ML17139A524
| ML17139A524 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/07/1982 |
| From: | Finkel A, Mccabe E, Narrow L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17139A522 | List: |
| References | |
| 50-387-81-26, 50-388-81-13, IEB-79-04, IEB-79-10, IEB-79-12, IEB-79-15, IEB-79-17, IEB-79-25, IEB-79-4, IEB-80-11, IEB-80-23, IEB-81-02, IEB-81-2, NUDOCS 8201250369 | |
| Download: ML17139A524 (17) | |
See also: IR 05000387/1981026
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
Region I
50-387/81-26
Report
Nos.
50-388/81-13
50-387
Docket Nos.
50-388
CPPR-101
License
Nos.
CPPR-102
Priority
B
Category
A
Licensee:
Penns
lvania Power and Li ht
Com an
2 North Ninth Street
Allentown
Penns
lvania
18101
Facility Name:
Sus
uehanna
Steam Electric Station
Units
1 and
2
Inspection At:
Allentown, Pennsylvania
and Berwick, Pennsylvania
Inspection
Conducted:
December
1,
1981
and
December
7-11,
1981
I
~Ins ectors:
84~~
L. Narrow, Reactor Inspector
(Ic 4%
date
signed
Approved By:
A.
E. Fsnkel,
eactor
Inspector
Ebe
C.
McCabe, Chief, Reactor Projects
Section
No.
2B,
DRPI
d te signed
i l~ lzz
date
signed
Ins ection
Summar
Unit No.
1
Ins ection
on December
1 and 7-11
1981
Re ort No. 50-387/81-26
Areas Ins ected:
Routine,
announced
inspection
by two region-based
inspectors
50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br />) of:
installation, modification,
and
QC of electrical
equipment;
and status of outstanding
items.
Results:
One violation was identified:
Failure to maintain control over
modification of electrical
equipment.
Unit No.
2
Ins ection
on December
1 and 7-11
1981
Re ort No. 50-388/81-13
Areas Ins ected:
Routine,
announced
inspection
(38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br />)
by two region-
based
inspector s of:
installation
and
QC of electrical
equipment;
and
status
of outstanding
items.
Results:
No violations were identified.
820l250369
820107
RDR *DOCK 05000887
RDR
J
l
sJ
DETAILS
1.
Persons
Contacted
Penns
lvania Power and Li ht
Com an
R. A. Beckley,
Resident
Nuclear
QA Engineer
~J.
R. Buczynski,
Lead Construction Surveillance
Engineer
"D. H. Cassel,
Resident
Engineer
P. Capatosto,
QA Engineer
"S. Denson,
Project Construction
Manager
- A. T. Drennon,
ISG Supervisor
F. Eisenhuth,
Senior Compliance
Engineer
- A. H. Featenby,
Assistant Project Director
J.
D. Green Operations
QA Supervisor
R.
E. Matthews,
QA Engineer
R. Prado,
Licensing Engineer
R. Prego,
QA Engineer
A.
R. Sabol,
Manager
NQA
J.
Saranga,
QA Engineer
R. J. Shovlin, Assistant, Project Director
D. J.
Thompson,
Assistant Plant Superintendent
Bechtel
Power Cor oration
Y. Ananda,
QA Engineer
"G. Bell, Lead Project
QAE
"E.
W. Figard,
ISG Supervisor
S. Guarnaccia,
Construction
Engineer
R. Holtzmon,
Lead Staff Valve Engineer
- W. Mourer, Field Construction
Manager
~J. O'ullivan, Assistant Project Field Engineer
"Present at exit meeting.
Other licensee
and contractor
personnel
were also interviewed.
Work in progress,
completed work, and plant status
in several
areas
were observed
during
a general
inspection of both units.
Work items
were examined for obvious defects
or noncompliance with NRC requirements
or licensee
commitments.
Craft and supervisory
personnel
encountered
in work areas
were interviewed.
