IR 05000267/1978010
| ML20010B834 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/28/1978 |
| From: | Dickerson M, Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20010B798 | List: |
| References | |
| FOIA-81-95 50-267-78-10, NUDOCS 8108180214 | |
| Download: ML20010B834 (8) | |
Text
- - _.
. _ - _ _
_
-
- _.
.
.
U. S. NUCLEAR REGULATORY C0f'.i4ISSION i
OFFICE OF INSPECTION AND EfiFORCEMEfiT
REGION IV
,
IE Inspection Report No. 50-267/78-10 Docket tio. 50-267 License flo. DPR-34
-
'
Licensee:
Public Service Company of Colorado P. O. Box 840 Denver, Colorado 80201 Facility flame:
Fort St. Vrain Nuclear Generating Station Inspection At:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted: June 5-9 and 19-22, 1978 G/2S/78 Inspector:
. g).
.
M. W. Dickerson, Reactor Inspector
' Date n
-
Reviewed By: M
[!oe.-,0 0/.2M78 l
'G. L. Madsen, Chief, Reactor Operations Date j
and Nuclear Support Branch l
l Inspection Summarv l
Inspection on June 5-9 and 19-22, 1978 (Recort No.50-267/78-10)_
l l
Areas inspected _: Routine, unannounced inspection of maintenance; plant operat 1s; 50*4 power level data review; licensee event reports; follow-up r
on circ, s/ bulletins; follow-up on itams of noncompliance, follow-up on inspec, identified and unresolved problems; and review of periodic and special norts. The inspection involved 65 inspection-hours on site by one (1) Nhs inspector.
Results: No ita of noncompliance or deviations were identified.
okO h 14 820514'
.
LIVEDALESI-95
'
.
..
,, _ _
. _,
.
..
_.
. _ _ _ _ _ _, _ _ _ _ _ _ -. _
_ _. _ _.
.
.
-2-i
..
DETAILS
.
1.
Persons Contacted
,
Public Service Company of Colorado r
- D. Alexander, Senior Health Physicist
- L. Brey, Superintendent Operations
- W. Craine, Maintenance Supervisor
-
,
M. Deniston, Reactor Operator M. Ferris, Engineer, Technical Services W. Franek, Results Supervisor
'
+E. Hill, Supervisor, Operations
+*W. Hillyard, Supervisor, Technical Services D. Hood, Shift Supervisor, Operations i
T. Howard, Senior QA Engineer
- F. Mathie, Superintendent, Maintenance
+L. McInroy, Superintendent, QA Services i
+*F. Swart, Superintendent, Nuclear Production I
- C. Tracy, Superintendent Operations QA i
- D. Warembuurg, Manager, Quality Assurance G. Wiltscheck, Results Technician
'
l R. Wollum, Results Technician
- Attended exit interview on 6/9/78 j
+ Attended exit interview on 6/22/78 2.
Licensee Action on Previous Inspection Findings
<
I (0 pen) Unresolved Item (IR 76-07):
Deficiency in supports for 2" and under piping. The licensee is to update their letter of i
November 17, 1977, regarding the status of corrective action relative to this matter.
l
'
(Closed) Deviation (IR 77-09): Failure to verify and document functional acceptability following surveillance testing. The inspector reviewed selected surveillance procedures and determined that the procedures contained provisions for return of the equipment /
system to operability.
(0 pen) Inspector Follow-up Item (IR 77-11): Turbine trip test results at 38% power. The licensee has completed the necessary sign off and
,
l review of the sequence 44 test and the contractor has instituted a l
program for calibration and control of equipment used in the test program. However, the contractor has not verified that the data taken prior to initiation of the calibration program is acceptable.
i
-
i i
,,,7
-
,
-
,
,. - - - -
- - - _ _
-
- -
_ _ _.
- __.
..-
- - _.
-
_-
(
-.
,
~
.
-3-
.
(Closed) Noncompliance (IR 78-04): Supply pressure to LC-2136 greater than specified; calibration intervals for LC-2136 & 21246 greater than allowable; and proper setpoint for LC-21246 not verified during cali-
'
bration. The licensee has completed the corrective action described in their letters p-78050 and p-78057 dated April 3,1978, and April 13, '
1978, respectively.
,
f 3.
Review of Plant Operations
!
During the inspection, the conduct of plant operations was reviewed to determine that they conform to requirements of the facility license
,
and the licensee's procedures.
Included in the review were observa-
tion of control room activities, logs, and records.
In addition the
inspector completed a tour of accessible areas.
The inspector's review of this area included:
,
l Shift Supervisor's Log (January 29 - June 5,1978)
!
