ML17138A434
| ML17138A434 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/25/1978 |
| From: | Durr J, Ebneter S, Jernigan E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17138A433 | List: |
| References | |
| 50-387-78-16, 50-388-78-15, NUDOCS 7811130151 | |
| Download: ML17138A434 (10) | |
See also: IR 05000387/1978015
Text
U.S.
NUCLEAR REGULATORY COMMISSION
OFFICE
OF INSPECTION AND ENFORCEMENT
Region I
50-387/78-16
Report
No.
50-388/78-15
~D-387
Docket No.
50-388
CPRCZI
License
No. CPPR-102
Prior ity
Category
Licensee:
Penns
lvania Power and Li ht
Com an
2 North Ninth Street
Allentown, Penns
lvania
18101
Inspection at:
Berwick, Pennsylvania
.
Inspection
conducted:
August 29 - September
1,
1978
.
P. Durr, Reactor Inspector
CF'nspectors:
. Jgrnigan,
R)actor Inspector
Facility Name:
Sus
uehanna
Steam Electr't tion, Units
1
and
2
dat
signed
~ ZE I 7g
date signed
Approved
ne er,
c
g
ie,
ng~neering
Support Sectio
o. 1,
RCSES
Branch
date
signed
date
igned
Ins ection
Summar
Ins ection
on Au ust
29 - Se tember 1,
1978
(Re ort Nos.
50-387/78-'16;
50-388/78-15
Areas Ins ected:
Routine,
unannounced
inspection
by regional
based
inspectors
of
t e pspe
we
sng activities
and piping quality assurance
documentation;
observa-
tion of baseline
pre-service
inspection activities;
and review of the component
storage
and maintenance
program.
The inspection
involved 56 inspector-hours
on
site by 2
NRC regional
based
inspectors.
Results:
In the
5 areas
inspected,
no items of noncompliance
were identified.
Region I Form 12
(Rev. April 77)
y5/
Vsl g
q go~~
DETAILS
Persons 'Contacted
Penns
lvania Power'and'Li
ht
Com an
L. Ballard, Site guality Assurance
Engineer
R. Beckley, Site guality Assurance
Engineer
- J.
D. Green,
Resident guality Assurance
Engineer
Bechtel
Cor oration
- M. K. Boone,
Lead Welding Engineer
- M. A. Drucker, guality Assurance
Engineer
G. Gelinas, guality Control Engineer
J.
Khandhar; Mechanical
equality Assurance
Engineer
H., F. Lilligh, Project guality Assurance
Engineer
R.
Lamb, guality Control Engineer,
Welding
H. Omar,
Lead Storage
and Maintenance
Engineer
B. Ott, Lead guality Control
Engineer
- A. L. Spielhagen,
Project Field Engineer
- K. G. Stout, Assistant Project Field guality Control Engineer
Com an
- E. A. Gustafson,
Resident Site Manager
- J.
M. LeVasseur,
Site guality Control Representative
W. Miller, Nondestructive
Examiner,
Level III
R.
M. Pulsifer,
NED Representative
R. Wagner,
I8SE guality Assurance
Supervisor
- denotes
those present at the exit interview.
Plant Tour
The inspectors
toured the units
1 and
2 reactor buildings observing
work activities, installed equipment,
storage
and protection,
and
evidence of the implementation of the quality control program.
They discussed
the technical
aspects
of the work in progress with
the construction craftsmen,
supervisors,
and quality control per-
sonnel.
No items of noncompliance
were identified.
Licensee Action on Previous
Ins ection Findin
s
(Closed)
Unresolved
Item (387/77-12-02):
Process
control check-
lists (weld card).
The licensee
issued Interoffice Memoranda
dated
September
28,
1977 and January
27,
1978,
both directing the addition
of nondestructive
testing requirements
to the form WR-5, items
26
and 28,
as appropriate,
for the removal of temporary attachments
and repairs.
In addition, the licensee verified the implementation
of this requirement
by direct observations
documented
on QAR-F-317.
The
NRC inspector
observed
welding in progress
and verified that
the associated
form WR-5 did require that pipe from which temporary
attachments
had
been
removed specified nondestructive
testing in
item 28.
(Closed)
Unresolved
Item (387/78-01-05):
Insufficient examination
coverage of welds
DC,
DE, and
DF in the reactor vessel.
The examination contractor
has
documented
in detail
those welds in
question
and additionally,
has
prepared
plots for each weld configu-
ration to demonstrate
that the maximum possible extent of the
affected welds
have
been
examined.
These plots are
a matter of the
preservice
inspection record.
This approach is consistent with
Section
XI of the
ASME,
B8PV Code.
(Closed)
Unresolved
Item (387/78-01-04):
Lack of appropriate
acceptance
standards.
Implementing
NDE procedures
have
been re-
vised to reflect evaluation,
acceptance/reject
criteria consistent
with the applicable
Code section.