3.
Licensee Action on Previous
Ins ection Findin
s
(Closed)
Unresolved
Items (387/79-16-01,
388/79-10-01)
(387/78-03-02)
and (387/78-03-06):
All of these
items pertain to cracks in potting
material of Westinghouse electrical penetrations
and the environmental
qualification of these
A loss of coolant accident
( LOCA) test
was performed
by the Westinghouse
Corporation at their Horseheads,
New York plant
on their electrical
The test data
has
been
supplied to the
NRC as part of
IEB 79-01B submitted.
The
NRC will address this item as part of their
overall review of electrical qualification data.
This item is considered
closed.
(Closed)
Unresolved
Item (387/79-15-05):
Lack of hardened
washers
under both the nut and b'olt head of A-490 bolts in the structural
steel
supports for the
CRD hydraulic control units.
The inspector discussed
resolution of the 'problem with the licensee
representative
and also observed
the installed bolts for this structure.
The specification permits
use of either A-490 or A-325 bolts.
After
the lack of the necessary
washers
was identified, the contractor
decided to replace
the A-490 bolts with A-325 bolts.
Inspection of
the bolts by the inspector
and the licensee did not identify any A-490
bolts in use.
This item is resolved.
(Closed)
Noncompliance
(387/79-20-01):
PGCC/ACR procurement
and
quality inspection of the supplier by the licensee.
The licensee
has
revised the quality and engineering
documentation
requiring NgA/Engineering
review and evaluation of specified documentation.
The licensee's
changes
were issued
in June of 1980.
The licensee
conducted
an audit
of the General
Electric facility in San Jose,
California during May,
1980.
The results of the audit are discussed
in
a later paragraph
of
this report identified as Item 387/79-20-02.
The inspector
reviewed the documentation
changes
and the results of
the audit findings that were conducted
by the licensee
in May, 1980.
The results of this review resolve the previously identified questions
concerning
procurement
and quality inspection of the supplier.
This items is resolved.
(Open)
Noncompliance
(387/79-20-02):
Failure to substantiate
gA
records
committed to by the Product guality Certification (PAC) for
the
ACR/PGCC equipment.
The licensee
performed
an audit of the product certification program
at the General
Electric (GE) facility San Jose,
California during
May
1980.
The licensee's
audit resulted
in one program deficiency,
seven
program implementation deficiencies,
and two recommendations.
A
response
to the licensee
audit was prepared
by General
Electric on
October 2,
1980 and is still under review by the licensee.
I
4
This item remains
unresolved
pending resolution
and acceptance
of the
audit findings by the licensee
and review by an
NRC inspector.
(Closed)
Unresolved
Item (387/79-31-05):
Damage
due to use of locking
pliars during pin pull testing.
FDI-WJGO and
FDDR KR1-548, Revision
39, required
a
100% pull test
and
visual inspection of the pin to wire and pin to connector installation
on each
reworked connector
assembly.
The inspector
randomly selected
assemblies
identifed in
NCR 5000
and determined that the work was
performed in accordance
with the requirements
of the inspection
documentation.
This item is considered
closed.
(Closed)
Unresolved
Item (387/79-40-03):
Use of plastic tie wraps
on
flexible metal conduit of the
ACR/PGCC system.
The licensee
has replaced
the plastic tie wraps with metal tie wraps
as defined in KRl-548-141 dated October 28,
1980 and verified by
quality control in QCIR NSSS-KRl-548-131-00653.
The inspector
on
a
random basis verified that the metal tie wraps
have
been
used
as
defined in the quality control documentation.
This item is considered
closed.
(Closed)
Unresolved
Item (387/81-17-02):
Training of PP5L,
E5S Construction
personnel.
The licensee
has
reviewed the individual
E and
S personnel
training
and experience files and
has given them site specific training in the
electrical
and instrumentation
requirements
area.
A refresher training
course
was also given to
E and
S personnel
at the site.
