ML20133E925
| ML20133E925 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 07/11/1985 |
| From: | Dance H, Skinner P, Van Doorn P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20133E873 | List: |
| References | |
| 50-413-85-20, 50-414-85-16, IEIN-85-15, NUDOCS 8508080066 | |
| Download: ML20133E925 (9) | |
See also: IR 05000413/1985020
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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REGION 11
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101 MARIETTA STREET.N.W.
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ATLANTA. GEORGI A 30323
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Report Nos.:
50-413/85-20 and 50-414/85-16
Licensee:
Duke Power Company
422 South Church Street
Charlotte, NC 28242
Docket Nos.:
50-413 and 50-414
License Nos.:
NPF-35 and CPPR-117
Facility Name:
Catawba 1 and 2
Inspection Conducted:
'l 26 - May 25, 1985
Inspectors:
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P. H. ' 5kfhner - ~
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Date Si(gned
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P. K. Tali Doorn' [
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Drte Signed
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Approved by:
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H. C. Dan'ce, Section Chief
Ddte ' Signed
Division of Reactor Projects
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SUMMARY
Scope: This routine, unannounced inspection entailed 210 inspector-hours on site
in the areas of site tours (Units 1 and 2); followup of licensee and NRC
identified items (Units 1 and 2); review of nonconforrping item documentation
(Unit 2); followup of IE Information Notices (Units 1 and 2); Instrumentation
(components and systems) - observation of work (Units 1 and 2); comparison of
as-built plant to FSAR description (Unit 2); maintenance observations (Unit 1);
surveillance observations (Unit 1); review of non-routine event reports (Unit 1);
and plant operations review (Unit 1).
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Results:
Of the 10 areas inspected, no violations or deviations' were identified
in 8 areas; one apparent violation was found in one area - (Failure to maintain
cleanliness control in the diesel generator room
paragraph 5.c.), and one
apparent deviation was found in one area (Failure to meet commitment to remove
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teflon tape
paragraph 3.d.).
85080B0066 850712
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DR
ADOCK 05000413
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REPORT DETAILS
1.
Persons Contacted
Licensee Employees
J. W. Hampton, Station Manager
E. M. Couch, Project Manager
- B. F. Caldwell, Station Services Superintendent
W. M. Carwile, Test Director
- J. W. Cox, Superintendent, Techncial Services
T. E. Crawford, Operations Engineer
L. R. Davison, Project QA Manager
- C. W. Graves, Jr., Superintendent, Operations
- C. L. Hartzell, Licensing and Projects Engineer
R. D. Hellams, Engineer-Turnover
- C. S. Kelly, Instrumentation / Electrical Technial Support
- R. A. Jones, Test Engineer
J.'A. Kammer, Test Director
- P. G. Leroy, Licensing Engineer
- T. D. Mills, Construction Engineer Electrical
- E. B. Miller, QA Engineer
C. E. Muse; Operating Engineer
- G. T. Smith, Superintendent, Maintenance
D.' Tower, Operations Engineer
Other licensee employees contacted included construction craftsmen,
technicians, operators, mechanics, security force members, and office
personnel.
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on May 24, 1985, with
.those persons indicated in paragraph 1 above.
The violation, deviation, and
unresolved items described in paragraphs 3.d. , 5.c. , 5.d. , and 8.b were
discussed in detail.
The licensee acknowledged the findings and had no
dissenting comments.
The licensee did not identify as proprietary any of the materials provided
to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters
a.
(0 pen) Unresolved Item 413/84-87-03:
Review of Operations Corrective
Action Program.
The inspector met with the NCI/Non-Routine Event Task
Force Director and the Catawba Compliance Engineer to be updated on the
licensee efforts to address this item.
A problem Investigation Report
System has been proposed and has been forwarded to appropriate licensee
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personnel for comment.
The inspector reviewed the proposed Station
Directives and PIR Flow Charts and considers the licensee to be making
satisfactory progress relative to this item.
This item remains open
pending further review and implementation of the improved program.
b.
(Closed) Violation 413/84-106-03:
Failure to meet Technical Speci-
fication (TS) Requirements for Ice Condenser Doors Prior to Changing
Modes.
The response for this item was submitted on March 29, 1985.
The inspector reviewed and verified implementation of corrective
actions described in the response and considers licensee actions to be
acceptable,
c.
(Closed) Violation 413/84-106-04:
Failure to Meet Procedure Require-
ments For Verification of Operability of the Ice Condenser.
The
response for this item was submitted on March 29, 1985.
The inspector
reviewed and verified implementation of corrective actions described in
the response and considers licensee actions to be acceptable.
d.
(0 pen) Violation 413/84-104-01:
Failure to Control Use of Teflon Tape.
