ML20009G786
| ML20009G786 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/24/1981 |
| From: | Dickerson M, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20009G782 | List: |
| References | |
| 50-267-81-11, IEB-81-02, IEB-81-2, NUDOCS 8108040661 | |
| Download: ML20009G786 (10) | |
See also: IR 05000267/1981011
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U.S. NUCLEAR REGULATORY COMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT.
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REGION IV
IE Inspection Report: -50-267/81-11
License DPR-34
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Docket: 50-267
Licensee: .Public Service Ccmpany of Colorado
P. O. Box 840
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Denver, Colorado
80201
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Facility Name: Fort St. Vrain Nuclear Generation 5tation
Inspection at: Fort St. Vrain Site, Platteville, Colorado
Inspection Conductad: May 1-31, 1981
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Inspectors:
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M. W. Dickerson, Senior Resident Reactor Inspector
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G. L. Plumlee, III, Resident Reactor Inspector
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Approved By
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s T. F. ~Wes.,enhan, Chief,- Reactor Project Section No.1 '
Dat'e
Inspectio Summary
Inspection conducted on May 1-31, 1981 (Report: 50-267/81-11)
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Areas Inspected: Routine, announced inspection of surveillance; maintenance;
operationel safety verification; plant operations; preparation for refueling;
refueling activities; plant trips-safety system challenges; IE Bulletin Follow-
up; Followup on previous violations; and review of periodic and special reports.
The inspection involved 185 inspector-hours on site by two NRC inspectors.
Results: Within the ten areas inspected, two items of noncompliance were
identified (failure to adhere to Technical Specification limitations, para-
graph 3.A.; and fatiure to follow a procedural requirement, paragraph 3.B.).
8108040661 010624?
PDR ADOCK 05000267
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DETAILS
1.
Persons Contacted
L. Brey, QA Manager
R. Craun, Senior Engineer
W. Franek, Results Supervisor
J. Gahm, Supervisor Technical Services
W. Franklin, Shift Supervisor
E. Hill, Superintendent of Operation
W. Hillyard, Administrative Services Manager
D. Hood, Shift Supervisor
F. Mathie, Operation Manager
T. Orlin, Superintcadent QA Services
L. Singleton, Superintendent Operation QA
J. Vandyke, Shift Supervisor
. Wadas,-Training Supervisor
D. Warembourg, Manager Nuclear Production
The inspector also contacted other plant personnel including reactor
operators, maintenance men, electricians, technician; and administrative
personnel.
2.
Licensee Action on Previous Inspection Findings _
(Closed) Violation (50-267/8103-01): Liquid waste release resulting in
release of tritium to unrestricted area in excess of LC0 4.8.2(a) ii: nit
of 3.00E-3pCi/cc. The licensee modified the system to provide a bypass
around the oil separator for use during liquid releases.
(Closed) Violation (50-267/8103-02). Personnel failed to comply with
requirements of RWP. All personnel involved were reprimanded and
working foremen and supervisors have been instructed to emphasize
RWP requirements in job briefings prior to job commencement and to
continue such briefings throughout the job.
(Closed) Violatior. (50-267/8021-01): Two valves required to be sealed
in position wera missing locking devices.
A new system for assuring
valves required to " sealed has been placed in service and confirmed
by the NRC inspectw.
3.
Operational Safety Verification
The NRC inspector reviewed licensee activities 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 operation.
The
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review was conducted by direct obse'vation of activities, tours of
the facility, .interviaws and discussion with licensee personnel, independent
verification of safety system status and Limiting Conditions for Operations,
(LCO), 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:
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:
Monitoring Instrumentation
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Radiation Controls
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Housekeeping-
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Fluid Leaks
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Piping Vibrations
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Hanger / Seismic Restraints
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Clearance Tags
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Fire Hazards
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Control Room Manning
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The operability of selected systems or portions of systems were verified
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by walkdown of the accessible portions.
Observed was the feeawater
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heater vent and drain system.
Procedures were also eviewed and imple-
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537 and 540. The
releases appeared to have been made in a satisfactory manner.
No violations or deviations were identified.
A.