The inspector
reviewed the records of the
E and
S personnel
and discussed
the courses
and type of information that was given by the licensee
to their personnel.
This item is considered
closed.
(Closed)
Unresolved
Item (387/81-17-03):
Modifications to Instrumentation
of ACR/PGCC system turned over to the integrated startup
group (ISG).
Further inspection of modifications to turned over instrumentation
identified additional
problems in performance of the work.
The results
of that inspection
are discussed
in Paragraph
4 of this report
and
have identified an item of noncompliance.
This items is therefore
resolved.
(Open) Unresolved
Item (387/81-17-04):
Requirement for maintenance
and inspection criteria during modification and rework of equipment
under control of ISG.
The licensee
is presently
reviewing their present
documentation
to
assure
that the necessary criteria have
been developed.
The inspector
informed the licensee that the requirements
of IEB 79-
01B attachment
No.
4 page
14 and
15 are to be considered
when preparing
the procedures
associated
with the maintenance
program for the nuclear
site.
This item remains
unresolved
pending completion of the licensee's
review and review of the results
by an
NRC inspector.
(Closed)
Unresolved
Item (388/81-04-06):
Evaluation of turned over
equipment for'conditions adverse
to quality.
This item was inspected
and closed
by the
NRC inspector during inspection
387/81-25.
4.
De radin
of Electrical
and Instrumentation
E ui ment Under Control of
the Inte rated Startu
Grou
During
a previous inspection
(387/81-17)
the inspector
had observed
that work performance
and cleanliness
during modification of electrical
and instrumentation
equipment
under control of the
ISG was inadequate
and could potentially degrade
the equipment.
The inspector
examined
the condition of equipment in several
areas:
In the
Lower Relay
Room the inspector
found that the dust plugs
were missing from the male
and female connector in the equipment
racks.
Panel
equipment
removed from the panels
were not plugged
with dummy panel dust plugs
and connector
dummy wire dust plugs,
were
mi ssing
from the cable connectors.
Dirt was found
on the
outside of the cabinets
as well as inside the equipment.
The inspector
found the
same condition when the Automatic Depressurization
System
(ADS) was inspected.
The protective dust plug connector
s
were not on the male connector
plugs of the Crosby Solenoid Yalve
boxes.
The use of connector dust caps,
connector dust plugs,
and
dummy panel
plugs are methods
used to comply with installation
and manufacturing
drawing requirement for maintaining the hardware
in a clean condition.
management
control of modification and re-work of Safety-related
requipment that is under the control of the Integrated Startup
Group
(ISG) is not being maintained in accordance
with the installation
and
vendor drawing requirment.
The inspector
informed the licensee that this was
an item of noncompliance
and
a violation of 10 CFR 50, Appendix B, Criterion
1 which states,
in
part, that:
"the quality assurance
functions are those of (a) assuring
that an appropriate quality assurance
program is established
and
effectively executed.
. ."
(387/81-26-01)
5
~
Licensee Action on
NRC Bulletins and Circulars
a.
The following Bulletins were closed:
Bu. 79-25:
Failure of Westinghouse
BDF Relays in Safety
Related
Systems.
This item had previously been resolved for Unit 1.
The licensee
has
now completed inspection of Unit
2 relays
and determined that there were
no relay's
of the type identified in the Bulletin.
This item is resolved.
Bu. 80-11:
Masonry Wall Design
The inspector discussed
the licensee's
masonry
wall reevaluation
program with the licensee
and
with field engineerng
and construction
personnel
responsible
for review of attachments,
preparation
of as-built drawing
and review of wall loadings.
The inspector also
examined applicable
procedures
and selected
drawings;
and inspected
selected
masonry walls in the reactor building and control
building to determine that attachments
and loading
conditions confirmed to the drawings.
No nonconforming
conditions were identified.
This item is resolved.