(March 17 - June 5, 1978)
Reactor Operator's Log (March 12 - June 5, 1978)
I Surveillance Logs 1-3 i
Operations Order Book i
Form l's (Jumper Log)
Plant Trouble Reports
l a.
Tour I
During the tour of the facility observations were made in the
following areas:
Monitoring Instrumentation i
Radiation Controls j
Housekeeping Fluid Leaks i
}
Piping Vibrations l
Hanger / Seismic Restraints Clearance Tags
i Control Room Manning i
During this tour it was noted that the back of Panel I-22, Helium Purification System regeneration panel, was open and that there were a number of loose wires. These had apparently been utilized
'
in testing which has now been concluded. To remove the extraneous
,
wiring the licensee indicated that a change notice would be issued.
b.
+
i
,-.
-
-
- -,. -,,
. -. -
-
--
. - - - -.,
,,
--
-
.
-4-
.,
Specifically inspected during the tour were panels which had been noted as being cpen during previous inspections (IR 77-09, 77-14).
These were the Diesel Air Compresser control panels and the 1049 Plant Remote Shutdown Panel and its associated recorder panel.
Each was found to be properly closed.
-
Other panels throughout the plant which had previously been noted by the inspector as requiring closure were also observed.
In general there has been improvement in maintaining panels closed following maintenance. At present the licensee is reviewing this matter to provide a method for assuring that panels are closed following maintenance. This matter remains open pending completion of this review by the licensee.
b.
Oscillations Oscillations were observed on June 3 and June 4, 1978, during Test RT-498.
The purpose of the test was to determine the influence of core flow distribution on the threshold for core oscillations.
During the test a core flow was established to produce as close as possible a uniform flow through the core regions. The threshold as induced by rapid load increases was to be determined for two conditions of core differential pressure.
The oscillction on June 3,1978, were observed following slight changes of orifices in several regions. Additionally a small grid frequency transient that caused turbine load to increase by 3 MWE was observed. Power was at 50% and core differentihl pressure was at 3.2 psid. Power was reduced to approximately 40% to stop the oscillations.
On June A, 1978, the oscillations occurred while the differential pressure was at 3.34 psid following a load increase from 40 to 45% power at a rate of 5% per minute.
Immediate power reduction was again required to stop the oscillatior.s. Successive reduc-tions in 5% increments were required each producing a reduction in the amplitude of the oscillations until they were stopped at 34% power. The maximum oscillation magnitude observed were approximately 1400F peak to peak in steam generator module B-1-5
and 120 F in fuel region 34. At present the data gathered during this test is being evaluated by PSC and GA.
No items of noncompliance or deviations were identified during the review of plant operations.
l
.
'
>
.
-5-
.
i 4.
Maintenance
!
l The inspector reviewed selected maintenance activities to determine that these activities met acceptable maintenance practices, the licensee's applicable administrative and maintenance procedures, and were in accordance with Technical Specifications.
-
The activities reviewed were as follows:
PTR 12-178 Repair of CRD #35.
PTR 12-179 Repair of CRD #22.
PTR 3-107 Annual Inspection of P21015, Bearing Water Pump.
PTR 3-560 C2107. Helium Recovery Compressor, not pumping.
PTR 3-58
' test and calibration purposes.LC-2136, level Controller, Install Vent Capability for PTR 4-381 FE-2140 Backup Bearing Water Flow Element, pinhole leak at weld.
!
PTR 5-187 "C" Circulator Water Pump, outboard bearing low on oil.
i PTR 3-28 E-4101, inspect Main Condensor Anchor Bolts.
'
PTR 4-142 V-11835. Hand Wheel separated from shaft.
PTR 5-38 C-9201X, Perform monthly inspection.
PTR 4-71 K-9204X, Perform semiannual inspection of standby diesel.
During review of the data package for PTR 12-178 it was apparent that no record for the installation of the Reactor Isolation Valve had been maintained. Discussion with licensee indicated that this had been recognized and that Procedure MP-12-1, dated March 8, 1978, had been developed which includes the requirement to document this maintenance activity.
Ho items of noncompliance or deviations were identified.
5.
Review of Licensee Event Reports
,
,
!
The inspector verified that licensee event reporting activities were in accordance with Technical Specification, Section 7, including identification of details, corrective action, review and evaluation, i
aspects of operations and accuracy of reporting.
The following reports were reviewed by the inspector:
RO 78-07 RO 78-10 R0 78-08 R0 78-11 RO 78-09 RO 78-12 No items of noncompliance cr deviations were identified.
.
.
- - - -
- -
_
.
..
-6-6.
Review of Bulletins / Circulars i
The inspector verified by record review, observation and discussion
.
with representatives of the licensee, the action taken in response i
to IE Bulletins and Circulars.