Technical Specification LC0 4.8.2(a) - Exceeded
On May 14,1981, at 1:00 p.m., the licensee reported to the
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Re;;ident Inspector that the limits of Technical Specification
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Limiting Condition for Operation (LCO) 4.8.2(a) for the concen-
tration of tritium in an unrestricted area had been exceeded on
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May 12, 1981. TS 4.8.2(a) states that "The maximum instantaneous
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release rate of radioactive liquid effluents from the site shall-
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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 CFR Part 20, Appendix B, for unrestricted
areas."
The specified release rate was 9.0 gpm at a dilution rate of
circulation water blowdown of 2,000 gpm.
A subsequent analysis
indicated an average release rate of 9.2 gpm and an average
dilution rate of 2,496 gpm.
However, a special test was perfonned
on release No. 460 to track liquid waste concentrations in the
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unrestricted area during the course of the release.
This con-
sisted of sampling on an hourly basis throughout the release.
The analysis run on the sample taken at 1:00 p.m. on May 12, 1981,
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25 minutes after start of the release indicated a concentration
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of tritium of 3.55E-3pCi/cc, in excess of the 3.00E-3pCi/cc speci-
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fied by LC0 4.8.2(a).
The cause has been attributed to an interruption of blowdown at
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12:55 p.m. for approximately two minutes which also caused automatic
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trip of the liquid waste transfer pump and closing of HV-6216,
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the liquid waste system isolation valve.
This allowed draining
of the highly concentrated liquid waste in the piping system
downstream of HV-6212 and resulted in an above limits concentration.
The licensee is considering relocating another isolation valve
at the junction of the liquid waste discharge line and the
circulating water blowdowr. line to isolate the dead leg until
conditions are acceptable for release.
Details on the release are available in the 14-day License Event
Report 81-036 dated May 27, 1981.
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Additionally, this matter was discussed with the licensee who was
informed that. failure to meet the requirements of the Technical
Specification was a violation (8111-01).
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The inspector had no additional questions in this area.
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'B.
Systems Abnomalities Book
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During a review of the Systems _ Abnormalities Book on flay 19, 1981,
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the NRC inspector noted two deviation foms which were initialed
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by a reactor operator as " equipment normal." However, a check of
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the System Status Tags Nos. 2196 and 2249, assigned respectively
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to each of the two forms, showed them to still be in place on the
equipment specified on the fonns for tagging.
System Status Tag 2196 was assigned to Loop 1 Steam Water Dump
Valves HV-2215 V-2213 and HS-2215.
System Status Tag 2249 was
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assigned to the Backup Bearing Water System Valve V-21453, on
HC-21417/48 and on HS-21331. A check of these tags by the
NRC inspector showed that they were still in place.
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Procedure P-2, " Equipment Clearance and Operation Deviation,"
paragraph 4.2.13, instructs the reactor operator to remove _the .
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" Operation Deviation Sheet" from the " Systems Abnormalities Book"
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and initial the form to indicate the system is normal and para-
graph 4.2.14 states that he is to verify all subtags listed on
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the deviation form have been returned.
Additionally, Operations
Order 81-01 requires that "the responsible operator will initial
the deviation form as indicated when the equipment is normal.
Reactor operator will check accountability of subtags on the
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deviation form, and transfer all paper and tags to shift supervisor."
The review of the deviation forms by the NRC inspector indicated
that for. System Status Tags 2196, the equipment had been altered
on December 19, 1980, and that the equipment was returned to normal
on December 16, 1980 (note inconsistency in dates).
For System
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Status Tags 2249, the tag indicated that the equipment was altered
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on April 18, 1981, and that the equipment was returned to normal on
April 30, 1981. A check later in the day on May 19, 1981, indicated
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that both deviation forms had been initialed to indicate equipment
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altered with a new date of May 19, 1981.
The matter was discussed with the licensee who was informed that
failure to comply with the procedural requirements was a violation
(8111-02).
The inspector had no additional questions in this area.
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C.
High Vibration Turbine Trip
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(1) Activities During Event
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A high vibration turbine trip occurred on May 13, 1981,'at-
1:34 p.m. while the reactor was operating at approximately.
79% reactor power.
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When the turbine tripped, the hot reheat bypass valves opened.
However, the low condensate header pressure switch sensed less
than 234 psig pressure'and in a few seconds tripped the hot
reheat bypass valves closed. This plus an unexplained time lag
in the opening of the hot reheat electromatics caused the turbine
exhaust pressure to increase rapidly.