Bu. 80-23:
Failure of Solenoid Valves Manufactured
by Valcor
Engineering Corporation.
Bu. 81-02:
Failure of Gate
Type Valves to Close Against
Differential Pressure
(Also Supplement
1).
The inspector discussed
the items identified in the above
two
Bulletins with licensee
representatives
and reviewed computer
printouts of equipment onsite to confirm that
none of the identified
valves
had
been
supplied to the site.
b.
The following Bulletins are closed for Unit 2 based
on review by
an
NRC inspector
during inspections
of Unit
1 as
shown below:
Bu. 79-04:
Incorrect Weights for Swing Check Valves Manufactured
by Yelon Engineering
Company-Closed
Inspection
Report (IR) 387/81-15.
Bu. 79-10:
Requalification Training Program Statistic-Closed
IR 387/81-02.
BU. 79-12:
Sort Period
Scrams at
BWR Facilities-Closed
IR
387/81-25.
Bu. 79-15:
Bu. 79-17:
Deep Draft Pump Deficiency-Closed
IR 387/81-25.
Pipe Cracks in Stagnant
Water Systems
at
Plants-Closed
IR 387/81-02.
The following circulars
have
been closed:
Ci. 78-06:
Potential
Common
Mode Flooding of ECCS Equipment
Rooms at
BWR Facilities.
Procedure
OP-69-004,
Rev.
C which is complete
and awaiting
review provides for control of water tight doors
and operation of
normally closed
plug valves in the drain lines.
Ci. 81-01:
Design
Problems Involving Indicating Pushbuttons
Manufactured
by Honeywell Incorporated.
Ci. 81-06:
Potential
Deficiency Affecting Certain
10
and
50 Hilliampere Transmitters.
The licensee
has determined that
none of the equipment identified
on the above
two circulars is on site
and it has
been identified
on the "Defective Device" list so as to prevent its being ordered
in the future.
Ci. 81-08:
Foundation Materials
A settlement
monitoring program is in effect for the
Pump
house.
The remaining Seismic
Category
I structures
are directly
supported
on bedrock.
Measured
settlement of the
pump house
is well within the projected
values
as established
in the
FSAR.
The following circulars are closed for Unit 2 based
on re0iew by
an
NRC inspector of Unit
1 as
shown below:
Ci. 77-12:
Dropped
Fuel Assemblies at
BWR Facilities-Closed
387/81-25.
Ci. 77-15:
Degradation of Fuel Oil Flow to the Emergency
Diesel Generator-Closed
IR 387/81-25.
Ci. 78-13:
Inoperability of Nultiple Service Water Pumps-
Closed 387/81-25.
Ci. 79-11:
Design/Construction
Interface
Problem-Closed
IR 387/80-32.
Ci. 79-12:
Potential
Diesel Generator
Turbogenerator
Problem-
Closed 387/80-24.
Ci. 79-13:
Replacement
of Diesel Fire
Pump Starting Contractors-
Closed
IR 387/81-25.
Ci. 79-18:
Proper'Installation
of Target
Rock Safety-Relief
Valves-Closed
IR 387/81-02.
Ci. 79-22:
Stroke
Times for Power Operated Relief Valves-
Closed
IR 387/81-02.
Ci. 79-24:
Proper Installation
and Calibration of Core Spray
Pipe Break Detection
Equipment
on BMRs-Closed
IR
387/81-25.
Ci. 79-25:
Ci. 80-07:
Shock Arrestor Strut Assembly Interface-Closed
IR 387/81-25.
Problems with HPCI Turbine Oil System-Closed
IR 387/81-02.
Ci. 80-15:
Loss of Reactor Coolant
Pump Cooling and Natural
Circulation Cooldown-Closed
IR 387/80-16
6.
Review of Nonroutine Events Identified b
the Licensee
The inspector
reviewed the status
of items which had been identified
by the licensee
as potentially reportable.
All items found to be
complete
were closed
as
shown below.