The response for this item was submitted on January 24, 1985 and
March 14, 1985.
In the response dated January 24, under Response to
Part (B) item 5, Duke Power Company states in part that the tape
installed by Nuclear Production in the Auxiliary Building will be
removed by March 1,1985.
The inspector toured the Auxiliary Building
on May 7 and noted several examples where teflon tape was still
installed on system components which could possibly come in contact
with reactor coolant.
This is a deviation 413/85-20-02:
Failure to
Meet Commitment to Remove Teflon Tape.
4.
Unresolved Items
New unresolved items are identified in paragraphs 5.d. and 8.b.
5.
Independent Inspection Effort (92706) (71302) (Units 1 and 2)
a.
The inspectors conducted tours of various plant areas.
During these
tours, various plant conditions and activities were observed to
determine that they were being performed in accordance with applicable
requirements and procedures.
No significant problems were identified
during these tours and the various evolutions observed were being
performed in accordance with applicable procedures.
During Unit 2 site tours, the inspector cbserved protection / storage of
plant equipment such as electrical cables, electrical components,
reactor vessel,
reactor vessel
internals, and safety-related
components,
b.
The inspector reviewed Nonconforming Item Reports (NCIs) and corrective
action evaluations (R6As) to determine if appropriate documentation and
evaluations were being made.
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c.
During a tour of the diesel generator room 1B on May 9,1985, the
inspector noted that the . room was not being maintained in the
cleanliness condition specified by Station Directive 3.11.1, House-
keeping and Cleanliness Levels In Safety Related Areas, Revision 9.
This cleanliness condition is specified as a Level IV area which
specifies all dirt and debris will be removed from the area.
At the
time of the tour, this room had open buckets of oil, oily rags and
material, a portable filter assembly which had leaked onto the floor
and other accumulation of material that was not appropriate to this
area.
This accumulation of material and debris in addition to being a
cleanliness problem, was also a fire hazard.
The shift supervisor was
notified of this problem and took prompt action to reestablish
cleanliness requirements.
This finding is a Violation 413/84-20-03:
Failure to maintain cleanliness control in the diesel generator room.
d.
During the period of May 9,1985 to May 15,1985, Catawba experienced
nine actuations of Engir.eered Safety Features (ESF) systems or portions
thereof.
Four of these actuations were associated with steam generator
low low level circuitry and five were associated with low low level
circuitry of the Nuclear Service Water System (RN).
Preliminary
investigation by the inspector indicates that several of these
actuations were due to improper planning and communication.
This item
will be identified as Unresolved Item 413/85-20-04:
Multiple
Inadvertant Actuation of . ESF, pending additional review by the
inspector of these incidents and review of investigations conducted by
plant personnel.
No violations or deviations were identified.
6.
Licensee Identified Items 50.55(e) (99020) (Units 1 and 2)
a.
(Closed) CDR 414/84-05:
Damaged Diesel Generator Oil Seals and Turbo
Charger Thrust Bearings.
Reports for this item were submitted on
April 26,1984 and July 5, 1984.
The inspector reviewed these reports
and verified implementation of corrective actions identified in the
reports and considers licensee actions to be acceptable.
b.
(Closed) CDR 413, 414/84-08:
No Circuit Protection Provided for Two DC
Welding Circuits.
Reports for this item were submitted on May 10, 1984
and March 1, 1985.
The inspector reviewed these reports and verified
implementation of corrective actions identified in the reports and
considers licensee actions to be acceptable.
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(Closed) CDR 414/84-10:
Rotork Actuators Fitted with Undersized Set
Screws.
Reports for this item were submitted on May 16, 1984;
August 30, 1984; February 1,1985 and April 1,1985.
The inspector
reviewed these reports and verified implementation of corrective
actions identified in the reports and considers licensee actions to be
acceptable.
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d.
(0 pen) CDR 414/85-02:
Vendor Weld on SI Accumulator Tank-Rejectable
Radiographic Indications.
The inspector observed repair welding of the
shell to upper head weld of Accumulator 20.
Control of Welding and
non-destructive examination appeared to be adequate.
This item remains
open pending completion of repair welding and radiography.
e.
(Closed) CDR 414/85-04:
Stainless Steel Valves Welded with Carbon
Steel Filler Material.
The report for this item was submitted on
April 19, 1985. The inspector reviewed this report and verified imple-
mentation of corrective actions identified in the report and considers
licensee actions to be acceptable.
f.
(0 pen) CDR 414/85-06:
Overpressurization and Rupture of Volume Control
Tank During Cold Hydrostatic Testing.
The inspector observed welding
in progress of the new Volume Control Tank being accompished by the
vendor (RECO).
This including review of welding procedures, review of
licensee surveillance of the vendor and visual inspection of fitup and
selected welds.
