval)
NDE-UT-205
4
Ultrasonic Examination of Reactor Coolant
12/20/93
Piping Welds {Second Interval)
NDE-UT-207
0
Straight Beam Longitudinal Wave
4/3/91
Ultrasonic Examination of Loop Stop Valve
Piping (Second Interval)
NDE-UT-601
0
Manual Ultrasonic Examination of Piping
10/4/93
Welds {Third Interval)
5
Procedures Examined
ID
Rev
Title/Subject
NDE-UT-603
10/4/94
NDE-UT-604
5/4/94
NDE-UT-605
10/4/93
NDE-UT-606
10/4/93
SGPMS 002
1/3/94
O
Ultrasonic Examination of Vessel Welds
Greater Than 2" in Thickness (Third
Interval)
O
Ultrasonic Examination of Bolting > 2" in
Diameter (Third Interval)
0
Ultrasonic Examination of Reactor Coolant
Piping Welds (Third Interval)
0
Manual Ultrasonic Sizing of Flaw
Indications (Third Interval)
3 * Plant Specific Guidelines Eddy Current
Data Analysis, Training, and Testing
Procedures were well written and appropriate for their intended
application.
c.
Observation of Work and Work Activities, Unit 3 (73753)
The inspector observed work activities, reviewed certification
records of NOE equipment and materials, and reviewed NOE personnel
qualifications for* personnel who had been utilized in the ISI
examinations during this outage.
The observations and reviews
conducted by the inspector are documented belo"w.
Activities Observed
Liquid Penetrant Examination (PT)
The inspector observed PT examinations of the welds listed below.
The observations were compared with the applicable procedures and
the Code.
The inspector performed an independent evaluation of the
indications obtained, to confirm the NOE examiner's evaluation.
Liquid Penetrant Examinations Observed
Weld No.
Drawing No
System
1-09
1154B-WMKS-022Al
Safety Injection
1-10
1154B-WMKS-022Al
Safety Injection
1-11
Safety Injection
1-12
1154B-WMKS-022Al
Safety Injection
l-09t
1148-WMKS-RC-10-l
6
Liquid Penetrant Examinations Observed
Weld No.
Drawing No
System
1-lOt
1148-WMKS-RC-10-l
1-18.t
1148-WMKS-RC-10-l
l-19t
1148-WMKS-RC-10-l
l-20t
1148-WMKS-RC-10-l
l-2lt
1148-WMKS-RC-10-l
The inspector noted, during the PT examination of welds marked (t),
that the licensee pre-cleaned and applied penetrant in accordance
with their procedures and consistent with the ASME Code.
After
approximately five minutes, of the penetrant dwell time, islands
appeared in the penetrant where the dye did not wet the inspection
area of interest.
The licensee installed a drape over the
inspection area to preclude contaminates from dripping from above,
and made two more attempts with progressively more aggressive pre-
cleaning methods with the same negative results.
The licensee
indicated that they were able to conduct an acceptable examination
only after they secured the ventilation in the cubical containing
the piping.
The above demonstrates that the licensee and their
contractor will take whatever measures are required to conduct
meaningful examinations.
During the first attempt to PT examine the welds indicated above,
the Health Physics (HP) technician who was providing continuous
coverage for the examinations being conducted in this locked
radiation area, was struck in the head by a falling wrench.
The
technician was not wearing a hard hat and sustained a laceration to
the scalp which required a number of stitches.
Hard hats were
available but their use was optional in the containment building.
By the end of this inspection the licensee had acquired additional
hard hats and mandated their use in all but Foreign Material
Exclusion areas of the containment building.
The inspector noted that the licensee had applied a Hazard
Identification System label to each individual can of penetrant
material.
These labels, in most cases, were applied such that the
material type and batch number on the manufacturers label were
covered.
The Hazard Identification System labels included hazard
information, procurement information, and in most cases, but not
all, material batch numbers.
The inspector's concern is that the
batch number transfer process, if accomplished, introduces the
potential for error and the eventual loss of traceability for the PT
materials.
The licensee indicated that would look into the matter.
The inspector reviewed the certification documentation for the PT
cleaner, developer and penetrant (See Table 1 below).
~l
7
The inspector reviewed the certification, qualification, and visual
acuity documentation for the PT examiners (See Table 2 below).
The examinations were performed satisfactorily.
Magnetic Particle Examination (MT)
The inspector observed MT examinations of the welds listed below.
