ML19207B501
| ML19207B501 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/28/1979 |
| From: | Dickerson M, Westerman F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19207B497 | List: |
| References | |
| 50-267-79-12, NUDOCS 7908300069 | |
| Download: ML19207B501 (6) | |
See also: IR 05000267/1979012
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U. S. NUCLEAR REGUIATORY COMIISSION
OFFICE OF INSPECTION AND ENFORCEZIENT
REGION IV
IE Inspection Report No. 50-267/79-12
Docket No. 50-267
License No. DPR-34
Licensee:
Public Service Company of Colorado
P. O. Box 840
Denver, Colorado
80201
Facility:
Fort St. Vrain Nuclear Generating Station
Inspection at: Fort St. Vrain Site, Platteville, Colora 4
Inspection Conducted: June 12-15, 1979
Inspector:
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M. W. Dickerson, Reactor Inspector
Date'
Reviewed by:
Ma
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'T. F. Westerman, Chifef', Reactor Projects Section
Date
Inspection Summary
Inspection on June 12-15, 1979 (Report No. 50-267/79-12
Areas Inspected: Routine, uannounced inspection of review of plant operations;
licensee event reports; followup on Bulletins / Circulars; review of special and
periodic reports; and followup on inspector identified and unresolved problems.
The inspection involved twenty-nine (29) inspection-hours on-site by one (1)
NRC inspector.
Results: Of the five (5) areas inspected, one (1) item of noncompliance was
found during the review of plant operations (Infraction - failure to comply
with T/S requirements - paragraph 3).
852 062
7908300 O
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Details
1.
Persons Contacted
- L. Brey, QA Manager
M. Ferris, Engineer, Technical Services
- J. Gamm, Supervisor, Technical Services
- E. Hill, Supervisor Operations
- T. Howard, Superintendent Operations QA
J. Liebelt, Supervisor Electrical Maintenance
- F. Mathie, Operations Manager
M. McBride, Engineering Coordinator
J. Solakiewkz, QA Engineer
J. Van Dyke, Shift Supervisor Operations
G. Wiltscheek, Results Engineer
V. Wetzbarger, Scheduling /QC Supervisor
R. Wollum, Scheduling QC
- D. Warembourg, Manager Nuclear Production
- Attended exit interview.
2.
Licensee Action on Previous Inspection Findings
(Closed) Unresolved Item (50-267/73-04):
Corrosion Monitoring Program.
Based on the information, regarding the results of the four year corrosion
monitoring program, contained in the licensees letter P-79110, dated
May 23, 1979, there are no further questions at this time.
,
(Closed) Open Item (50-267/77-04): Steam Generator Bimetallic Weld. Based
upon the information contained in a transmittal from Gammill to Fuller, dated
March 30, 1979 and Public Service Company letter P-79073 dated April 6, 1979.
The matter is considered resolved.
(Closed) Open Item (50-267/77 -11): Turbine Trip Test. The data utilized
from strip chart recorders wai used to determine 1/4 amplitude dampening
only. No other acceptance cre eria were utilized from instrumentation
which was not in a formal calibration program prior to December 1977 for
the Turbine Trip Test. Based on this information, an informal calibration
program prior to this date, and the fact that no instrumentation was
noted as being out-of-calibration at the time of formal calibration program
initiation (December 1977) The data appears to be acceptable.
(Closed) Open Item (50-267/7903-1): 50% Load Time Not Explicitely
Defined In Diesel Generator Test SR5.6.1.a.w.
The licensee has revised
the surveillance test to specifically define the time at 50% load.
852 063
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3
(Closed) Open Item (50-267/7908-4): Fire Water Booster Pump Installation.
The addition of Booster pumps P-2109 and P-2110 to proved fire water
for motive force of the circulator pelton wheels has been completed.
3.
Review of Plant Operations
The inspector selected several procedures for review which had been changed
by the licensee for those systems which had undergone maintenance, or were
disturbed during the outage.
Included was a determination by review of
records whether the systems were returned to service in accordance with
approved procedures.
During this review it was determined that overall plant operating pro-
cedure 1 (OPOP I) pages 11 and 12 had been signed off on June 12, 1979 as
" Reserve Shutdown System Operable" based on section B.2.a(1) 1.3
"Preoperational Valve lineup made per S0P 12-05" and section B.2.a(1)1.4
Prerequisites complete per S0P 12-05".
A review of Appendix 1 to
S0P 12-05 (valve lineup checklist) indicated that the status of valves
HV-1104-1 and HV-1102-1 had apparently not been checked as required.
Since the check list had not been completed and OPOP I had been signed
off based on completion of the check list, the licensee was informed that
this was an item of nonconformance and was considered an infraction.
Technical Specification AC 7.4.a requires in part that, " written procedures
shall be establishsd, implemented and maintained . . .", and OPOP 1,
General Plant Requirements states that section B of the procedure contains
check lists to determine the operability of Various Plant System and that
completion of the check lists shall be in accordance with the following:
All system checklists shall be completed in their entirety
before startup
following a shutdown from refueling and instrumentation and control system
signoffs, prerequistes per S0P signoffs, and the senior licensed operator
signoffs are required.
