IR 05000267/1980025
| ML19345G341 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/22/1981 |
| From: | Dickerson M, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19345G338 | List: |
| References | |
| 50-267-80-25, NUDOCS 8103180443 | |
| Download: ML19345G341 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
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IE Inspection Report No. 50-267/80-25 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 Generation Station Inspection at:
Fort St. Vrain Site, Platteville, Colorado Inspection Conducted:
December 1-31, 1980 x
Inspector;,:
?-, 6. ' [4 M
/- 2 2 -N M. W. Dickerson, Senior Resident Reactor Incoector Date
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G. L. Plumlee III, Resident Reactor Inspfector Date Approved by:
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T. F. Westerman, Chief. Reactor Projects Section No.1 Date
j Inspection Summary Inspection conducted on December 1-31, 1980 (Recort No. 50-267/80-25)
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Areas Inspected:
Routine, announced inspection of review of Bulletins / Circulars;
surveillance; operational safety verification; and review of periodic and special reports.
The inspection involved 75 inspector-hours on site by three (3) NRC inspectors.
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Results: Within the four (4) areas inspected, one violation was identified (failure to perform a surveillance within the specified time period, I
Paragraph 2C).
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DETAILS 1.
Persons Contacted L. Brey, QA Manager W. Franek, Results Supervisor W. Franklin, Shift Supervisor J. Gamm, Supervisor Technical Services E. Hill, Superintendent of Operatica W. Hillyard, Administrative Services Manager D. Hood, Shift Supervisor F. Mathie, Operations Manager T. Orlin, Superintendent Operations QA G. Reigel, Shift Supervisor J. Van Dyke, Shift Supervisor D. Warembourg, Manager, Nuclear Production The inspector also contacted other plant personnel including reactor operators, maintenance men, electricians, technicians and administrative personnel.
2.
Operational Safety Verification The 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 review was con-ducted by direct observation of activities, tours of the facility, inter-views and discussion with licensee personnel, independent verification
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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.
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 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:
Monitoiing 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 by walkdown of the accessible portions.
Observed were the Emergency Diesel Generator System and the Fuel Storage Auxiliary System.
Procedures were also reviewed and implementation observed for Liquid Waste Release
- 424.
The release appeared to have been made in a satisfactory manner.
A.
Plant Tour During a plant tour on December 18, 1980, it was noted that:
Pressure instrument PDIS 21330 (Helium Circulator "D" Steam Turbine Trip) was missing an environmental protection cover.
This is con-sidered an open item.
(8025-01)
There was a leak from flange FE 2186.
The inspector was informed that this was "D" circulator bearing water system and the leak will be fixed during the next outage.
The Moisture Monitor Instrument Penetration Outer Covers were removed.
The inspector informed the licensee that although these covers are tertiary and do not appear to be required by Technical Specifications,
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the FSAR describes normal operation with these covers in place.
The inspector stated that if they are to be left removed, a 10 CFR 50.59 Safe'.y Analysis should be performed.
This is seen item (8025-02)
No viviations or deviations were identified in ti.is area.
B.
Control Room Observations On December 24, 1980, the inspector performea a review of the
" System Abnormalities Book." During this raview it was determined that the eight " Standard Clearance Points" forms listed below did not have approval signatures or dates.
Number Systems Component
1171
LV-3250-1 719
HV-5355 834
G-7204 630
FE-4198-P 634-
5-7537 705
S-7546 1170
HV-5133 788
A-2309-5 The inspector also determined that all of the above had been issued clearance tags which did contain signatures and dates and that none were safety related.
However, during a review of procedure P-2
" Equipment Clearances and Operation Deviations" and discussion with operators, shift supervisors and plant management it was established that the' procedure had apparently been written for standard clearances l
with standard clearance points and did not cover the cases where
standard clearance points for either safety or non-safety related
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components might be used, such as the single point clearances enumerated previously.
As a result of the discussion plant manage--
ment indicated they would revise procedure P-2 to clarify the use of non-standard clearance points and the requirement for approving clearance' point forms.
This is an unresolved item (8025-03).
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same. clearances had been approved and dated when the inspector made a recheck on December. 29, 1980.
