ML19351G131
| ML19351G131 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/15/1980 |
| From: | Dickerson M, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19351G107 | List: |
| References | |
| 50-267-80-24, NUDOCS 8102230161 | |
| Download: ML19351G131 (8) | |
See also: IR 05000267/1980024
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V. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Iaspection Report No. 50-267/80-24
Docket No. 50-267
License No. DPR-34
Licensee:
Public Service Company of Colorado
P. O. Box 840
Denver, Colorado 80201
Facility Name:
Fort St. Vrain Nuclear Generating Station
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Inspection at:
Fort St. Vrain Site, Platteville, Colorado
Inspection C onduc.ted:
November 1-30, 1980
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Inspector:
or>
11, 4
p
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W. p; ckerson, Senior Resident Inspector
Date
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lt 16 0
Approved by
\\ F. Wepterman, Chie;, Reactor Projects 5ection No. 1
Date
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Inspection ummary:
Insoection Conducted on November 1-30, 1980 (Report No. 50-267/80-24)
Areas Inspected:
Routine, announced inspection of review of plant operations;
followup on previous items of noncompliance; surveillance; maintenance; opera-
tional safety verification; and review of periodic and special reports.
The
- nspection involved 98 inspector-hours on site by one (1) NRC inspector.
Results:
Within the six (6) areas inspected, two items of noncompliance were
identified (failure to comply with procedural requirements, Paragraph 4 and
exceeding a Technical Specification LCO, Paragraph 38).
8102 230 g
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DETAILS
1.
Persons Contacted
G. Billings, Shift Supervisor
L. n. rey, QA Manager
W.
+:rKlin, Shift Supervisor
J. Gamm, Supervisor Technical Services
E. Hill, Superintendent of Operation
W. Hillyard, Administrative Services Manager
D. Hood, Shift Supervisor
J. Liebelt, Maintenance Supervisor
/. Mathie, Operations Manager
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T. Orlin, Superintendent Operations QA
J. Van Dyke, Shift Supervisor
D. Warembourg, Manager, Nuclear Production
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V. Wetzbarger, Scheduling & QC Supervisor
The inspector also contacted other plant personnel including reactor
operators, maintenance men, electricians, technicians and administrative
personnel.
2.
Licensee Action on Previous Irspection Findings
(0 pen) Unresolved Item (50-267/7502-03T:
Fission Product Probe.
The licensee intends to remove the Fission Product Probe for analysis
during the March 1981 shutdown.
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(0 pen) Open Item (50-267/7607-01):
FSAR Amendment Electrical Modifica-
tions.
The licensee intends to submit an amendment to the FSAR in mid
1982.
(0 pen) Unresolved Item (50-267/7607-04):
Seismic and En,ironmental
Qualifications.
Clarifications of certifications are still required
on two equipment items.
Additionally, the two inch a.d under Class 1 piping support program is
still in progress and is expected to be completed by the end of 1982.
However, a status report to NRR by PSC Nuclear Projects Department on
this matter appears to Le overdue.
(0 pen) Open Item (5.-267/7610-01):
Power Ascention Program.
Tests
above 70% power lesel have not been conducted pending approval by NRR
to excc+d the 70% power level.
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(0 pen) Unresolved Item (50-267/7613-01):
Plant Operating Cycles.
TPe
licensee has indicated that a procedure for data collection will be
implemented on January 1, 1981.
Additionally, previous data compilation
for the plant is to be completed March 1, 1981.
(0 pen) Unresolved Item (50-267/7614-01):
Pulled Fusses.
An audit to
identify !ach fuse block and then indicate the size fuse that is
required, is to start by July 1, 1981 and be completed within one
year.
(Closed) Open Item (50-267/7915-02):
Procedure for PTRs to be Revised
to Define Requirements for Stating Work Methods.
Work methods are now
defined in new procedure P-7, Work Control-Maintenance.
(0 pen) Unresolved Item (50-267/7919-01):
Correct identified Orawing
Discrepancies (Bulletin 79-02).
Corrective action with regard to this
item is included with that being made for Bulletin 79-14.
(0 pen) Unresolved Item (50-267/8008-01):
Radio Transmitters caused
Upset in Buffer-Mid-Buffer System.
Test T-148 was run on July 16, 1980,
to determine the effects of radio transmitters on various instruments in
the Reactor Building and the Turbine Building.
However, the test was
run at zero reactor power and was inconclusive.
The test is to be rerun
on December 6, 1980 with the reactor at power.
(0 pen) Ooen Item (50-267/8009-01):
Responsibility for Review of
Maintenance Activities for Equipment Trends.
This is not yet described
in a procedure but the computer program and data base to be used are
being determined.
The program is expected to be operational July 1, 1981.
(Closed) Unresolved Item (50-267/8010-01):
Replace Manita Tags with
Pre-Prirted Taas in Storage Area.
