ML19318A710
| ML19318A710 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/05/1980 |
| From: | Collins R, Dickerson M, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19318A704 | List: |
| References | |
| 50-267-80-08, 50-267-80-8, NUDOCS 8006240055 | |
| Download: ML19318A710 (6) | |
See also: IR 05000267/1980008
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U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
IE Inspection Report No. 50-267/80-08
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
Inspection at:
Fort St. Vrain Site, Platteville, Colorado
Inspection Conducted: April 1-30, 1980
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Inspectors:
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M. W. Dickerson, Senior Resident Reactor Inspector
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R. E. Collins, Resident Reactor Inipector
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Approved By:
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T. F. Westerman, Chief, Reactor Projects Section
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Inspection Summary
Inspection April 1-30, 1980 (Report No. 50-267/80-08)
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Areas' Inspected: Routine, announced inspection of Review of Previous Items of
Noncompliance; Surveillance; Maintenance; Operational Safety Verification; and
Review of Bulletins / Circulars. The inspection involved 169 inspector-hours
on-site by two (2) NRC inspectors.
Results: Within the five (5) areas inspected, one item of noncompliance was
identified (Infraction - Failure to meet Technical Specification for Diesel
Generator Day Tank Levels, Paragraph 3) .
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DETAILS
1. .
Persons Contacted
L. Brey, QA Manager
W. Craine, Maintenance Supervisor
W. Franek, Results Supervisor
W.. Franklin, Shift Supervisor
J. Gamm, Supervisor Technical Services
E.-Hill, Operations Superintendent
F. Mathie, Operations Manager-
J.' Van Dyke, Shift Supervisor
D. Waresbourg, Manager Nuclear Production
-The inspectors also contacted other plant personnel including reactor
operators, maintenance men, electricians, technicians and administrative
personnel.
2.
Li,censee Action on Previous Inspection Findings
(Closed) Item of Noncompliance (50-267/8001): Failure to Maintain
Deisel Generator Day Tanks at required level during power operation.
The
inspector reviewed the licensee's corrective action outlined in PSC
Letter P-80050 dated March 17, 1980.
(Closed) Item of Deviation (50-267/8001): Failure to Warm-Up Test instru-
ments in accordance with manufacturer's recommendations. Tags have been
placed on the instruments indicating the warm-up requirement.
(Closed) Item of Noncompliance (50-267/8002-1): Test equipment not
identified on records of surveillance test 504.1.1.4c-d for dates of
January 5-8, 1980. The data sheet now used for the surveillance list
has been-revised to include a space for daily recording of the test
instrument used.
(Closed) Item of Noncompliance (50-267/8002-2): Calibrations performed
utilizing outdated procedure revisions. The inspector reviewed the
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licensee's corrective action as outlined in PSC letter P-80077 dated
April 11, 1980. Responsibility for this action has been assigned to the
Scheduling Supervisor.
Previous surveillance tests performed to outdated
test procedures were verified by the inspector to have since been performed
using the latest procedures.
3.
. Operational Safety Verification
The inspector reviewed licensee activities to ascertain that the facility
is being operated safely and in conformance with regulatory requirements,
and that the licensee's management control system is effectively dis-
. charging its responsibilities for continued safe operation.
The review
was conducted by direct observation of activities, tours of the facility,
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interviews and discussions with licensee personnel, independent verifi-
cation of safety system status and limiting conditions 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:
Shift Supervisor Logs
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Reactor Operator Logs
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Technical Specification Compliance Log
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Operating 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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Selective Valve Lineups
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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 Vibration
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Hanger / Seismic Restraints
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Clearance Tags
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Control Room Manning
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The operability of selected systems or portions of systems were verified
by walkdown of the accessible portions.
The observations were for the:
Reserve Shutdown System
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PCRV Safety-Valves
PCRV Secondary Closures
Procedures were also reviewed and observations were made for the drawing
of samples and performance of analysis associated with liquid waste
release No. 384 and gas waste release No. 432. The samples drawn and
analyzed associated with the liquid waste release were RC 15361 and
RC 15362. The samples drawn and analyzed associated with the gas
waste release were RC 15370 (Grab Sample) and RC 15369 (Tritium Analysis).
All were well below 10 CFR 20 release limits.