The observations were compared with the applicable procedures and
the Code.
The inspector performed an independent evaluation of the
indications obtained, to confirm the NOE examiner's evaluation.
Magnetic Particle Examinations Observed
Weld No.
Drawing No
System
1-24
2-26
ll 548-WKS208A5
ll 548-WKS208A5
Relative to the MT examinations above, the inspector noted that
although marginally acceptable contrast was obtained between the red
MT powder and the dark brown tightly adhering oxide coating on one
of the welds examined, significantly better cohtrast would have been
obtained had grey powder been used .
The inspector reviewed the certification documentation for the MT
powder, the yoke, and the 10 Lbs. test weight (See Table 1 below).
The inspector reviewed the certification, qualification, and visual
acuity documentation for the MT examiners (See Table 2 below).
The examinations were performed satisfactorily.
Ultraso_nic Examination (UT)
The inspector observed UT examinations of the welds listed below.
The observations were compared with the applicable procedures and
the Code.
The inspector performed an independent evaluation of the
indications obtained, to_confirm the NOE examiner's evaluation.
Weld No.
1-09
1-10
Ultrasonic Examinations Observed
Drawing No
System
ll 48-WKS-022Al
1148-WKS-022Al
Safety Injection
Safety Injection
I
I
I
8
Ultrasonic Examinations Observed
Weld No.
Drawing No
System
1-11
1148-WKS-022Al
Safety Injection
1-12
1148-WKS-022Al
Safety Injection
1-24
11548-WKS-2018A5
The inspector observed data acquisition for the automated ultrasonic
examination of reactor vessel ,;C" hot leg nozzle to vessel weld
employing the H Ultrasonic Data Recording and Processing System
(UDRPS).
These observations were made at the remote data
acquisition site and at the local control site inside the
containment building.
The inspector reviewed the 17 preliminary
indications identified to date.
The inspector reviewed the certification documentation for the UT
instruments, transducers, and couplant (See Table 1 below).
The inspector reviewed the certification, qualification, and visual
acuity documentation for the UT examiners (See Table 2 below).
The examinations were performed satisfactorily.
Eddy Current Testing (ET) Steam Generator. (S/G) Tubing
The licensee performed 100% bobbin coil examination (tube sheet to
tube sheet) of the non-plugged tubes in the "A" S/G, and Rotating
Pancake Coil (RPC) examinations of 301 tubes from 6" below to 6
11
above the top of the tube sheet (secondary side).
Five tubes were plugged in the one generator examined by the
licensee, this outage, as indicated below.
The inspector observed ET data acquisition activities.
The
observations were compared with the applicable procedures and the
Code.
The analysis was being conducted at the W Pittsburgh
facility, and thus not available for observation.
The inspector
reviewed the RPC data for the ten most significant indications .
---- -
- ---=- - =- =-=--- .=--=---==-~ -- - -
S/G
A
B
C
Total
S/G
A
B
C
Total
Notes:
AVB
-
MBM
-
EB
0
@
0
9
Surry Unit l Plugging History
Preservice
1984
1986
1990
1
3MBM
0
0
1
1 MBM
2MBM
0
0
0
2EI)*
20
2
4
4
2
Surry Unit 2 Plugging History
Preservice
1985
1993
1
l
0
0
0
2AVB
1
0
0
2
1
2
Anti-Vibration Bar
Manufacturing Buff Mark
1995
50
0
0
5
1992
2AVB
0
0
2
Total
7.
2
1
10
1994
0
4AVB
0
4
1 Obstruction - plugged and 1 MBM - Tube Pull
Top of Tube Sheet Indication - Tube Pull
Foreign Object O.D.
1 Obstruction
1 Single Axial Indication >40
1 Multiple Axial Indication >40
2 Non-Quantifiable Indications
The examinations were performed satisfactorily.
Thermally Treated Inconel Alloy 600 Mechanical Tube Plugs
Total
6
8
4
18
Westinghouse notified the licensee, by letter OG-94-107 dated December
30, 1994, of recent field experience with Alloy 600 thermally treated,
mechanical S/G tube plugs that would necessitate a revision to the
corrosion algorithm presented in WCAP-12244. The revised algorithm was
10
incorporated in WCAP-12244, Revision 3.
The licensee has identified
four plugs, in Unit 1 S/Gs, that have 1992 required repair dates (Unit 1
S/G A - three plugs, S/G B - one plug).