This item remains open pending completion of the
repair work and completion of further evaluations being conducted by
the licensee.
No violations or deviations were identified.
7.
Followup of IE Information Notices (92717) (Units 1 and 2)
The inspector verified that the licensee had reviewed and taken appropriate
corrective actions relative to Information Notice 85-15:
Nonconforming
Structural Steel for Safety,-Related Use.
The licensee evaluated the one
shipment received from the vendor to be acceptable for its use in the Unit 2
Turbine Building.
No violations or deviations were identified.
8.
Instrumentation (Components and Systems) - Observation of Work and Work
Activities (52153) (Units 1 and 2)
a.
Requirements for installation of instrumentation are contained in
various licensee specifications and site procedures.
The inspector
observed installed instrumentation for conformance to requirements in
the areas of location, conformance to installation procedure require-
ments, use of specified materials and components, mounting of
instruments,
routing of tubing,
tubing supports, inspection,
separation, physical protection and record keeping.
The inspector also
reviewed instrumentation Departmental Audit No. CD-84-16 dated
December 28, 1984.
The instrument loops observed were process control
loops 2KC PG 7980 (Component Cooling Pump Motc r Cooler) and 2CAPG5020
(Auxiliary Feedwater Pump A Suction Pressure); ESF loops 2NSPT 5040 and
2NSPT 5380 (Contaiment Pressure); and safety-related display and safe
shutdown loops 2FWLT5120 (Refueling Water Storage Tank Level) and 2NILT
5260 (Containment Sump Level).
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b.
During. this review, . questions arose which were unable to be fully
addressed prior to the 'end of the inspection period.
These questions
-inv'olve loop 2FWLT5120 and involve additional verification required of
the inspector and evaluations required by the licensee.
These
-questions are as follows:
(1) Verification that insulators and heat tracing personnel are
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adequately trained to prevent damage to safety-related instrument
tubing.
This verification is required since this work is
conducted after. construction inspections are complete.
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(2) ~ Verification that insulation does not prevent expansion loops from
functioning properly.
-(3) Verification that instruments mounted in electrical boxes are
seismically mounted and properly inspected. There appeared to be
some confusion as to. inspection requirements for mounting of these
types of instruments.
(4): During review of the inspectors questions the licensee noted that
.a change to the instrument inspection instruction (M610) had
inadvertantly deleted inspection of mounting.
The licensee
indicated that a preliminary evaluation indicated that mounting
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had been inspected anyway.
This must be verified and the
instruction must be corrected.
(5) Loop 2FWLT5120 does not appear to-meet minimum slope criteria at-
the expansion loop.
Inspection of similar loops in Unit 1
disclosed possible slope violations in loops 1FWLT 5000, 5010 and
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5120.
The licensee was requested to evaluate this problem as to
significance and cause.
(6) During inspection of Unit 1 loops it was noted that heat traced
loop 1FWLT5000 was not insulated.
The licensee was requested to
evaluate this condition.
These questions are assigned Unresolved Item No. 413/85-20-01,
414/85-16-01:
Verification of Adequate Installation of Instrumen-
'tation.
No violations or deviations were identified.
9.
-Comparison of As-Built Plant to FSAR Description (37301) (Unit 2)
-The inspector verified that control and logic instrumentation met the FSAR
. description for Train A of the Residual Heat Removal System.
No violations or deviations were identified.
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10.
Maintenance Observations (62703) (Unit 1)
Station maintenance activities of selected systems and components were
observed / reviewed to ascertain that they were conducted in accordance with
the requirements.
The inspectcr verified licensee conformance to the
requirements in the following areas of inspection:
(1) that the activities
were accomplished using approved procedures, and functional testing and/or
calibrations were performed prior to returning components or systems to
service; (2) quality control records were maintained; (3) that the
activities performed were accomplished by qualified personnel; and (4) parts
and materials used were properly certified. Work requests were reviewed to
determine status of outstanding jobs and to assure that priority is assigned
to safety-related equipment maintenance which may affect system performance.
Examples of this observation was work performed to correct seat leakage of
valves 1XC 50A, 1KC 53, and 1KC 995.
No violations or deviations were identified.
11.
Surveillance Observations (61726) (Unit 1)
During the inspection period, the inspector verified plant operations were
in compliance with various TS requirements.
Typical of these requirements
were confirmation of compliance with the TS for reactor coolant chemistry,
refueling water tank, residual heat removal, control room ventilation, and
DC electrical power sources.
The inspector verified that surveillance
testing was performed in accordance with approved written procedures, test
instrumentation was calibrated, limiting conditions for operation were met,
appropriate removal and restoration of the affected equipment was
accomplished, test results met requirements and were reviewed by personnel
other than the individual directing the test, and that any deficiencies
identified during the testing were properly reviewed and resolved by
appropriate management personnel.
