ML18003A473
| ML18003A473 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 02/16/1979 |
| From: | Bradley R, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18003A466 | List: |
| References | |
| 50-400-79-02, 50-400-79-2, 50-401-79-02, 50-401-79-2, 50-402-79-01, 50-402-79-1, 50-403-79-01, 50-403-79-1, NUDOCS 7903220173 | |
| Download: ML18003A473 (7) | |
See also: IR 05000400/1979002
Text
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UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30303
RePort
Nose I
'50-400/79-02,
50-401/79-02,
50-402/79-01
and
50-403/79-01
Licensee:
Carolina
Power and Light Company
336 Fayetteville Street
Raleigh,
27602
Facility Name:
Shearon Harris Nuclear Power Plant
License
NoseI
CPPR-158,
CPPR-159,
CPPR-160
and
CPPR-161
Inspection at:
Shearon Harris Nuclear Power Plant
ew Hill, North Carolina
I
Inspector:
R. D.
ley
Approved by:
~ l/
A. R. Herdt, Chief
Projects
Section
Reactor Construction
and Engineering
Support Branch
D te
igned
g
/d'te
Signed
SUMMARY
Inspection conducted
January
23-26,
1979
This routine,
unannounced
inspection involved 31 inspector-hours
on-site
in the areas of project status;
licensee action on previous inspection
finding; concrete
placement-main
dam conduit encasement;
licensee
identified items;
document controls;
and walk-through inspection of the
power block, batch plant, aggregate
testing laboratory,
and the energy
and environmental
center.
Results
Of the five areas
inspected,
no apparent
items of noncompliance
or
deviations
were identified in four areas;
one apparent
item of noncompli-
ance
was
found in one area (infraction-lack of document control, para-
graph 5.c).
-
'y90882II I'73
h
DETAILS
Persons
Contacted
Carolina
Power
and Li ht
Com an
(CPRL)
-S.
"T
"R
""A.
""G.
-K.
D.
D. Smith, Manager,
Power Plant Construction Department
H. Wyllie, Manager,
Nuclear Construction Section
M. Parsons,
Site Manager
Lucas,
Resident
Engineer
L. Forehand,
Principal
QA Specialist
V. Hate,
Senior
QA Engineer
L. Montague, Director of Project Analysis
Canady,
Geologist
/
Other licensee
employees
contacted
included two QA/QC specialists,
two QA/QC inspectors,
two engineers,
one aide
and two office personnel.
Daniel Construction
Com an
-W. D. Goodman,
Construction Project Manager
P.
K. Harris,
Document Control Supervisor
-Attended exit interview
Exit Interview
The inspection
scope
and findings were summarized
on January
26,
1979 with those persons
indicated in Paragraph
1, above.
The
licensee
was informed of the apparent
noncompliance
discussed
in
paragraph 5.c.
The licensee
acknowledged
these findings.
Licensee Action on Previous
Ins ection Findin s
(Open) Noncompliance
No. 400,401/78-08-03,
Failure to Calibrate
Fine Aggregate
Sieves.
The inspector
reviewed the licensee's
letter of response
dated January
2,
1979, held discussions
with the
principal
QA specialist
and the senior civil QA specialist,
reviewed
a newly issued
QC Instruction 13.5
on sieve analysis,
examined
new
sieve acceptance
equipment,
and reviewed card files and the sieve
certification records.
In that actions
planned for including sieve
acceptance
activities under the site calibration program are
incom-
plete, this item will remain open.
Unresolved
Items
Unresolved
items were not identified during this inspection.
-2"
5.
Inde endent Ins ection Effort
Pro'ect Status
and Site Ins ection
On January
23,
1979,
the inspector
conducted
a walk-through
inspection of the site which included observation of concrete
placement at the main dam,
concrete
cylinder curing in the
Energy and Environmental Center,
construction activities in
the power block area,
and facility activities at the batch
plant and aggregate
testing laboratory.
Total concrete
placed to date recently exceeded
200,000 cubic
yards.
Chicago Bridge and Iron Company
has
completed erection
of the seventh wall liner ring for the unit
1 containment
building.
Installation of vertical reinforcing steel
along
the face of unit 2 containment
and at the interface of reactor
auxiliary unit 2 has
been completed.
The combined work force
now totals
some 2,840 people.
Rigging International of Oakland, California has
been
awarded
the contract for installing heavy
components
and the contain-
ment
dome for all four units.
b.
Concrete
Placement Activities
The inspector monitored placement activities underway at the
Main Dam Conduit encasement
(second lift).
Records of the
first three batch tests for air content,
slump,
and temperature
for placement
number
MDD047 (mix M-54, 3,000 lbs.) were reviewed
and the fourth test performance
was witnessed
by the inspector
on January
23,
1979.
A pump was being used for placement of
the 290 yard pour with samples
being taken at pump discharge.
All recorded values
were within specified limits. It was
noted that approximately
63 yards
had been rejected
due
to placement
delays attributed to pump malfunction.
C.
Desi
n Control (Units
1 and 2)
CPS Administrative Procedure
AP-IX-02, "Document Distribution
and Control", Revision 7, governs site Document Control activi-
ties.
Detailed internal Work Guides
have been
completed for
the various areas of Document Control and identify individual
personnel responsibilities.
Document Control clerks have been
receiving individualized on-the-job instruction in the use of
work guides
and are certified under
CPRL training procedure
AP-IX-13.
Internal audits of field drawing files are
now
being conducted
on
a monthly basis
and office files are being
audited every other month.
