ML18017A627
| ML18017A627 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 07/10/1979 |
| From: | Bradley R, Bryant J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18017A624 | List: |
| References | |
| 50-400-79-10, 50-401-79-10, 50-403-79-09, NUDOCS 7908160415 | |
| Download: ML18017A627 (6) | |
See also: IR 05000400/1979010
Text
8AE
gy,R
Egg
P~
o
++*++
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I I
101 MARIETTAST., N.W., SUITE 3100
ATLANTA,GEORGIA 30303
Report Nos.
50-400/79-10,
50-401/79-10,
50-402/79-09,
50-403/79-09
Licensee:
Carolina
Power
and Light Company
411 Fayetteville Street
Raleigh, North Carolina
27602
Facility Name:
Shearon Harris Nuclear Power Plant
Docket Nos.
50-400,
50-401,
50-402,
and 50-403
License
Nos.
CPPR-158,
CPPR-159,
CPPR-160
and
CPPR-161
Inspection at Shearon Harris site near Raleigh, North Carolina
Inspector:
R
.
ra
e
Date Signed
Approved by:
rya
,
ection Chief,
RCES Branch
ate Signed
SUNHARY
Inspection
on June
12-15,
1979
Areas Inspected
This routine unannounced
inspection involved 28 inspector-hours
onsite in the areas
of construction status;
licensee identified items;
steam generator modification;
concrete placement;
review of contractor
gA manual procedures;
IE Bulletins; and
a
walk-through inspection of the power block, storage
yard number
12,
and the con-
tainment
dome subassembly fabrication area.
Results
Of the areas
inspected,
no apparent
items of noncompliance
or deviations
were
identified.
P9 08160
DETAILS
1.
Persons
Contacted
Licensee
Employees
+P.
W. Howe, Vice President,
Technical Services
- S.
DE Smith, Vice President,
Construction Department
-R.
M. Parsons,
Site Manager
-A. M. I,ucas,
Resident Engineer
- G. L. Forehand,
Principal gA Specialist
Other licensee
employees
contacted
included two construction superintendents,
four concrete inspectors,
one carpenter
foreman,
and
one licensing engineer.
Other Organizations
C. Brooks,
Chicago Bridge and Iron Company
(CBRI), gC Welding Supervisor
J. Given,
Lumbermens
Mutual Insurance
Company, Authorized Nuclear Inspector
L. Hall, Westinghouse Electric Corporation,
Tampa Division, Welding Engineer
+Attended exit interview
2.
Exit Interview
The inspection
scope
and findings were
summarized
on June
15,
1979, with
those
persons
indicated
in Paragraph
1
above.
Methods for assuring
a
reliable concrete truck drum rotation count were discussed in detail.
3.
Unresolved Items
Unresolved
items
are matters
about which more information is required to
determine
whether
they are
acceptable
or
may involve noncompliance
or
deviations.
One
new unresolved
item identified during this inspection is
discussed in paragraph 4.b.
4.
Independent Inspection
Construction Status
The inspector
made
a walk-through inspection of the powerblock
and
storage
areas
which included observation of concrete
placement within
Unit
1 containment,
rebar installation for Unit 2 containment,
welding
and radiography of containment
dome plates,
and heat exchanger
storage
and steam generator activities in storage
yard number
12.
Erection of
the Unit
1
containment
liner is
now at the fourteenth ring.
Work
forces have completed the second liftof the Unit 2 containment building
placement
on the east
side
around
the valve chambers.
Seal
mat work
-2-
on horizontal
surfaces
and
sloped
walls for the
reactor auxiliary
building for Units 3 and 4 is continuing with an average of one concrete
placement
being
made per week.
The
combined
work force at the site
now totals
some 3300 persons.
Concrete Placement Activities
Upon arriving at the site on June
12,
1979, the inspector,
as
a part
of his walk-through inspection,
observed
a partial placement
of the
Unit
1 containment
secondary
shield wall.
This
was
a
12 foot lift
designated
as
placement
number
1CBIW233005.
A 5,000
pound,
M-72 mix
was being placed
by one
pump,
and
a total of 95 yards
was scheduled
for placement.
The inspector
reviewed the latest concrete test report
and noted the air~ slump,
and temperature
readings for a 5 yard delivery
on ticket number
34219 for truck number 24.
All results
were within
prescribed limits.
The inspector held discussions
with inspection
and placement personnel
and monitored vibration activities underway.
Surveillance of activities
at the point of truck discharge
to the
pump disclosed
an inoperative
drum revolution counter
on truck number
24 which, at that point, had
essentially
completed its discharge of concrete.
Specification CAR-SH-
CH-6, paragraph
12 states
"Each truck shall be equipped with an accurate
revolution counter."
Truck number
24 did not have an operative counter
at 3:15 p.m.
and
was
immediately taken out of service for repairs.
The inspector verified proper repair of the counter actuator in the
shop at 5:00 p.m.
A similar finding was
noted
on April ll, 1979,
and classified
as
a
Deficiency in inspection
report 50-402,
403/79-06.