Only one plug was identified in
Unit 2 S/Gs, which had a 2010 required repair date.
Table 1
NDE Equipment and Consumables Records Examined
Equipment/Consumables
Serial No/ Heat No./ Lot No./
Batch No.
Cleaner
Developer*
Penetrant. .
Red.No. 8 Powder
44-G4
426-G6
311-C47, 42-H47
92G027
MT 10 LBS. Test Weight
Block #15
922194
UT Instruments
UT Transducers
93137807, 93137907, W09746,
W09748, and Wl0792
04872, 17259, 011038, MI4208,
33608, 33616,88-582, 93-798,93-408, 93-675,88-568, 93~
797, H4107,93-677, 93-796,93-411, and H4108
UT Couplant
092071
ET MIZ-18 Remote Data Acqui-
sition Units (RDAU)
W0724, W0982, and W05051
ET Calibration Standards
MGT-007-94, MGT-005-94, AV-
015-89, AV-014-89, Z-2430, Z-
1938, Z-5219, AB-010-88, AB-
004-88
ASME B&PV Code,Section V, 89NA paragraph T-625(b) states:
"When examining austenitic stainless steel or titanium,
all materials shall be analyzed individually for chlorine
and fluorine contents ... " T-625 further requires that the
analysis for chlorine be accomplished in accordance with
ASTM D 808 or SE-165 annex 2 and the analysis for fluorine
be accomplished in accordance with SE-165 annex 3, both
reported as a percentage of the residue by weight.* All
but one of the certification documents, provided by the
licensee, reported the halogen family contaminants in the
PT consumables as total halogens or as chlorine only.
From the report provided the inspector, it could not be
determined whether the PT consumables were consistent with
the 89NA Edition of ASME B&PV Code Section V applicable to
11
the PT examination of welds 1-09, 1-10, 1-11 and 1-12 on
Drawing 11548-WMKS-0122Al.
The licensee is pursuing a
clarification in this matter.
Table 2
Qualification, Certification, and Visual Acuity Records
Examined
Examiner
MOH
PEMc
JOO
AJD
HRH
SFR
WJS
SHT
RGC
WDG
PGM
KLS
DGT
JMC
UT-II
UT-II
UT,. II I
UT-II
MT-II
MT-II
MT-II I
MT-II
Method-Level
PT-II
VT(l,2,3)-II
PT-II
PT-III
VT(l,2,3)-III
PT-II
ET-IIA *
ET-III
ET-III
ET-IIA
ET-II
ET-II
ET-II
ET-I
ET-II
ET-IIA
MSM
ET-IIA
ET-IIA
JTS
ET-I IA
TFS
ET-IIA
UT-1
UT-I
MT-I
UT -I I IL
MT -II
UT-II
MT- I I
UT- I I
MT- I I
PT-II
PT-II
PT-II
DWS
AWM
KOH
JHJ
JWB
UT-III
UT-II
MT -I II
PT -II I
,
,
I'
12
Records support the conclusion that examinations were conducted in
accordance with applicable procedures and regulatory commitments.
Within the areas examined, no violations or deviations were identified.
3.
Flow Accelerated Corrosion (FAC) (49001)
The licensee has established a FAC inspection program which implements
the CHECWORKS EPRI (Electric Power Research Institute) computer code,
industry experience, and previous inspection data as predictive tools
for determining and prioritizing inspection locations.
The inspector
conducted interviews with licensee and contractor personnel and reviewed
records as indicated below.
Observations/Findings
During RFO 12, the licensee planned to examine 97 locations in their FAC
program.
At this writing the licensee had identified three FAC degraded
components.
Two components will be replaced this outage, one will be
repaired this outage and replaced at the next refueling outage.
Two of
the three replaced component's wall thickness had been reduced below
code Minimum (2-FW-PPS-l Code Minimum 0.965"
Actual Measured Minimum
0.767", 2-FW-PPS-4 Code Minimum 0.965"
Actual Measured Minimum 0.887").
The inspector reviewed the Wall Thickness Engineering Evaluations for
the below listed components.