The material with manila tags has
been pul:ed from the storage bins and is now in a separate storage
area where it~is being retagged or scrapped.
(0 pen) Open Item (50-267/8010-02):
Bulletin 79-27, '.wo items remain to
be completed during Refueling outage planned for September 1981.
(Closed) Unresolved Item (50-267/8012-01):
Independent Verification
of Clearance Tags.
This has been upgraded to noncompliance item
8020-01.
(0 pen) Open Item (50-267/8014-03):
Conflict on Calibration Frequency
Between ADM-14 and Computer List.
The conflict is scheduled to be
resolved by January 1, 1981.
(Closed) Unresolved Item (50-267/8016-02):
Storage of Documents.
Copies of hanger drawings and related isometrics which are stored outside
of the record storage building have been made and are now stored in the
record storage building.
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(0 pen) Open Item (50-267/8016-03):
Revision to ENG Procedures.
Revisions
to ENG 1 and ENG 3 procedures is expected to be complete by January 15, 1981.
(Closed) Open Item (50-267/8016-04):
Revision U of Orawing E-1777.
Distribution of revision U to this drawing has been made to the site
document storage and to the plant.
(0 pen) Open Item (50-267/8018-02):
SR 5.10.3-M/5.4.2-A Requires Modifi-
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cation.
Modification has been made to the surveillance procedure but it
had not been approved as of November 30, 1980.
3.
Operational Safety Verification
The inspector reviewed licensee activitiec to ascertain that the facility
is being operated safely and in conformance with regulatory requirements,
and the licensee's management control system is effectively discharging
its responsibilities for continued safe operc':on.
The review was con-
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ducted by direct observation of activities, tours of the facility, inter-
views and discussions with licensee personnel, independent verification
of safety system status and limiting conditicns for operations, and review
of facility records.
Included in the inspection were observation of control room activities,
review of operational logs, records, and tours of accessible areas.
Logs and records reviewed included:
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Shift Supervisor Logs
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Reactor Operator Logs
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Equipment Operator Logs
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Auxiliary Operator Logs
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Technical Specification Compliance Logs
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Operations Order Book
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System Status Log
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Form 1 Log (Jumper Log)
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Plant Trouble Reports
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During tours of accessible areas, particular attention was directed
to the following:
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Monitoring Instrumentation
Radiation Controls
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Housekeeping
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Fluid Leaks
Piping Vibrations
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Hanger / Seismic Restraints
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Clearance Tags
Fire Hazards
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Control Room Manning
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Procedures were also reviewed and implementation observed for Liquid
Waste Release No. 415 preceded by SR 5.8.2 bc-m Radioactive Liquid
Effluent System Instrumentation Functional Test.
The release appeared
to have been made in a satisfactory manner.
A.
Control Room Observetions
During observations in the control room on November 13, 1980, and
again on November 14, 1980, the inspector noted that POI-7319
(Refueling Floor to Ambient Differential Pressure) was pegged in
the position indicating a positive differential pressure.
A check
each day indicated that the indication was erroneous and that
a negative differential pressure was being maintained as required.
A PTR was written to investigate the cause of the incorrect pressure
indication.
No significant cause for the instrumentation indication
could be found.
However, while the instrument was being worked
on it began to operate properly.
Frequent checks since that time
have indicated no additional problems.
During observations in the control room on November 3,1980, it was
noted that the Wind and Speed recorder was tagged as inoperative with
PTRs10-428 and 10-438 written to repair the device.
A check indicat-
ed that problems with the computer allowed it to be 180 degrees out
of synchronization.
New parts are on order to repair the device.
In the interim an Operations Order has been placed in effect which
requires a check of the instrument each shift by the operators.
Since this information would be critical in case of an inadvertent
release, there are provisions in.the current emergency plan to
utilize other sources of information.
Additionally, an agreement
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with the National Oceanic and Atmospheric Administration to use informa-
tion from their tower near Erie, Colorado, has been developed and is
being circulated for final signatures.
Morever, Public Service Company
is negotiating with the National Weather Service to erect a new tower
adjacent to the site.
This tower is expected to be erected in approxi-
mately one year.
The inspector had no additional questions in this area.
8.
Technical Specification LC0 4.8.2(a) - Exceeded
On November 7, 1980, at 10:30 a.m. the licensee reported to the
Resident Inspector that the limits of Technical Specification
Limiting Condition for Operation (LCO) 4.8.2(a) for the concentra-
tion of tritium in an unrestricted area had been exceeded.
TS 4.8.2.(a) states that "The maximum instantaneous release rate of
radioactive liquid effluents from the site shall be such that the
concentration of radionuclides in the Cooling Tower blowdown water
discharge does not exceed the values specified in Table II, Column
2,10 CRR 20, Appendix B, for unrestricted areas."