Typical of the surveillance items that were witnessed in part or in full
were weighing of high pressure carbon dioxide cylinders,125 VOC Essential
Diesel Auxiliary Power System Battery Service Test, and various calibrations
of portions of the nuclear instrumentation and radiation monitoring systems.
No violations or deviations were identified.
12.
Review of Licensee Nonroutine Event Reports (92700) (Unit 1)
The below listed Licensee Event Reports (LERs) were reviewed to determine if
the information provided met NRC requirements.
The determination included:
adequacy of description, verification of compliance with TS and regulatory
requirements, corrective action taken, existence of potential generic
problems, reporting requirements satisfied, and the relative safety signifi-
cance of each event.
Additional inplant reviews and discussion with plant
personnel, as appropriate, were conducted for those reports indicated by an
asterisk (*).
The following LER's are closed:
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84-22*
11/15/84
Inoperable Emergency Core Cooling
Flowpath
84-23*
11/19/84
ESF Actuation-Auxiliary Feedwater
Pump Start Due To Trip Of Main
Feedwater Pump
84-24*
11/24/84
Low-Low Steam Generator 1C Level
Actuation Of Motor Driven Auxiliary
Feedwater Pumps
84-25*
11/27/84
Auto Start Of Auxiliary Feedwater
Pumps On A Trip of Main Feedwater
Pumps
84-26
11/27/84
Required ~ Fire Watches Not Performed
84-28
12/5/84
ESF Acutation Due To Blackout on
Essential Switchgear
84-29*
12/6/84
Potential Loosening Of Control Rod
Drive Mechanism Set Screws
84-30
11/29/84
Containment Penetration Leak Rate
Test Improperly Performed
85-02*
12/31/84
Ice Condenser Lower Inlet Doors
Blocked Open
85-04*
1/14/85
Manual Trip Of Reactor Following
Loss Of Cooling Water To Reactor
Coolant Pumps Motors
85-06
1/20/85
Inadvertant Cooldown During Natural
Circulation Test
85-10
2/1/85
Power Range Instrumentation Neutron
Flux - High Negative Rate Trip
85-12
2/9/85
Safety Injection Caused By A Static
Inverter Failure
85-16
3/2/85
Incorrect Calibration Of Power Range
Trip Setpoints
85-20
3/14/85
Reactor Trip Caused By A Loose Power
Range Detector Cable
85-21*
3/13/85
Inoperable Turbine Driven Auxiliary
Feedwater Pump
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85-23
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Seventy-five Percent Power Exceeded
During Testing Prior To Authori-
zation
No violations or deviations were identified.
13.
Plant Operations Review (Unit 1) (71707 and 71710)
The inspectors reviewed plant operations throughout the reporting p ariod to
veri fy conformance with regulatory requirements, TS and administrative
controls.
Control room logs, danger tag log, TS Action Item Log, and the
removal and restoration log were routinely reviewed.
Shift turnovers were
observed to verify that they were conducted in accordance with approved
procedures.
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The inspectors also verified by observation and interviews, that measures
taken to assure the physical protection of the facility met current
requirements.
Areas inspected included the security organization, the
establishment and maintenance of gates, doors, and isolation zones in the
proper condition, that access control and badging were proper, and
procedures followed.
In addition to the areas discussed above, the areas toured were observed for
fire prevention and protection activities.
These included such things as
combustible material control, fire protection systems and materials, arid
fire protection associated with maintenance and construction activities.
During this inspection period the inspector reviewed the Auxiliary Shutdown
Panels instrumentation and controls againsy the controls listed in FSAR
Tables
7.4.7-1,
7.4.7-2,
aqd 7.4. 7-3.
A gcomparison of the listed
instruments actually installed on these panels shows that there are several
instruments and controls that do not agree with the instruments identified
in these tables.
This was discussed with the licensee.
The licensee
provided the inspector a proposed change in the FSAR (Revision 12) which
identifies some of the differences but this proposed change does not
identify all the differences.
The licensee has stated that another revision
is being developed for submittal to the NRC for approval prior to fuel load
on Unit 2.
Based on this discussion, this item is identified as an
Inspector Follow-up Item 413/85-20-05:
Correction of FSAR Tables 7.4.7-1,
7.4.7-2, and 7.4.7-3.
No additional violations or deviations were identified.
14.
Previously Identified Inspector Findings (92701) (Unit 1)
(Closed) Inspector Followup Item 413/84-79-02:
Completion of Core Damage
Mitigation Training.
The licensee committed to completion of core damage
mitigation training for applicable personnel by completion of full power
testing.
The inspector reviewed the training and selected training records
of various personnel.
Based on this review this item is closed.
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