This caused both circulators
in Loop 2 to trip on drain malfunction resulting in an Tutomatic
Loop 2 shutdown.
The rapidly changing reheat pressures created instabilities
in the 150 pound steam header. As a result, the feedwater flow
from the steam driven feed pumps began oscillating,
Compounding
the oscillating feedwater flow problem was a problem with the feed-
water flow rate limiter which ramped down at a rate inconsistent
with the setting of 0.25%/second.
The recctor operator placed both header pressure controllers
in manual position to eliminate the 150 pound header instabilities.
The pressure stabilized but at low pressure, which caused the
two steam driven feedwater pumps to go into the recirculating
mode. The loss of the two steam driven feedwater pumps caused
the flow from the motor driven feed pump to increase.
Adjust-
ments to the controller helped stabilize the feedwater flow.
However, at this time the auxiliary boiler was approaching
its high pressure trip point and the pressure was manually
relieved. This caused the pressure in the 150 pound header
to increase sharply and in turn caused the feedwater from
the steam driven feed pump to increase sharply.
This sharp
increase in feedwater flow resulted in tripping both Loop 1
circulators on low programmed speed and the reactor scramed
from about 17% reactor power on a two loop trouble scram. The
ISS switch was then placed in the " low power" position and
"B" circulator restarted.
This ended a one minute loss of
forced circulation.
"A" circulator was restarted two minutes
later.
An inspection of the turbine-generator has revealed no damage
other than loose integral covers on each of the two sixteenth
stages of the low pressure turbine.
Small portions of five of
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the lugs holding the : overs in place were missing.
Additionally,
four diaphragms, two for each of twelfth and thirteenth stages
of the low pressure stages were loose. At the end of the report
period the licensee was preparing to repair and reassemble
the turbine.
(2) Radiological Considerations
At approximately 1:40 p.m. on May 13, 1981, activity was noted to
be increasing on all of the high pressure separator monitors.
This
was attributed to Reactor Coolant being forced down the shaft of
one or more of the helium circulators due to a buffer system
upset which was caused by the circulator trips.
Air sampling in the Reactor Building was initiated along with
constant monitoring of the Reactor Building exhaust stack.
At 2:01 p.m. air samples detected activity in the Reactor
Building of 1.7E-9 mci /cc and acces' control to the Reactor
Building was established. At 2:33 p.m. the air sampling
indicated an increase to 4.5E-9 mci /cc.
All persons were
removed from the Reaccor Building and a respiratory require-
ment for entry was established.
By 3:01 p.m. the activity
level had decreased to 2.1E-9 mci /cc and general access
was established.
During this period of time no personnel overexposures
occurred nor did any of the stack monitors indicate any
release of measurable radioactivity from the Reactor Building.
No violations or deviations were identified.
4.
Surveillance (Monthly)
The NRC inspector reviewed a.il aspects of surveillance testing involving
safety-related systems. The review included observation and review
relative to Technical Specification requirements.
The surveillance
tests reviewed and observed were:
SR 5.4.1.2.1.C-M Steam Pipe Rupture (Pipe Cavity) Test
SR 5.4.1.2.2.C-M Steam Pipe Rupture (under PCRV) Test
SR 5.8.1.abc-M Radioactive Gaseous Effluent System Test (Release #537)
SR 5.4.1.1.4.b-M Linear Power Channel Scram Test
SR 5.8.1.abc-M Radioactive Gaseous Effluent System Test (Release #540)
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The NRC inspector noted that during the performance on May 14, 1981,
- of SR ~5.4.1.1.4b-M,I .e low level trip for channel 3. LLT-2 which
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should trip at 1.93 O 05V corresponding to 6% reactor power actually
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tripped at 2.112v.
Immediate corrective action was taken by the licensee
to recalibrate the power range channel.
No-violations or deviations were identified.
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5.
Maintenance (Monthly)
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The NRC 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
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aopropriate Codes and Standards.
