ML19210D207
| ML19210D207 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/10/1979 |
| From: | Dean S, Rich Smith, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19210D197 | List: |
| References | |
| 50-298-79-14, NUDOCS 7911260038 | |
| Download: ML19210D207 (7) | |
See also: IR 05000298/1979014
Text
.
.
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-298/79-14
Docket No. 50-298
License No. DPR-46
,
Licensee:
Nebraska Public Power District
.
P. O. Box 499
.
Columbus, Neb.aska 68601
~
. , .
Facility Name:
Cooper Nuclear Station
Inspection At:
Cooper Nuclear Station, Nemaha County, Nebraska
,
Inspection Conducted: September 10-14 and 19-21,1979
/
.
Principal
'
Inspector:
-/ O -79
G. (K. Constatfie, Reactor Inspector
Yate
l?-J O- 79
.
_
,
R.* Smith,' Reactor Inspector
~Date
Y
D
/O'/O-79
t
S. R. Dean, Reactor Inspector
Date
Approved By:
N [<
/6-/d- 7d7
T. F. Westerman, Chief, Reactor Projects Section
Date
Inspection Summary
Inspection conducted September 10-14 and 19-21, 1979 (Report No. 50-298/79-14)
Areas Inspected:
Routine, unannounced ir.spection of plant operations, Quality
Assurance Program, Part 21 Report, and a follow-up on IE Bulletins, Circulars and
LER's. The inspection involved one hundred thirty-three (133) hours on-site by '
'
three (3) NRC inspectors.
.
'
+~
Resul ts: No items of noncompliance or deviations were noted in five of the six
'
areas inspected.
One item of noncompliance (deficiency - Failure to log unexpected
'
change in power level TS 6.6.1).
.
092
332
7911260
h
-
.
-2-
DETAILS
Persons Contacted
L. F. Bednar, Electrical Engineer
R. D. Black, Shift Supervisor
P. F. Doan, Mechanical Engineer
R. A. Jansky, Shift Supervisor
H. A. Jantzen, I&C Supervisor
-
J. H. Kuttler, Lead HP Technician
,.
- L. C. Lessor, Station Superintendent
C. R. Noyes, Technical Assistant to Station Superintendent
J. L. Peaslee, Shift Supervisor
J. V. Sayer, Chemistry & HP Supervisor
R. W. Seier, Quality Assurance Supervisor
P. V. Thomason, Assistant to Station Superintendent
M. G. Williams, Operations Supervisor
V. L. Wolstenholm, Quality Assurance Specialist
W. H. Wunderlich, Administrative Supervisor
- Present at the exit interview.
In addition to the above technical and supervisory personnel, the inspectors
held discussions with various maintanance, operations, technical support and
administrative members of the licensee's staff.
1.
Plant Status
During the period of this inspection, the plant was in routine full power
operation on September 10, 11 and 19-21, 1979. The Unit experienced recirc
pump seal failure on September 12 and remained shut down for repair until
September 14, 1979.
2.
Review of Plant Operation
The inspectors reviewed logs and records, discussed plant operation with '
management and shift personnel, observed a safety system operability test
from the control room and locally observed routine and abnormal operation
of the plant, observed routine radiological controls during maintenance of
a primary system within containment, and toured accessible areas of the
plant.
The purpose of this effort was to determine that operations were
being conducted in accordance with license conditions and other NRC
requirements.
>:R
-3;
+
The below listed logs and records were reviewed:
- ,
,
..'
Reactor Operations Log
June 5 - July 14, 1979
.
September 10-20, 1979
1392
333'
-3-
Shift Supervisor's Log
June 18 - August 31, 1979
.
September 10-20, 1979
Scram Reports
79-4 May 25, 1979
'p.
.
79-5 August 9, 1979
d-
79-6 September 13, 1979
l
,
Night Order Book
August 1 - September 20, 1979
['
'
.
Jumper Log
All outstanding entries
[C
.
-
The inspectors witnessed the operability testing of the High Pressure
Coolant Injection System in accordance with System Operating Procedure
2.2.33 and Surveillance Procedure 6.3.3.1.
The test was performed
following maintenance to the HPCI turbine stop valve. The coupler
between the valve actuator and valve stem had failed. The deficiency
was discovered on September 12, 1979 while performing routine surveillance
testing.
The inspectors observed normal power operation from the control room and
within the plant.
During observation of normal reactor power operation,
the inspectors witnessed the isolation of a small primary coolant leak.