Contrary to this requirement the licensee determined at 7:40 a.m. on
November 7, 1980, that the concentration of tritium in the Cooling
Tower water blowdown water discharge which was made on October 23,
1980, was 3.23E-3uci/cc exceeding the limit of 3.00E-3uci/cc stated
in Table II, Column 2, 10 CFR 20, Appendix 8, for unrestricted areas.
Tne specified release rate was 3.0 gpm to be followed by a system
water flush of 6000 gpm at the same release and diluting rate.
However,
due to apparent cingging in the building sump discharge line and
difficulty in establishing the release rate at 3.0 gpm to release
while flushing was apparently made at a release rate of 4.8 gpm and
resulted in the excessive release.
Interim corrective action was taken immediately to provide 1 change
to SR 5.8.2 bc-m to provide for establishment of the flow rate using
sump flow integrator F10-6216, periodically evaluating this flow rate
and to make adjustments as necessary to ensure an acceptable flow rate.
Additionally, the licensee is evaluating the possibility of installing
a bypass line around the oil separator which is now part of the liquid
waste release system.
The modification is deemed necessary since the
retention of the radioactive liquid waste in the oil separator is
the primary cause for potential releases in excess of limits if this
material is not flushed from the system at the same specified release
and dilution rate as the initial release.
Additional details on the release are available in the fourteen day
report, R0 80-67 dated November 20, 1980.
The inspector had no additional questions in this area.
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4.
Maintenance (Monthly)
The inspector reviewed records and observed work in progress to ascertain
that the following maintenance activities were being conducted in
accordance with approved procedures, Technical Specifications and appro-
priate Codes and Standards.
PTR 11-272 Repair Front Fan Bearing - ACM
CWP 80.63)
CN 868 ) For Monitoring Degradation of Charcoal Filters.
During a review of authorized Controlled Work Procedure (CWP) 80.63 and
Change Notice (CN) 868 the inspector determined that a device had been
installed correctly on filter F-7301 to monitor the degradation of the
the charcoal filters even though Page G-4 of the CN for this installa-
tion was known to indicate an incorrect installation.
Procedure G-2, FSV Procedure System, establishes the system of procedures
and procedure controls.
Section 4.5, Procedure Compliance, states in
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part that "All levels of FSV Station and Project personnel are responsible
for assuring compliance with authorized procedures, or for initiating
action to obtain appropriate procedure revisions if compliance is not
possible. . . ." Contrary to this requirement no appropriate revisions
(or deviations) for either CWP 80.63 or CN 868 were written and approved
although as stated previously Page G-4 of the CN was known to be incorrect
and required changes from the indicated installation.
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The inspector had no additional questions in this area.
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5.
Surveillance (Monthly)
Theinspectorreviewedallaspectsofsurveilkancetestinginvolving
safety-related systems.
The review included observation and review
relative to Technical Specif' .ation requirements.
The surveillance
tests reviewed and observed were:
SR 5.8.2.bc-m Radioactive Liquid Effluent System Instrumentation
Functional Test
SR 5.4.1.2.6.b-m Reheat Header Reactivity Test
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SR 5.4.1.3.5.b-m Circulator Orain Pressure Test
No items of noncompliance or deviations were identified.
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6.
Reoort Reviews
The inspector reviewed the following reports:
Monthly Operations Report - September 1980
Monthly Operating Information Report - October 1980
Monthly Operations Report - October 1980
No items of noncompliance were identified.
7.
Review of Plant Operations
The inspector reviewed one aspect of facility operations to determine if
it was being accomplished in accordance with regulatory requirements.
Reviewed was the licensee's review and audit program.
To determine
this the inspector attended a Plant Operating Review Committee (PORC)
meeting to verify membership, n eting frequency and that the licensee
followup was consistent with meeting decisions.
No items of noncompliance or deviations were identified.
8.
Inspection of TMI Task Action Plan Category "A" Requirements
A review and inspection of the licensee's action on the TMI Task Action
Plan Category "A" items was conducted at the plant site by NRR on
January 18 - 19, 1980, in conjunction with the Resident Inspector.
The
results of the review are contained in a March 31, 1980 letter from
T. P. Speis to J. K. Fuller which confirmed NRR acceptance of each item
or noted specific items that were not' applicable to' Fort St. Vrain.
Two
items, 2.1.8.c and 2.2.1.c (Improved Iodine Instrumentation and shift
and relief turnover procedures) were required by the letter to receive
additional inspection by the Resident for implementation prior to the
resumption of operation from the then current shutdown.
This was accom-
plished and reported in Inspection Report No. 50-267/8008.
No items of noncompliance or deviations were identified.
9.
Exit Interview
Exit interviews were conducted at the end of various segments of this
inspection with Mr. O. Warembourg (Manager, Nuclear Production) and/or
other members of the Public Service Company staff.
At the interviews,
the inspector aiscussed.the findings indicatei in the previous paragraphs.
The licensee acknowledged these findings.
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