During a tour of the facility on April 2,1980, with the reactor at 57%
power, the inspector observed that both diesel generator day tank levels
were at approximately.385 gallons, well below that required by T/S
LCO 4.6.1 which' states in part that:
. . . Both the diesel-generator
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sets are operable, including the following:
. 500 gallons in each day
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tank . . . ." Moreover, an Operations Order reissued April 1,1980,
by the Superintendent of Operations requires that the day tanks be filled
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after any run of the diesel generators. The latter requirement was
apparently not effective in' maintaining the required level as both
diesel generators had been run on March 31, 1980, and the tanks had
appsrently not been filled after the run.
The failure to comply with the T/S requirement as indicated above was
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discussed with the licensee who was informed that this was an apparent
item of noncompliance for failure to adhere to the Technical Specifi-
cation ~ requirements.
The inspector had no additional questions in this area.
4.
Maintenance
The inspector reviewed records and observed work in progress to ascertain
that maintenance of activities are being conducted in accordance with
approved procedures, Technical Specifications and appropriate codes and
standards.
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1The following. maintenance-activities were reviewed:
PTR 10-339 Repair steam valve packing on V-75640
.PTR 3-463 . Troubleshoot and repair 'B' Instrument Air Compressor
PMR-1-M
Buffer - Mid Buffer Operability Check
'During observation of PMR-1-M, Buffer - Mid Buffer Operability Check, the
inspector noted that the radios in use between the control room and
reactor building caused an upset in the buffer helium supply to Helium
Circulator 1A.-
The upset occurred only when the radio transmitter in the
' reactor building was keyed.
It could not be determined at the time
whether indication or actual valve movement was affected. The licensee
indicated that this matter will be investigated.
This will remain as
an unresolved item '(80-08/1).
Following IE inspection report No. 50-267/80-06, there were three mainte-
nance activities that were not completed at that time. The following
activities.were completed and closed out:
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PTR3-76 Repair Expansion Joint on Pump P-4101 (Circulating Water
Tower Pump)
PTR3-377 Emergency Water Booster Pump Mechanical Seal Repair
Auxiliary Boiler Tub Replacement, PTR3-261, is still in progress.
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No items of noncompliance or deviations were identified.
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Surveillance
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The inspector reviewed all' aspects of surveillance testing involving
safety-related systems.
The review included observation and review
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_ relative to Technical Specification requirements.
The surveillance tests
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reviewed and observed were:
SR 5.4.1.3.5.b-M Circulator Drain Pressure Test
SR 5.4.1.2.6.b-H Reheat Header Activity Test
SR 5.4.1.1.6.c-R Primary Coolant Moisture Scrim Calibration
No items of noncompliance or deviations were identified.
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6.
IE Bulletins / Circulars
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The inspector verified by record review, observation and discussion with
representatives of the. licensee, the action taken in response to IE
Bulletins / Circulars.
The following Circulars were reviewed:
80-07
Problems with HPCI Turbine Oil System.
Not applicable to
Fort Saint Vrain.
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The following Bulletins were reviewed-
79-03A-
Longitudinal Weld Defects in ASMI SA-312, Type 304 Stain-
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less Steel Pipe. None in use at Fort Saint Vrain.
80-03
Loss of Charcoal from Standard Type II, 2 inch, Tray
Adsorber Cells.
Inspection found no degradation or
bypassing nor loss of charcoal.
80-06
Engineered Feature (ESF) Reset Controls. Not applicable
to Fort Saint Vrain.
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7.
- Category A" Lessons Learned Implementation
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Two items, 2.1.8.c Improved Iodine Instrumentation and 2.2.1.c Shift and
Relief Turnover procedures were to be verified as required by the enclo-
sure (dated March 20, 1980) to the letter from T. P. Spies (NRR) to
J. K. Fuller (PSC).
The enclosure required that procedures required by
2.1.8.c be in place prior to the resumption of power and that for 2.2.1.c
the adequacy of checklists and logs be determined. Each of these items
were verified prior to the. resumption of power following the staff's
visit to the site on January 18-19, 1980.
8.
Unresolved Items
Unresolved items are matters about which more information is required
in order to ascertain whether they are acceptable items, items of non-
compliance, or-' deviations.
One unresolved item disclosed during the
inspection is discussed in paragraph 4.
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9.
Exit Interviews
Exit-interviews were conducted at the end of various segnents 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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