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No violations or deviations were identified in this area.
C.
Walkdown of Fuel Storage Facility Auxiliary System During a walkdown of the Fuel Storage Facility, Auxiliary System on December 22, 1980, it was determined that the annual technical specification surveillance required by SR 5.7.2(b) had not been performed since August 20, 1979, a period of 16 months.
A check of the fuel storage wells determined that the only fuel storage well containing fuel during this period was number 5 and that it contained 10 elements.
Discussion with representatives of the licensee indicated that this matter had also been disclosed during a Public Service Company Audit on December 18, 1980, and that corrective action was in progress.
This was confirmed by a review of QA audit No. 901-80-01.
A review by the inspector of SR 5.7.2b.A also showed that the surveillance was completed on December 23, 1980.
Technical Specification SR 5.7.2(b) states that "the fuel storage facility cooling system flow indicators, and flow and temperature alarms shall be calibrated and functionally tested annually." How-ever, as noted previously, a period of 16 months had elapsed since the surveillance was performed on August 28, 1980, and was contrary to the requirements of the technical specification.
This is a violation (8025-04).
Since the licensee had previously identified this violation and had completed the corrective action prior to the completion of this inspection, no response is required of the licensee.
The inspector found this to be an isolated occurrence.
The inspector found that the personnel involved have been given additional guidance to pre-vent recurrence.
The licensee is also establishing computer track-ing of surveillance testing.
The inspector had no additional questions in this area.
D.
Lineup Check of Emergency Diesel Generators The inspector performed a lineup check of selected portions of the Emergency Diesel Generators.
The pre-operational valve list of standard operation procedures.50P 92-04 was utilized to verify proper valve alignment.
Switch positions were also observed in the Emergency Diesel Generator Room.
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The inspector had the following findings:
There were several valves (vent and isolation valves) such as those
.to PS-9203 which were not tagged or la~eled while others such as o
V-92137 to PS-9208 and'V-92138 to PS-9207 were labeled.
Moreover, the drawing for this system P&ID 92-2 in a note referring to Detail B states that none of the valves are numbered.
This matter is considered to be an unresolved item (8025-05).
No violations or deviations were identified in this area.
3.
Surveillance (Monthly)
The inspector reviewed all 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 5.4.1.2.7 c-M Superheat Header Temperature Test SR 5.4.1.2.4 a-M Circulator IC and ID Tripped Test SR 5.4.1.3.3 b-M Circulator Bearing Water Pressure Test During observation of SR 5.4.1.3.3 b-M the inspector noted that the DVM (#M3147) being used to determine minimum voltage was a brand new instru-ment and no calibration data was available with the exception of a manufacturers certification.
This item is considered open.
(8025-06)
There were no violations or deviations identified.
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'IE Bulletin.s.
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The inspectors 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:
80-11 Masonary Wall Design.
The licensee had identified the subject walls at Fort St. Vrain, had re evaluated the design adecuacy and had submitted this information to the NRC.
80-21 Valve Yokes Supplied By Malcom Foundry Company, Inc.
The licensee had determined that valve yoke castings supplied-by Malcom Foundry had not been used at Fort St. Vrain.
80-23 Failures of Solenoid Valves Manufactured by Valcor Engineering Corporation.
The licensee had determineo that solenoid >alves
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manufactured by Valcor Engineering Corporation had not been installed at Fort St. Vrain.
80-24 Prevention of Damage Oue to Water Leakage Inside Containment (October 17, 1980, Indian Point 2 Event).
Determined not applicable to Fort St. Vrain since the secondary containment was not similiar to those described in the bulletin.
No violations or deviations were identified.
5.
Report Reviews The inspectors reviewed the following reports for content, reporting requirements, and adequacy:
Seventeenth Startup Report, August 23, 1980 through November 22, 1980.
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Report of Changes Tests and Experiments, January 1, 1979 through
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December 31, 1979.
Monthly Operating Information Report - November 1980.
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No violations or deviations were identified.
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Unresolved Items
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Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or deviations.
Two unresolved items (8025-03, 8025-05) disclosed during the inspection are discussed in Paragraphs 2B and 20 respectively.
7.
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.