As the licensee
deficiency
response
identifying proposed
corrective
steps
which will
be taken to avoid further noncompliance
had not been
received
as of
this date, this item is being identified as Unresolved Item 400/79-10-01,
"Inoperative Concrete Truck Revolution Counter." It was observed that
the yardage
discharged
by truck 24 had been placed within the specified
time
and results
of
QC acceptance
at the
pump line discharge
point
were acceptable
as observed earlier.
Steam Generator Modification
Inspection report 50-400, 401/79-08 summarized preliminary work activi-
ties underway in conjunction with the Westinghouse modification of six
steam
generators
at the Harris site.
A 24 inch auxiliary feedwater
port has
now been
cut through the four inch shell of the first steam
generator.
A weld torch assembly
proven out in the
Tampa
shops
was
used to cut the port from within the generator
in order to keep the
interior free from contamination.
The licensee's
site
QA unit has recently agreed
to perform specific
functions for Westinghouse in addition to their nondestructive
examination
responsibilities.
The licensee
has
designated
hold points
under the
Inspection
Point
Program
established
by
who retains
responsibility for quality assurance
during the modification.
No items of noncompliance or deviations were noted during the above inspection.
5 ~
Containment
(Steel Structures
and Supports)
- Review of equality Assurance
Implementing Procedures
(Units 1'and 2)
The inspector
re-examined
the
CBGI gA Manual for ASME Section III Products,
previously reviewed
and described
in inspection report 50-400,
401,
402,
403/78-04,
to verify established
quality assurance
procedures
comply with
PSAR requirements.
The review confirmed that adequate
gA plans, instructions
and procedures
for specific safety related activities have been established
in the gA manuals
and that these
documents
conform to the gA program described
in Section 1.8 of the Harris PSAR.
No items of noncompliance or deviations were identified.
6.
Licensee Identified Items
a.
Prior to this inspection,
the licensee
identified the following item
under
(Closed)
Item
(400,401/79-08-01),Westinghouse
RC
pump bolts
impact
tested
above specified
temperature.
The licensee
notified Region II
by telephone
on May 22, 1979, that the potentially reportable deficiency
had been
evaluated
and determined to be nonreportable.
The inspector
held discussions
with the site principal
(}A specialist,
reviewed the
applicable Deficiency and Disposition Report
(DDR 230),
and evaluated
the licensee's justification for nonreportability attached to memorandum
PPED-792129
dated
June
15,
1979.
The inspector
concurred with the
licensee's
determination.
b.
During this inspection the licensee reported the following as
a potentially
reportable item under
(Open)
Item (400,401/79-10-02
and 402, 403/79-09-02),
Defective class
3 component
cooling heat
exchangers.
The inspector
was
informed
on
June
13,
1979, that during field activities at the site,
access
covers
were
removed
from the subject
heat
exchangers
for units
1 and
2 and
the following discrepancies
were noted:
(1)
Wall thickness of nozzles for Units
1 and 2 is below the dimension
specified by the project drawing.
(2)
Incomplete penetration
was detected
in the Unit
1 heat exchanger
nozzle weld.
(3)
Cladding welds
on Units
1
and
2 heat exchanger
water boxes
have
porosity,
undercut,
weld splatter,
incomplete
and
arc
strikes.
-4-
The eight heat exchangers
are in storage at the site and were furnished by
in 1976.
The inspector
held discussions
with gA personnel,
examined
the components
involved,
and reviewed the data package for serial
number
This item
remains
open
pending
completion of CPL'S
evaluation..
7.
Inspection and Enforcement Bulletins
The inspector
contacted
the Nuclear Licensing Unit in Raleigh to coordinate
the following bulletins for which a response
has been received by Region II:
a.
(Open)
IEB 78-12B, "Atypical Weld Material in Reactor Pressure
Vessel
The licensee's letter of May 29,
1979
was received
and reviewed.
This
bulletin will remain open pending receipt of CPL'S supplemental
response
for vessels
3 and 4 which shall be transmitted within 30 days subsequent
to the submittal of Combustion Engineering's generic report to NRC.
b.
(Closed)
IEB 79-03, "Longitudiual Weld Defects in ASME SA-312 Type 304
Pipe
Spools
Manufactured
by Youngstown
Welding
and Engineering
Company"
The licensee's
letter of May 17,
1979 was recieved by IE:II and
CPSJ.
has determined that the subject pipe is not in use or planned for use
in safety related systems.
C.
(Closed)
IEB 79>>04, "Incorrect Weights for Swing Check Valves Manufac-
tured by Velan Engineering Corp."
The licensee's
response
of May 29,
1979 states
that there are
no Velan
swing
check
valves
planned
for use in seismic
catergory I piping
systems at SHNPP.
d.
(Open) IEB 79-07, "Seismic Stress Analysis of Safety Related Piping"
The inspector
reviewed CPM.'s response
of May 29,
1979.
This bulletin
will remain open pending completion of a technical evaluation of CPM 's
response
by the IE Headquarters staff.
e.
(Closed)
IEB 79-09 "Failures of
GE Type AK-2 Circuit Breaker in Safety
Related Systems"
The licensee's
response
of June
14,
1979 states
that there are
no
type AK-2 circuit breakers
planned for use in safety related
systems
at SHNPP.