'
.
.
The following Bulletins and Circulars were reviewed:
Circulars Bulletin
78-02 78-05 78-04
,
78-06 78-07
,
!
No items of noncompliance or deviations were identified.
7.
Startup Reports The inspector reviewed the sixth Fort St. Vrain Startup Report.
The report covering the period November 22, 1977, through February 22, 1978, was reviewed in the Region IV office.
)
No items of noncompliance or deviations were identified.
8.
Power Ascention Program j
a.
Scope of Inspection
.
The inspector reviewed selectoi test data associated with the i
power ascention program. S':ce i:elly reviewed was the test data developed at 50% power lew ! (# ~quence 46).
r
!
Included in the reviews -ers n.< Itcensee's evaluation of the data,
^i test changes, test defit tencies, data sheets, QA audits, and test data approval.
'
Reviewed were sequences Technical Review Committee Meeting Minutes for Meeting through Meeting No.17; and the following QA meses summarizing
the QA surveillance conducted in accordance with QA Surveilla j
Procedures 201, 401, and 601:
I i
l
'
.,
,
1
,,-,.,,. - -,,,
,. -, -.. -,, - - -
+,-m.
,. -. -. -
-
.. -
-
..
.
-.
-
.
-
.
.
).
.
.
,
-7-
.'
.
I 8/2/76 HFR:10: HLB:76 8/11/76 HFR:12: HLB:76 9/2/76 JCS:12: HLB:76 12/1/76 TLH:07: HLB:76 1/19/77 TLH:03: HLB:77
.
i 9/20/77 JCS/TLH:06: HLB:77
'
.
10/28/77 JCS:08: HLB:77
11/2/77 QA Review of Sequence 46.
.
b.
Inspection Findings
"
(1) QA Surveillance i
^
QA surveillance of the test data is being conducted on a
'
100% basis.
While same administrative problems are being i
identified, timely corrective action is generally resolving the problems.
(2) Steam Generator Performance
<
l Steam generator performance at 50% power continued to improve compared to that observed at lower power levels.
i Durin; he Sequence 46 test (50% power), an average reheat temperature j
of approximately 9500 steam temperature of 9200F.F was achieved with an average main i
'
temperature was from 790 F to 8050 Maximum measured crossover tube
F
!
(3)
H.2 Tritium
/
Outgassing of the H
2 getter prior to replacement in the e
purification system has apparently improved its efficiency and the removal of hydrogen and tritium is considered accept-
able.
2,
,
.
(4) Helium Purification System Detectable levels of nitrogen continue to be observed at the discharge of the purification system.
f (5) _ Gas Chromatograph Calibration
-
Calibration of gas chromatograph continues to exceed
acceptance valves of + 30.
!
.
l
.
m
,,
a r
-
,
,
---r-
-
~~~
_j.L
'
__
_-
..
7,
~
....
s q-8-
!
(6)
PCRV Liner Cooling - Heat Loads greater than expected.Several PCRV liner cooling tu
j Extrapolation of thE.1un at AT's
'
peratures to higher power levels indicates th t th tube tem-
'
ance criteria will not be met.
a.
-
modification to the FSAR is under considerationBased on
}
(7)
!!eliumLeakRate,
.
{
The helium leak rate continues to be higher th
{
i, The average helium loss during this test (at 50%
an desired.
lt 62 pounds per day.
power) was
!
(8)
'
f Nuclear Instrument Decalibratior i
Decalibration of the nuclear instrumentatio of the control rod positions continue to be observ d
n as a function (9)
}'
Helium Circulation Shutoff Valve Actuatio e.
$
n The actuation of a circulation shutoff valve o
!
!
circulator imbalance has not occurred since n slight f
'
15 testing.
have been experienced with no actuation of the i
]
equence l
valves.
!
i shutoff
!
(10)
Temperature Coefficient / Temperature Defect i
ThetemperaturecoefficiengmeasuredduringSe
'
(50% power) was -5.2 x 10 4F/0
{
quence 46 of -4.0 x 10-5 F vice the predicted valve f
h.P/0F and the temperature defect at 12230F
j was 0.0613 APvice 0.059 u.
i i
(11)
Xenon Build-uo and Decay The measured change in reactivity due to Xeno i
{
rising from 40% to 505 reactor pa;r agreed with th n build-up in dicted value within + 10%.
e pre-9.
Exit Interview
Exit interviews were conduted on June 9 and 22
,
.
the inspector discussed the findings indicated i
, 1978. At the inter
graphs.
The licensee acknowledged these findingsn the previous paraview
1
.
'
$
i i
'
l
,
t
.
.
. _. _ _ - _
_
.
.
.-
-
_