Wall Thickness Engineering Evaluations Examined
Component
Component
System
Disposition
Identification
Type
2-SD-PSF2-298
6" goo Elbow
Steam Drain
Reinspect in 2005
2-SD-PSF2-297
6" goo Elbow
Steam Drain
Reinsoect in 2000
2-SD-PSF2-282
6" goo Elbow
Steam Drain
Reinspect in 1999
2-MS-PSFl-33
5" 45° Elbow
Reinspect in 1999
2-SD-PSF2-296
6" goo Elbow
Steam Drain
Reinspect in 2006
2-SD-PSFl-45
6" 45° Elbow
Steam Drain
Reinspect in 2006
2-SD-PSFl-44
6" 45° Elbow
Steam Drain
Reinspect in 2006
2-SD-PSF2-281
6" goo Elbow
Steam Drain
No further inspection
required unless opera-
tional conditions or
criteria change .
2-SD-PSF2-255
4.5" 90°
Steam Drain
Reinspect in 2000
Elbow
-..=-=---~-==---=-=--
-13
Wall Thickness Engineering Evaluations Examined
Component
Identification*
2-BD-PSF2-65
2-SD-PSFR-50
2-FW-PPS-4
2-FW-PPS-4
Component
Type
3.5" 90°
Elbow
2"x4" Con-
centric Re-.
ducer
18" Pipe
18" Pipe
System
Blowdown
Steam Drain
Dispositio*n
No further inspection
required unless opera-
tional conditions or
criteria change.
No further inspection
required unless opera-
tional conditions or
criteria change.
Replace
Replace
The licensee has established and continues to implement an effective
program to maintain high energy carbon steel piping systems within
acceptable wall thickness limits.
Within the areas examined, no violations or deviations were identified.
4.
Feedwater Heater Replacement (55050)
The inspector reviewed procedures, observed work activities and reviewed
selected documents as indicated below, to evaluate the licensee's
performance in the replacement of the Unit 2 Feedwater heaters.
The
Feedwater heaters were built.to the requirements of ASME Code Section
VIII 1986, and installed in accordance with ANSI B31.l-1967.
The inspector reviewed, for technical adequacy Design Change Packige 87-
13-2, "Replacement of First and Second Point Feedwater Heaters and Fifth
Point External Drain Coolers.
11
The inspector observed welding in
progress as indicated below.
The inspector reviewed certification
documentation attesting to the qualification and maintenance of qualifi-
cation for the.welders observed.
The inspector reviewed the welding
filler material Certified Material Test Reports (CMTR)s.
The inspector
reviewed the Welding Procedure Specification (WPS) and the supporting
Procedure Qualification Records (PQR)s.
The documents were examined for
compliance with licensee procedures and Sections II and IX of the ASME
B&PV Code.
Welding Fi 11 er Material CMTRs Examined
Type
Size
Heat/Lot No.
E-7018
3/32"
91201/292814
E-7018
1/8"
T28061/2C430A01
5 .
103,
14
Welder's Qualification Certification
Documentation Examined
WA-4801, AN-3560 and RM-9660
WPSs Examined
WPS
. PQR
Revision E, 05/91
101 Revision B 9/7/82
102 Revision A 1/25/85
103 1/28/85
105 Revision B 8/27 /82
The Design control package for the Feedwater heater replacement was
appropriate to the circumstances.
Welding associated with the Feedwater
heater replacement was accomplished by properly qualified and certified
- welders in accordance with properly qualified welding procedures using*
appropriately certified welding filler material.
Within the areas examined, no violations or deviations were identified.
Exit Interview
The inspection scope and results were summarized, on February 24, 1995,
with those persons indicated in paragraph 1.
The inspector described
tbe areas inspected.
Although reviewed during this inspection, propri-
etary information is not contained in this report.
Dissenting comments
were not received from the licensee.
6.
A~ronyms and Initialisms
ANSI
AVB
ID
MBM
No.
NRC
p. E.
American National Standards Institute
American Society of Mechanical Engineers
Anti-Vibration Bar
Boiler and Pressure Vessel
Certified Material Test Report
Demonstration Power Reactor
Electric Power Research Institute
Eddy Current
Identification
Inservice Inspection
Manufacturing Buff Mark
Magnetic Particle
Number
Nuclear Regulatory Commission
Professional Engineer
Procedure Qualification Record
PS I
RC
RDAU
Rev.
RPC
S/G
VCR
w
WPS
15
Preservice Inspection
Quality Assurance
Remote Data Acquisition Unit
Revision
Refueling Outage
Rotating Pancake Coil
Steam Gener,ator
Ultrasonic
Virginia Corporation of Richmond
Virginia Electric Power Company
Welding Procedure S~ecification