The remaining
items were either
obviously not complete
and were not reviewed by the inspector or in
some cases
were considered
by the licensee
as complete
and were reviewed
by the inspector but found to be not ready to close.
The latter items
are also
shown below.
Completed
Items
(Closed) Potential
Construction Deficiency (381/80-00-09
and
388/80-00-09)
also reported
under
10 CFR 20 (80-SC-03).
Leak
through bolt hole in Jamesbury butterfly valve.
Licensee later
notified NRC that fur ther evaluation
showed that item was not
reportable
under
The status of this item was reviewed during inspection
387/81-17,
388/81-09 but remained
unresolved.
The inspector
reviewed documentation
onsite.
NCR No.
5836
has
been closed
and accepted
by gC.
Valve
No. 2-11-126B
has
been
removed
and returned to the vendor.
Record of this valve is maintained
in IR 54.0-14204-HRC-2231-1
which remains
open.
This item is resolved.
(Closed) Construction Deficiency (387/81-00-02;
388/81-00-02)
Overstressing
of diesel
generator
exhaust line.
The D-6 exhaust
line has
been revised to add
a third expansion joint to absorb
excessive
thermal
movement.
The inspector
examined
Design
Change
Package
(DCP) No.
233 and Start
up work Request
(SWR) No.
2131
for performance
of this work.
The work was complete
June 8,
1981.
In addition Table 3.2-1 of the
FSAR had been revised to
incorporate
ASME Code
Case
1481-1 (N-19).
This item is resolved.
(Closed) Construction Deficiency (387/81-00-05):
Mislocation of
fuel Support Castings.
Review of documentation
had revealed
a possible
discrepancy
in
the location of four fuel support casting
groups.
This was
documented
on
GE IPSE Nonconformity Report
(NR) 17.5. 140.
Location
of these
castings
were physically checked.
They were" found to
have
been mislocated
and were re-arranged
in the proper location.
In addition,
the locations of the remaining peripheral
castings
were checked.
They were found to be properly located.
The
inspector
examined
NR 17.5. 140 and Supplier Deviation Disposition
Report
(SDDR) No.
115 which covered corrective
action.
This item is resolved.
(Closed) Potential
Construction Deficiency (387/81-00-11,
388/81-
00-11):
Failure of design to maintain control
room habitability.
Further evaluation
determined that this deficiency was not reportable.
The design of the control
room and central, structure
was revised
from a dual pressure
envelope to a single pressure
envelope for
the control structure.
With this design the reported
excessive
from the duct system
has
no significance.
The design
change is
described
in Section 6.4.2 of the
FSAR (Rev. 26).
This item is resolved.
(Closed) Potential
Construction Deficiency (387/81-00-18;
388/81-
00-18):
Improper crimping of CRD terminations.
After further
evaluation
the licensee notified
NRC that this items was not
reportable
under
10
The inspector
examined
NCR No.
7612 which was dispositioned to
rework the deficient terminations
and which was completed
and
accepted
September
9,
1981..
This item is resolved.
b.
Incomplete
Items
(Open)
10 CFR 21 Report (80-SC-04):
Malfunction of Comsip containment
gas analyses
equipment.
The inspector
reviewed documentation
showing that rather than
upgrade existing equipment,
the licensee
had returned
the panels
to the vendor
and obtained
new panels,
which were being installed
During examination of gA documentation,
the inspector
noted that
a question
had been raised
by the licensee
concerning
environmental
qualification of the
new panels.
This item remains
unresolved
pending acceptance
of the environmental
qualification of the equipment
by the licensee
and its review by
an
NRC inspector.
(Open) Construction Deficiency (387/80-00-03;
388/80-00-03):
Disc/body interference of Pacific Valves, Inc.
Swing Check Valves
which prevent closure of the valves.
The inspector discussed
this problem with the licensee
representatives
and reviewed documenation
concerning investigation of the problem
and corrective actions taken.