PRT 4-382 Repair Hydraulic oil leak on HV-2254 in accordance with
MP 91.10, Hydraulic Operator Relief Valve Replacement
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PRT 4-383 Repair Hydraulic oil leak on HV-2292 in accordance with
MP 91.10
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PRT 5-54
Repair Hydraulic oil leak on FV-2206
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PTR 5-143 Noise in LP section after turbine trip and during coast down
PTR 5-286 Remove and Replace "B" Circulator C-2102 in accordance with
MP.21-15, Helium Circulator Change Out Procedure
PM 21.20
Quarterly Inspection of Helium Recovery Compressor C-2107S
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"B" Rix
P!P - 4
Refueling
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h!P - 7
Non-Routine Fuel Reflector Handling
No violations or deviations were identified.
6.
Refueling Activities
The NRC inspector reviewed the licensee's Refueling Procedure FHP-4
and the procedure for Non-Routine Fuel Reflector Handling,.FHP-7, to
verify technical adequacy and procedure canpletion prior to handling of
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fuel in the core.
The NRC inspector r.ct.ed that Task 78 of FHP-4 trans-
ferring RCD's between FSC and FHM, as written requires transferring the
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region constraint devices from the fuel storage cask to the fuel handling
machine.
The actual transfer should be from the fuel handling machine
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to the fuel storage cask.
The NRC inspector also noted in Task 208 of
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FHP-4 that a data tape number was incomplete.
The licensee stated that
deviations to the procedure where necessary would be written and approved
prior to performance of the specific evolution.
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The NRC inspector also verified ventilation requirements in the fuel
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storage areas and that the licensee was maintaining good housekeeping
in the refueling area.
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No violations or deviations were identified.
7.
Report Reviews
The NRC inspector reviewed the following reports for content, reporting
requirements and adequacy:
Monthly Operating Information Report, March 1981
Monthly Operations Report, March 1981
No violations or deviations were identified.
8.
IE Bulletin
The NRC inspector verified by record review, observation and discussion
with the licensee, the action .aken in response to IE Bulletins.
The following Bulletin was reviewed:
81-02 - Failure of Gate Valves to Close Against Differential Pressure.
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The licensee has determined that neither the Borg-Warner or Westinghouse
valves in question have been purchased or installed at Fort St. Vrain.
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No violations or deviations were identified.
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9.
Review of Plant Operations
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The NRC inspector reviewed aspects of facility operations to determine if
they were being accomplished in accordance with regulatory requirements.
A.
Procurement and Storage
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The NRC inspector reviewed the following purchase orders, receipt
records, storage and certification records. Additionally, observa-
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tion as made of the receipt inspection for two of the purchase orders
and observed several items in storage.
P0 N3128 Repair of P-9105X
P0 N3443B Cage, Equal Percentage, for Fisher Valves
S/N 6374792
P0 N2951 Pipe 2h" CS
Pipe 3" CR. Molly
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P0 N3263 Relief Valve
P0 N3327 22 AWG 3 twisted pr. shielded
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The NRC inspector questioned the disposition cf NCR 80-27 which
indicated a hold point for notification to QA prior to disassembly
was not a quality hold point.
This'was resolved.at the time of
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discussion and_NCR 80-27A was issued which requires the :aotor to
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be insulation resistance tested prior to installation and verifica-
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tion of motor operability; e.g., excessive noise, vibration, over-
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heating, and pump pressure for P-9105X (P0 N3128).
The inspector had no additionai questions in this area.
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B.
Review and Audit
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The NRC inspector attended a Plant Operating Committee Meeting No. 411
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to determine compliance with the Technical Specifications and other
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regulatory requirements.
Additionally, the NRC inspector observed
portions of QA Audit No. QAA 601-81-01 of the Water Chemistry and
Radiochemistry areas.
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C.
Security
The NRC inspector attended a training lecture and verified that
lesson plan objectives and the schedule were-being met.
Additionally,
the NRC inspector observed that acceptable scores were achieved by
several individuals during the conduct of weapons qualification
testing.
D.
The NRC inspector verified that the licensee's on site arrangements
for medical support and treatment are implemented as described in the
The NRC inspector also witnessed a training session
for emergency preparation in which the control room cperators were
required to wear fresh air masks.
The records of licensee personnel
were also reviewed for emergency training.
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No violations or deviations were identified.
10.
Exit Interview
Exit interviews were conducted at the end of various segments of this
inspection with Mr. D. Warembourg, Manager, Nuclear Production, and/or
other members of the Public Service Company staff.
At the interviews,
the inspector discussed the findings indicated in the previous paragraphs.
The licensee acknowledged these findings.
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