To verify established
measures
preclude
the use of obsolete
drawing documents,
the inspector selected
fourteen safety-
related
drawings involving civil/structural, electrical
and
mechanical disciplines for the fuel handling,
waste processing,
containment,
and reactor auxiliary buildings.
Drawings were
selected
from stick files maintained in the Field Superintendent's
trailer (control number 001), the Field Engineering Office
trailer (control number 035), site Mechanical Engineering
Section (control number 370),
and the site Electrical Engineering
Section (control number
188).
Revision levels of drawings
from each of the above
areas
were
reviewed to determine if they were the latest revisions
recorded
in the Document Control document record card file.
A comparison
was also
made between
the record card file and the Document
Control master reproducible
drawings.
The inspector
determined that the present
system for document
control does not provide assurance
that drawings, including
changes
thereto,
which prescribe activities affecting quality
are distributed to and used at the location where the prescribed
activity is performed.
This was evidenced
by the fact that:
(1)
The master
copy of drawing CAR-2167-G-1399R3 did not
reflect that RCI-C-269 was applicable.
(2)
Master drawing CAR-2168-G-153SOlR7
referenced
FCR-AS-004
as being applicable
when it actually affected
drawing
CAR-2168-G-153S02
only.
(3)
The following two drawings selected
from the stick files
(control number 001) maintained for the Fuel Handling
Building and the Reactor Auxiliary Common Building in the
Field Superintendent's
trailer, were not stamped
to
indicate all of the applicable
FCR's
and RCI's:
(a)
Drawing CAR-2167-G-1399R3 indicated that DCN-550-135
was applicable,
but omitted reference
to RCI-C-269
which was also applicable.
(b)
Drawing CAR-2167-G-1610R3 disclosed
that FCR-C-332
and RCI-C-336 were applicable,
but omitted reference
to FCR-C-336.
(4)
The following two drawings selected
from the stick files
(control number 035) maintained in the Field Engineering
Office trailer, did not indicate the latest applicable
revision level or all appropriate
FCR/RCI documents:
(a)
A copy of drawing CAR-2167-G-1897R3 with FCR-C-188
outstanding
was found in the files after revision
4
had been issued.
Review of the Document Transmittal
form issued
by Document Control indicated that
revision
4 had been received
and the recipient
had
destroyed
revision 3.
(b)
Drawing CAR-2168-G-153SOlR7
did not reflect that
FCR-AS-001,
FCR-AS-002,
FCR-AS-003
and RCI-C-52,
RCI-C-61, RCI-C-76, RCI-C-84 and RCI-C-85 were
applicable.
The drawing did reference
DCN-650-05 which
applies to another
drawing,
CAR-2168-G-154SOl.
This matter
was discussed
with CPRL management prior to and at the
exit interview and
CPGL has
committed to investigating the problem
and taking necessary
corrective action.
This item has
been identified as
a noncompliance in the infraction
category
and
has
been designated
as 400,401/79"02-01,
"Lack of
Document Control".
Licensee Identified Items
Prior to this inspection,
the licensee identified several
items under
Items reported were:
a
~
(Closed)
Item (400/78-08-07),
Containment drawings, details omitted.
The licensee's
final report of November 28,
1978
was reviewed
and
evaluated
and discussions
were held with the site principal gA
specialist
and resident engineer.
The omitted details
were
identified on DCN-550-112 and subsequently
incorporated
onto
drawing CAR-2167-G-0630
by revision
4 on November
13,
1978.
The
corrective actions identified in the report have been
implemented
and Region II has
no further questions.
b.
(Closed)
Item (400/79-02-02,
401/79-02-02,
402/79-01-01,
403/79-01-01),
Welder qualification Test
Coupon Thickness not
Compatible with ASME Code.
CPM, informed Region II by telephone
on January
4,
1979 that the potentially'reportable
deficiency had
been determined to be nonreportable.
The inspector held discus-
sions with the site principal gA specialist,
the welding senior
gA
specialist,
and the resident
engineer.
The applicable Deficiency
and Disposition Reports
(DDR's
190 and
194) were examined
and the
licensee's justification for nonreportability contained in a-
memorandum, from A. M. Lucas to Mr. George Forehand
dated January
9,
1979,
was evaluated.
It was determined that the wrong bend test
jig had been
used to qualify two welders
who had completed
15
safety-related
on Category
3 service water pipe.
All welding
being performed by these
welders
was stopped
and the welders
were
immediately retested
without additional training and both passed
on the first test.
It was also noted that both men are experienced
welders.
The affected welds passed all routine visual inspections
plus final MT (100 percent) without any problems.
In addition,
each weld will be subjected
to bydpoatatic pressure
testing
go
verify system integrity.
The bend test jigs being used by
COL have
now been conspicuously identified to facilitate
proper selection of jig size versus
coupon thickness.
Region II
has
no further questions
at this time.
(Open)
Item (400/79-02-03),
and Reactor Coolant
Pump Embedment Plate Welds.
The licensee
reported
the subject
potential deficiency to Region II on January
12,
1979.
Approxi-
mately nine anchor plates (for embeddment)
fabricated
by a
supplier to
CPGL were found to have unacceptable
linear indi-
cations after nondestructive
examination
was performed by the
supplier
and prior to performance
of post weld heat treatment
by a subtier supplier.
The plates
involved had not been
delivered to the site.
This item remains
open pending
NRC
review of the licensee's
final evaluation.