ML20137G642
| ML20137G642 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 01/09/1986 |
| From: | Jaudon J, Mcneill W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20137G612 | List: |
| References | |
| 50-298-85-32, NUDOCS 8601210128 | |
| Download: ML20137G642 (4) | |
See also: IR 05000298/1985032
Text
._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _
'
.
APPENDIX B
U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-298/85-32
License:
Docket:
50-298
Licensee:
Nebraska Public Power District
P. O. Box 499
Columbus, Nebraska 68601
Facility Name:
Cooper Nuclear Station (CNS)
Inspection At:
CNS Site, Brownville, Nebraska
Inspection Conducted:
December 2-6, 1985
I- 9-N
Inspector:
.
W. M. McNeill, Project Engin'eer, Project
Date
Section A, Reactor Projects Branch
!
l
l
Approved:
_
//s/
d/l
/f [d
l
P./Jaud
, Cfiief, Project S'ection A
Date'
{
'
eacthr P ojects Branch
i
l
Inspection Summary
Inspectinn Conducted December 2-6, 1985 (Report 50-298/85-32)
Areas Inspected:
Routine, announced inspection of the calib,ation program.
The inspection involved 36 inspector-hours onsite by one NRC inspector.
Results: Within the area inspected, one violation was identified (failure of
procedures to address certain gauges).
I
8
12101288iggg
-
aoocx O
!
,
7-
_
.
-2-
' DETAILS
1.
Persons Contacted
R. Brungardt, Operations Manager
J. M. Clark, Mechanic
L. P. Clark, Electrical Supervisor
R. C. Deatz, Engineering Specialist
- J. R. Flaherty, Assistant Plant Engineering Supervisor
M. E..Halkins, Instrument and Control Supervisor
- H. A. Jantzen, Instrument and Control Foreman
- J. M. Meacham, Technical Manager
- D. M. Norvell, Maintenance Manager
p
,
L
-
- G. Sayer, Technical Staff Manager
- G. Smith, Senior QA Specialist
P. V. Thomason, Nuclear Operations Division Manager
The NRC inspector also interviewed other plant and general office
personnel, including engineering, administrative, and cle,'ical.
- Denotes presence at exit interview.
L2.
Surveillance Testing and Calibration Control Program
_
The objectives of this inspection were to ascertain whether the licensee
had developed programs for control and evaluation of surveitlance testing,
calibration, and _ inspection required by the Technical Specifications and
inservice inspection [ testing of pumps and valves as required by
10 CFR 50.55a(g)]. Also, the objectives were to ascertain the calibration
of' safety-related instrumentation not specifically controlled by Technical
Specifications.
In this regard, the USAR, Technical Specifications,
Quality Assurance Program for Operation Policy Document, Revision 2,
dated April 29, 1985, and the fcllowing procedures were reviewed:
.
Procedure' =
Rev.
Number-
Title
No. Date
.QAP-400
Instrument and Equipment Calibration ~ and Control
9
8-30-85
SP-6.0.1-- Surveillance Program
2
10-17-85
MP-7.0'2 Work' Item Tracking-Preventative Maintenance
0
9-27-85
.
_
,
.
MP-7.1.1 Mechanical Gauging Equipment Control
1
1-7-85
'
~&_ Calibration
s
y
'
MP-7.1.2 Test Equipment Calibration
7
9-26-84
,
m
,
'
.
-3-
It was found by the NRC inspector that a program was established which
addressed the identification of equipment, calibration frequency,
standards to be used, traceability to the National bureau of Standards,
calibration procedures, stickers identifying status and records to be
maintained. The program provides for evaluation of previous testing when
equipment is foundiout of calibration.
The preventative maintenance
program is used.to recall equipment from . service for calibration and .
identifies the procedures to be used for calibration. Surveillance
testing, inservice inspection and other safety-related testing require use
of calibrated equipment and documentation of the specific equipment which
has been used. These activities are controlled with a master schedule
based on Technical Specifications requirements.
The NRC inspector sampled recent surveillance activities. Ten recent
surveillances were reviewed in detail; in particular, the calibration of
the equipment and the calibration standards used for calibration were
examined. The scope of this sample included pressure gauges,
counter-timers, digital voltmeters, vibration meters, timers and dead
weight testers. The equipment's, calibration procedures, calibration
records and vendor certifications of calibration were reviewed.
It was observed that a series of six pressure gauges (serialized LLRT-2
through 7) are used for local leak rate testing.
Because of the lack of
procedure requirements the following was found:
LLRT-6 had a check
performed on July 8, 1985, which noted that at 100 psi this gauge read
94.6 psi.
If the manufacturer's reported accuracy (.5% of full scale
which is 100 psi) is used as a tolerance then this check is unacceptable.
Surveillance testing reports document that this gauge had been used on
July 12, 17, and 18 and again on August 2, 3, 8, 9, and 18.
This testing
was at 58 psi and the gauge was within tolerance at the 50 and 75 psi
check points on July 8, 1985. Subsequently, this gauge was reportedly
dropped and readjusted on October 22, 1985.
It is implied that the LLRT-series of gauges are to be calibrated prior
to use but there is no definition of how soon prior to use. This series
of gauges was found to have been calibrated from as little as 2 days prior
to use to as much as 74 days prior to use. The LLRT-series of gauges
has been calibrated with several different standards (dead weight testers
and pressure gauges) which have had an accuracy of .25% to .03%.
All
standards were greater than accuracy of the LLRT-series gauges.
The lack of procedural requirements in regard to tolerance, frequency,
standards, and documentation was identified as an apparent violation
(50-298/8532-01). A procedure change is underway to correct the above
prchlem.
Changes to the applicable procedure Nos. MP-7.5.4.2 and
SP-6.3.1.1 are going to address a tolerance, frequency, standards, and
documentation requirements for the LLRT-series of gauges.
-
-
- -
- -
- ~
-
,
. ..
s
e
,m.
- s '
'
'
_4_
-
,
,
4
- ; Additional observations were that procedures did not define the requirements
of calibration lof thermome'.ers and hydrometers used for battery checks
-
. required by Technical Specifications (4.9.A.3).
These instruments were
'
not under the scope of-the calibration program.
It'is planned byiCNS to
,
put theselinstruments under the calibration program. -In review of calibration
records it was. noted that a vibration meter (IS-1903) had been found by an
'outside lab to be out. of tolerance on April 27, 1985. The report noted
<
that the velocity.and displacement readings were low by 10% of full scale.
s
There appears to have been no "Out of Calibration Test Equipment
Eval.uation Sheet" initiated for this case. This meter had been used on
March'13 and 15,1985, .for surveillance 6.3.82 and on April 19, 1985,
.for surveillance 6.3.20.1, which are safety-related' pump operability tests
(RHR service water booster and standby liquid control). CNS I&C personnel
'
are evaluating this event.
Subsequent surseillances performed prior to
'
,
,
' plant startup:found no problems with equipment and they were performed
s
with' metering that was satisfactorily calibrated. ~This appears to be an
-
isolated event.
.
-
3;
Exit Meeting
- ,
.
"*
'
I,
- The NRC : inspector conducted an exit meeting on December 6,1985,= with the
!
~
licensee' personnel denoted in paragraph 1.
The NRC senior resident
' ~
'
inspector also attended. At this-meeting, the scope and findings of the
-
,
'4
inspection were summarized.
s
,
'
,
,
-
,
r
p
,
4
,
_ ,.
' t
,
+
$
. .
v
\\
$
.n
Wj
4
+
@
__
______________-.____ _ .