Additionally, this is consistent
with specification
8856-M-166, Revision 1,
Addendum 2,
and current
examination practices
with respect
to dispositioning indications.
The inspector audited volumetric and surface
examination
procedures
for verification of correct acceptance/reject
criteria.
Reactor'Coolant
Pressure
Boundar
Pi
e Weldin
- Observation of
Wor
cts vs tes
nt t
The following pipe welding activities were observed
and it was
verified that they were being performed in accordance
with the
III and
IX codes,
the Quality Assurance
Manual
and regulatory requirements:
The welding of the root pass for the 26" diameter,
schedule
1.156", main steam isolation valve weld VNB-B21-2-FW B6.
Verified the weld identification, weld procedure,
weld appear-
ance,
welder qualification,
and quality control documentation.
The fitup and'root
pass welding of the 26" diameter,
schedule
1.156", main steam line pipe to fitting weld VNB-B21-2-FW B3.
Verified the weld identification, joint preparation,
procedure,
weld appearance,
welder qualification, and quality
control documentation.
No items of noncompliance
were identified.
5.
Reactor
Coolant Pressure
Boundar
Pi in
- Review of ualit
Records
The following reactor coolant pressure
boundary piping component
quality assurance
documentation
was reviewed for compliance with
ASME III code requirements,
FSAR commitments,
and regulatory re-
quirements.
~Com onent
Diameter
~S stem
Pipe Spool
DCA-110-2-4
24"
'HR
Pipe Spool
DLA-104-1-3
12"
Pipe Spool
B21G001
Item 8
26"
MS
Check Valve 24DCA-CK-AO-F050A-PT
24"
W 'W
The review consisted of selective
examinations of the material test
reports,
nondestructive
examination records,
manufacturer
statements
of conformance,
and fabrication/inspection
reports.
The "General Electric guality Control Checklist Nuclear
Power
Piping 127, Revision
2". for the 26" diameter,
main steam pipe spool
B21G001,
item 8,
shop sheet
F-12, indicates that for the 1.037"
thick circumferential
A and
B the preheat
was 175'F.
Further
investigation of the documentation for 10 similar main steam pipe
welds disclosed that the preheat
was 175'F in all cases.
The
III Code data form NPP-1 states
that the pipe was designed
and
fabricated
in accordance
with the
1971 edition of ASME III, addenda
summer
1971,
Class
1.
Paragraph
NB-4620 of the
1971
code requires
a 200'F preheat or a post weld heat treatment for this pipe.
However, the
FSAR, table 3.2-3 note 5, states
that piping field
installation post weld heat treatment will be made in accordance
with the
ASME III Code,
1974 edition with the
summer
1976 addenda.
Paragraph
NB4620 was changed
in code
addenda winter 1973 and again
in summer
1976 to exempt material of
1 1/4" thickness or less
from
preheat
and post weld heat treat requirements.
The licensee's
representative
stated that an engineering
evaluation
would be performed to verify that
a transition from the'971
code
to a later edition for post weld/preheat treat requirements
would
not adversely affect the design.
He also stated that
a records
review would be performed to assure. that any
GE supplied
P-1 pipe
materials
.
1 1/4" to
1 1/2" in thickness
were properly post weld/
preheat treated.
This item is considered
unresolved
pending
com-
pletion of the foregoing evaluation
and document review.
(387/78-
16-01)
In addition, the material certifications for some of the above
listed components
do not completely list all characteristics
re-
quired to be reported
by the materials specifications.
Specifically,
the metallurgical report for the 90'lbow in pipe spool
DCA-110-2-
4 does not list the hardness
as required
by specification
SA-240.
Also, the welding wire certification for the E308-15 filler metal,.
heat
No.
740654A,
does
not list the results of the fillet weld test
required
by SFA-5.4.
The licensee
stated that the lack of some test results
on material
certifications
has
been recognized.
A program is being
implemented
to review all document
packages
for this problem.
This item is
considered
unresolved
pending the formal implementation of the
review program (387/78-16-02).
Safet
Related
Com onents
Stora e, Handlin
, and Protection
Units
1 and
2
The inspector observed
the storage
and protection provided for the
reactor recirculation
system
pumps
and isolation valves,
pumps,
residual
heat
removal
(RHR) pumps,
and residual
heat
removal
system heat exchangers.
The inspector
found that the storage
and
protection provided for the above
mentioned
components
was consistent
with the requirements
of the applicable
procedures
and specifications,
with the exception of the heat exchangers.
During inspection of
the in-place .storage of the
RHR heat exchangers,
the inspector
observed that the internal nitrogen atmosphere
had
been
removed in
February
1977, to permit modification work and installation of
connecting piping.
Removal of the nitrogen atmosphere
was acceptable
to the component supplier for the performance of the modification
<<r
work.