The B loop recirculating pump seals had been slowly degrading for seven
hours prior to the occurrence.
Plant management and operators were aware
of the situation and were monitoring pump performance and leak rate in
light of the seal preblem. At approximately 1:15 p.m. on September 12, 1979,
the leak from B loop recirculating pump rapidly increased to approximately
30 gallons / minute.
Plant power was reduced from approximately 100 percent
to approximately 50 percent and at approximately 1:35 p.m., the leak was
isolated with B loop recirculating pump secured.
Beginning at approximately
10:00 p.m. on September 12, 1979, a plant shutdown was begun and at
approximately 4:09 a.m. on September 13, 1979, the reactor was scramed
from approximately 12 percent power.
Health Physics and Radiation Control practices were reviewed at the
contamination control point. Acceptable radiological control practices
were observed to be in effect.
No radiation exposures exceeding the
limits of 10 CFR 20 Occurred as a result of this maintenance activity.
The inspectors toured accessible areas of the plant including the contain-
ment building. The following conditions were observed:
,
General cleanliness was satisfactory.
_ l h,ii h
'
, V/
' Q(h' *
.
,
There were no excessive fluid leaks.
fj
.
' ' g t-
There were no excessively vibrating piping.
.i
.
,
There were no observed fire hazards.
.
Seismic restraints and pipe hangers appeared to be in satisfactory
.
condition.
,
1392
334
'
4
During discussions with shift operators on the current method of adjust-
ing RRMG set speed, the inspector learned that on or about September 18,
1979, while attempting to reset a scoop tube lock out, the ARRMG set ran
back to minimum then ramped back to 93 percent. When the inspector looked
at the Operator's and Shift Supervisor's Logs he discovered that the
event had not been logged.
The failure to log this unexpected deviation from normal station operation
is in noncompliance with Technical Specification 6.6.1 and Cooper Nuclear
'
Station Administrative Procedure 1.4.
_
No other items of noncompliance were noted in this area.
3.
Quality Assurance Program Review
The objective of this inspection effort was to review changes made to the
licensee's QA program and verify that this program is in confonnance with
the approved QA program as required by 10 CFR 50, Appendix B.
Selected
licensee personnel were interviewed to determine their familiarity with
this program. A sample of Administrative Procedures, Quality Assurance
Instructions and Procedures were reviewed to ensure compliance with the
approved QA program. The inspector reviewed the licensee approved QA
program amendment 37 of the FSAR and it was determined that although a
QA program is in effect, changes have been submitted to this program to
better identify the requirements necessary for Cooper Nuclear Station.
Minor procedure changes will be necessary to implement the submitted
Quality Assurance Program. These changes will be inspected at a future
date.
The inspector had no additional questions in this area.
4.
Part 21 Report - Namco Controls
A Part 21 report was made by Namco Controls on August 24, 1979 regarding
Namco EA180 series limit switches. Three of these switches are used on
each of the eight main steam stop valves.
Four of the valves are inside
the drywell and the other four are outside of the drywell in the steam
tunnel.
Cooper Nuclear Station had reported to Namco the discovery of
" crystal-like" resin deposits on one of the switches. Tests conducted by
Namco indicated that the deposits were from the vaporization of some of the
Loctite in impregnated gasket material. Namco believes that the deposits
were formed due to excess or non-uniform impregnation of the Loctite in
the gaskets. A question was raised as a result of the Namco report as .to
whether the switches at Cooper Nuclear St. tion were exposed to higher than
design temperatures.
The inspector discussed the location of the switches
l
with plant staff, observed drywell temperature monitors and observed while
plant staff took a direct reading on one of the installed Namco switches.
As a result of this review, it was determined that the Namco switches are
exposed to an approximate maximum temperature of 1800F, compared to the
continuous design limit of 1940F.
The inspector has no further questions
at this time.
1392
335
.
-5-
5.
Follow Up on IE Bulletins
The inspector performed follow up on'the following IE Bulletins to determine
that the licensee's station staff had received a copy of the Bulletins and
had reviewed them for applicability. The inspector reviewed the licensee's
response for each Eulletin to determine that the response had been submitted
in the time frame required and the information discussed in the licensee's
reply was supported by facility records or a visual examination of the
facility.
The licensee's corrective actions or proposed corrective act'ons
were reviewed to verify appropriateness.