In all sixteen valves (12-inch and
20-inch) were examined, all having
a external
lever arm and
referred to as "testable" valves.
One valve was incorrectly
assembled
and
had been
re-assembled
correctly; several
valves
were found to have interference
problems
and were reworked;
and
the packing
on all valves
was replaced
in order to reduce friction.
The inspector determined that four additional
12-inch and 20-inch
swing check valves
from the
same
vendor are installed onsite.
They have
simi liar body and disc assembly
configurations but
without the external
lever arm.
They have not been
examined or
tested to determine whether they have
simi liar interferences.
This item remains
unresolved
pending examination or other determination
by the licensee that the remaining four valves are free of
body/disc
assembly
interference.
(Open) Construction Deficiency (387/80-00-10;
388/80-00-10):
Embedment of Hilti shell
type expansion
achors.
11.
The inspector discussed
the status of inspection
and replacement
of these
anchors
and reviewed the applicable specification, field
procedure
and
QC instruction for this work.
The inspector also
reviewed selected
documents
recording the results of re-inspection,
evaluation
and repair/rework
as well as the field engineering
log
documenting
the status of the work.
The inspector
then observed
the status of the work in selected
rooms which were complete
as
well as
rooms in which the, work was still incomplete.
Identification
of the status of individual anchors
by tagging or paint marks
was
also
examined.
In Unit 1, of a total of 280 rooms:
All rooms
had
been examined/tested
by field engineering
and
the results
documented for evaluation,
57 rooms
had
no "Q" listed anchors,
and
24 rooms
had
been evaluated,
repair/rework completed
and
inspected
by QC.
This item remains
unresolved for Unit
1 pending completion of
evaluation,
repair/rework
and
QC inspection of a larger percentage
of the rooms.
In Unit 2, examination/test
by field engineering
had not been
completed for any rooms
and this item remains
unresolved.
(Open) Construction Deficiency (387/80-00-26;
388/80-00-26):
Deficiency in shimming of base plates;
including use of pipe
welding of leveling nuts inside the pipe shims
and welding
of pipe
shims to anchor bolts.
Re-insp'ection,
evaluation
and corrective actions for this deficiency
are conducted
under the
same
program
as described
above for item
80-00-10.
The status of this program was reviewed
by the inspector.
This items remains
open pending completion of additional
work by
the licensee
and its review by an
NRC inspector.
(Open) Potential
Construction Deficiency (387/81-00-01;
388/81-
00-01):
Excessive
wear of the hing arm/disc
stud interface of
Pacific Valve, Inc.
swing check valves.
This problem was identified
on 6-inch, 8-inch and 10-inch valves
and the excessive
wear with
consequent
jamming of the valve discs
and their failure to seat
properly was noted
on valves of a non-"Q" system.
After furter inspection
and evaluation of "Q"-listed valves the
licensee notified
NRC that this item was not considered
to be
reportable
since
no evidence of excessive
wear
had
been identified.
0
12
The licensee
also stated that an inspection of"g"-listed check
valves will be
made after fuel load in order to. identify and
correct wear
problems if they develop in the future.
During discussions
with the licensee
and review of documentation
the licensee
determined that the non-"g" valves which had
shown
evidence of excessive
wear
had been
in service for approximately
3 months.
Twelve "g" listed valves
had been
inspected for wear.
Of these,
4 valves
had
seen
service of one week or less
and 8
valves
had
been in service
between
one to four weeks.
This item remains
unresolved
pending inspection of "g"-listed
valves following fuel load and review of the results
by an
NRC
inspectors
7.
Exit Interview
The inspector
met with licensee
representatives
(see Details
Paragraph
1) at the
end of the inspection
on December
11,
1981.
The
NRC Resident
Inspectors
also attended
the meeting.
The inspector
summarized
the
purpose
and
scope of the inspection
and identified the inspection
findings.
f
~
4
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