However, it was not clear to the inspector
that the above
concurrence
was intended to be for an indefinite period of time.
This item is considered
to be unresolved
pending the supplier's
approval of long term storage of the
RHR heat
exchangers
without
the specified internal nitrogen atmosphere
(387/78-16-03
and 388/78-
15-01).
7.
Installation
and Stora
e Records
The inspector audited
equipment
maintenance
requirements for the
aforementioned
components
listed in paragraph
6.
The inspector
also verified the associated
storage
inspection
records.
The
inspector found that storage
inspections
had
been
performed at the
required frequencies.
The inspector concluded that the equipment
supplier's
storage
requirements
were being met except
as discussed
in paragraph
6 above.
No items of noncompliance
were identified.
8.
Preservice
Ins ection Procedures
The inspector
reviewed procedures
for work activities relative to
preservice
examinations.
The inspector considered
the above item
with regard to criteria delineated
in 10 CFR 50.55.a(g)
and the
ASME Boiler and Pressure
Vessel
Code,
Section XI, 1974 edition
including the Winter 1975 Addenda.
The inspector
examined the
following documents relative to the above.
General Electric Company
Procedures:
l
ISE-QAI-322, Revision 3, dated
March 29,
1978, titled "Ultrasonic
Examination of Similar and Oissimilar Metal Welds."
ISE-QAI-300, "Personnel
Qualification and Certification Program."
I
GE-IPSE Orawing 160-78C-0255,
"Ultrasonic Test Calibration
Standards
- Safe-Ends."
The inspector'considered
the following aspects
relative to the
inspection:
Implementing procedures
reviewed,
approved,
and controlled.
Specified type of apparatus,
transducers,
and calibration
technique,
frequency,
and
beam angles.
Personnel
qualification requirements
consistent with the
ASME,
BSPV Code,
Section XI, and SNT-TC-lA.
Reference
level for monitoring discontinuities is established.
Method of recording/reporting significant .indications.
No items of noncompliance
were identified by the inspector.
9.
Witness of Preservice
Ins ection Activities
Unit 2
The inspector 'witnessed
the volumetric examinations of selected
welds using the manual ultrasonic technique.
Specifically, examina-
tions of the dissimilar metal
welds associated
with the recirculation
inlet nozzles
were observed.
Examinations
performed from the
stainless
steel
extension
piece revealed
indications exceeding
the
recordable level.
These indications
were observed
in nine of the
ten nozzles
examined.
The radiographic
technique
was used
on
portions of welds in four nozzles to verify the presence/location
of indications within the material.
The radiographs
disclosed
an
apparent
discernable
linear indication in each weld radiographed.
These indications could be correlated with those located
by ultrasonic
examination.
The safe-end
to extension
piece assemblies
were
fabricated off site and therefore sufficient manufacturing
documenta-
tion was not available for a complete evaluation at this time.
However, the licensee's
representative
stated that
a complete
evaluation
would be made.
This matter is unresolved.
(387/78-
16-03)
The inspector considered
the above
items with regard to criteria
delineated
in the
ASME Boiler and Pressure
Vessel
Code,
Section XI,
including Winter 1975 Addenda,
and requirements
of the implementing
procedure.
The inspector considered
the following aspects
relative to the
examination
being conducted.
Personnel
qualification of each inspector performing examinations.
This included the three levels of certification, Level 1, ll,
and 111.
Compliance with procedural
requirements
in the following
areas.
Test instrument
was operating
on required frequency,
instrument linearity, and signal attenuation
accuracy.
Scanning
techniques
(beam angles,
scanning
surface,
scanning
rate,
and direction)
and extent of coverage.
Calibration methods
including block size
and reference reflectors.
Beam angles
and distance
amplitude correction technique.
Recording
technique of reference reflectors.
)
No items of noncompliance
were identified.
10.
Data Review of Preservice
Ins ection
The inspector
examined
records related to volumetric/surface
examin-
ation of welds required to be examined for compliance with the
requirements of Section
XI of the
ASME,
B8PV Code.
The inspector
examined preliminary reports/documentation
of examinations
performed
on all ten of the recirculation inlet nozzle welds.
The inspector's
review was to ascertain
compliance in the following
areas:
the method, technique,
recording/reporting of indications
are as stipulated in the implementing procedure.
No items of noncompliance
were identified.
ll.
Unresolved
items are matters
about which more information is re-
quired in order to ascertain
whether they are acceptable
items,
items of noncompliance,
or deviations.
Unresolved
items disclosed
during the inspection
are discussed
in paragraphs
5, 6, g, and .10,
12.
Exit Interview
The inspectors
met with licensee
representatives
(denoted
in para-
graph
1) at the conclusion of the inspection
on September
1, 1978.
The inspectors
summarized
the scope
and findings of the inspection.
d )
0