,
IEB
Title
Status75-04B
Cable Fire at Browns Ferry
Closed
78-05
Malfunctioning of Circuit Breakers
Closed
78-11
Examination of Mark I Containment Torus
Closed
78-14
Deterioration of BUNA-N Components in ASCO
Closed
Solenoids
79-11
Faulty Overcurrent Trip Device in Circuit
Closed
Breakers for Engineered Safety Systems
79-13
Cracking in Feedwater System Piping
Closed
79-17
Pipe Cracks in Stagnant Borated Water
Closed
Systems (PWR's)
No items of noncompliance or deviations were noted in this area.
6.
Follow Up on IE Circulars
The inspector reviewed the following IE Circulars to determine that the
licensee's station staff had received these Circulars and reviewed them
for applicability. The inspector reviewed the licensee's actions and
proposed actions on each Circular to determine if these actions were
consistent with the situation at the facility.
IEC
Title
Status
.
78-15
Tilting Disc Check Valves Fail to Close
Closed
.
78-17
Inadequate Guard Training
Closed
,
79-02
Failure of 170 Volt Power Supplies
Closed
79-04
Loose Locking Nut on Limitorque Valve
Closed
Operators
t392
336
-6-
-
IEC
Title
Status
79-05
Moisture Leakage in Stranded Wire Conductors
Closed
79-08
Attempted Extortion - Low Enriched Uranium
Closed
79-09
Ruptured Diaphragms - Scott Air Packs
Closed
79-10
Pipefittings Manufactured from Unacceptable
Closed
Material
79-12
Potential Diesel Generator Turbocharger
Closed
,
Problem
7
79-13
Replacement of Diesel Fire Pump Starting
Closed
Contractors
79-15
Bursting of High Pressure Hose and Malfunction Closed
of Relief Valve and "0"-Ring in Self-Contained
Breathing Apparatus
79-17
Contact Problem in SB-12 Switches on General
Closed
Electric Metalclad Circuit Breakers
No items of noncompliance or deviations were noted in this area.
7.
Follow Up on Licensee Event Reports
The inspector reviewed the following licensee event reports to verify that
reporting requirements were met and to assess whether further NRC action
is appropriate.
LER
Title
Status
79-06
Fire Watch net established when doors
Closed
removed between diesel generator rooms
79-07
Core spray valve failed to open during
Closed
surveillance.
79-10
Surface linear indication found during ISI.
Closed
,
79-12
Vessel temperature reached 2200F during leak
Closed
test without primary containment being
E
established.
f
s
79-13
Drywell/ Suppression Chamber differential
Closed
,
~ '
pressure not established within 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />
due to leaky valve.
r
-
79-16
RHR Pump tripped during surveillance.
Closed
1392 337
.
-7-
LER
_ Title
Status
79-20
Failure of relief valve bellows monitoring
Closed
switch.
79-23
High steam flo,i d/p switch failure
Closed
-
In addition to the above, the following LER's were reviewed on site to
verify that the report accurately describes the actual event and to
verify that corrective action planned or taken is appropriate.
LER
Title
Status
'
79-5
Recirculating MG trip
Closed (See
comment below)
79-8
Breaker 1FA failed to trip
Closed
79-15
Breaker lA5 failed to close
Closed
79-18
Level switch found out-of-specification
Closed
79-19
PCI did i.ot start
Closed
During the review of LER 79-5, the inspector investigated how I&C shop
personnel verify what the set point for a particular instrument should-
be. The inspector noted that LER 79-5 had reported that NBI-LIS-58A had
two sets of contacts: one to provide a scram and a primary containment
isolation at 12.5 inches, and the other to give a ATWS recirculation
pump trip and MSIV isolation at -37 inches. A corrected LER 79-5-1
indicated that the level indicator had one switch to give an MSIV
closure at -37 inches and the other switch to give the ATWS recircula-
tion pump trip at -37 inches. The normal method of verifying a set
point is to consult the I&C set point book which is maintained by the
I&C supervisor.
In the case of the first LER, the set point book was not
used.
Instead an I&C component index that was being developed to provide
input for computer records had been used. Although the I&C component
index had been through one level of review the data in it was incorrect.
The inspector expressed concern that the licensee should ensure that
incorrect safety-related data should not be stored in the computer.
,
This item will remain open pending further review.
?
-
8.
Exit Interview
< , '~ t
~
. ;f
.
The inspector met with the Station Superintendent at the conclusion of
o
the inspection.
The scope of the inspection and the findings were
discussed.
)hb
bb