In addition to the system 12 review noted above the inspector also reviewed
S0P 11, Prestressed Concrete Reactor Vessel; S0P 21-02, Helium Circulator
Auxiliary System; and S0P 31 Feedwater and condensate system.
Review of the above procedures and checklists indicated a need for a system
of control for items such as stop valves to pressure differental indicators
which are closed, where flexibility is exercised in a system when a valve
is closed or open instead of open or closed as shown on a pre-startup
checklist, when bypasses are cracked open, where valves may be partially
opened and where one of several duplicated components is utilized instead of
the others.
In discussing this with the licensee it was indicated that this
need had been recognized and that numbered control tags were an order which
would replace the present system of using unnumbered status tags. Use
of the numbered tags should provide fcr supervisory control and establish
the systems status. This will remain as an open item.
852
064
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The inspector also reviewed records of the control rod withdrawal sequence,
plant startup, heatup, approach to criticality and rise to less than 2%
power and determined that they were conducted in accordance with approved
procedures and the Technical Specifications.
The inspector had no additional questions in this area.
4.
Holdup Items For Greater than 2% Power
a.
Emergency Condensate Isolation Vtives
An engineering evaluation study of the hydraulic operators used on
emergency feedwater condensate isolation valves HV-2237 and HV-2238 has
resulted in the replacement of the hydraulic operators with seismically
qualified limitorque valve operators. The addition of the operators
has resulted in the need of the additional support of two spring
hangers and eight hydraulic snubbers. At the time of the inspection
the valve operators had been installed but the hanger and snubbers
had not been installed.
b.
PCRV Deflection Tests
Deflection tests have been performed on the PCRV up to 400 psia and
no constraint _is imposed on power greater than 2% except that
deflection tests are also required at approximately 28% power.
c.
Two Loop Dump
The two loon dump radification (fix) have been completed and T-62
the functional test has been completed and found acceptable by the
licensee.
d.
Phase III Fire Protection
The phase III fire protection system has been completed with the
exception of CN-619, the installation of one spray shield over inverter
IA in the 480 volt room. Additionally functional test 724 has not
been completed because of diffievlties associated with the first hit
annunciator panel.
c.
Hydraulic Snubbers
At the time of the inspection sixteen snubbers remained to be tested,
reassembled and installed.
f.
Alternate Cooling Method
The alternate cooling method has been installed and functionally tested.
A review of the functional tests by the inspector indicated that the
testing had been performed satificatorrily.
Ob2
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g.
A letter from the licensee to reactor licensing is in preparation which
would resolve those items included in letter P-78071, dated May 8,
1978, which were required to be resolved prior to startup after the
first refueling. The status of the items are as follows:
(1) CN 892 has updated the applicablu P&I's and S0P 21-02 and
S0P 46 have been revised to show valves V 211526, V-46181, V-46182
and V-42144 closed.
(2) CN 892 completed for seismically qualifying the following
instrument root valves:
PS-1194
LS-21502
LS-92206-3
PI-11217
LG-21502
LS-92207-3
LIS-11267
PDIS-2329
M-92800
PIT-11215
PDIS-2330
M-92801
PDT-2133
PT-23103
M-92802
PDT-2134
PT-23104
M-92803
= >
u-
PI-21470
LCV-4501
(3) The Cardox Tank and associated piping systems has been determined
by the licensee not to require upgrading. The piping system
is supported to withstand OBE and DEE forces. Additionally the
Cardox Tank is an "FM" approved installation and will withstand
seismic forces in accordance with code requirements.
5.
Startup Report
The tenth and eleventh startup reports for Fort St. Vrain for the period
November 22, 1978, through May 22, 1979, reviewed by the inspector,
contained no relevant information on the initial approach to power tests
since none were performed during this period of time due to the restriction
for plant operation in excess of 70 percent power and the shutdown of the
plant for refueling.
6.
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 of aspects relative
to operations and accuracy of reporting.
852 006
6
The following reports were reviewed by the inspector:
U.E. 75-21
R.O. 79-07
A.O. 76-20
R.0. 79-09
R.O. 77-47
R.O. 79-10
R.O. 78-37
R.O. 79-11
R.O. 78-39
R.O. 79-15
R.O. 79-01
No items of noncompliance or deviations were identified.
7.
IE Bulletins
The inspector verified by record review, observation and discussion with
representatives of the licensee, the action taken in response to IE Bulletins.
The following Bulletins were reviewed by the inspector:
- s ,
x._
78-12B
79-07
79-01
79-09
79-03
79-10
'
79-04
79-11
No items of nonconformance or deviations were identified.
8.
Exit Interview
An exit interview was conducted with representatives of the licensee
on June 15, 1979, at the conclusion of the inspection. At the interview,
the inspector discussed the findings indicated in the previous paragraphs.
The licensee acknowledged these findings.
852 067