IR 05000267/1982011
| ML20054M411 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/16/1982 |
| From: | Dickerson M, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20054M404 | List: |
| References | |
| 50-267-82-11, NUDOCS 8207130161 | |
| Download: ML20054M411 (7) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-267/82-11 License: DPR-34 Docket:
50-267 Category: 5 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: May 1-31, 1982 Inspectors:
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Mu m 4-/o- #2-M. W. Dickerson, Senior Resident Reactor Inspector Date
~bn f-/c 42, G. L. Plumlee III, Resident Reactor Inspector Date Approved:
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[-/( -3 ~2-T. F. Westerm5t(,' Chief, Reactor Project Section A Date Inspection Summary
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Inspection conducted May 1-31, 1982 (Report: 50-267/82-11)
l Areas Inspected:
Routine, announced inspection of Surveillance; Maintenance; i
Operational Safety Verification; Follow Up of Previous Inspection Findings; Review of Plant Operations; NRC Circular Followup; Review of Licensee Event
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Reports; and Review of Periodic and Special Reports. The inspection involved 177 inspection-hours onsite by two NRC inspectors.
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Results: Within the eight areas inspected, no violations or deviations were
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identified.
i 8207130161 820628 PDR ADOCK 05000267 O
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DETAILS 1.
Persons Contacted M. Block, Superintendent of Operations T. Borst, Radiation Protection Manager B. Burchfield, Results Engineering Supervisor W. Craine, Superintendent of Maintenance M. Deniston, Shift Supervisor D. Evans, Shift Supervisor W. Franek, Nuclear Site Engineering Manager W. Franklin, Shift Supervisor C. Fuller, Technical Services Engineering Supervisor J. Gahm, QA Manager E. Hill, Operations Manager D. Hood, Shift Supervisor J. Liebelt, Senior Maintenance Supervisor M. McBride, Technical / Administrative Services Manager H. O'Hagan, Shift Supervisor G. Reigel, Shift Supervisor L. Singleton, Superintendent Operations QA J. Van Dyke, Shift Supervisor D. Warembourg, Manager Nuclear Production R. Webb, Maintenance Supervisor W. Woodard, Health Physicist The NRC inspectors also contacted other plant personnel including reactor operators, maintenance men, electricians, technicians, and administrative personnel.
2.
Licensee Action on Previous Inspection Findings (Closed) Violation (50-267/8205-01) Inadvertent Radioactive Liquid Waste Release. The surveillance procedure used for liquid waste releases, SR 5.8.2bc-M, has been modified to include an independent valve position verification.
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 review was conducted by direct observation of activities, tours of the facility, interviews and discussion with licensee personnel, independent verification of safety system status and limiting condition for operations, and review of facility records.
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Included in the inspection were observation of control room activities, review of operational logs, records, and tours of accessible areas.
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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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Operations Deviations Reports
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Clearance Log
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Temporary Configuration Reports
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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
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Radiation Controls
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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.
The NRC inspector verified the operability of the Decontamination and Radioactive Liquid Waste Systems.
No problems were identified during the system walkdowns.
Procedures were also reviewed and implementation observed for Gaseous Effluent Releases No. 618 and 623 and Liquid Waste Release No. 553.
The releases appeared to have been made in a satisfactory manner.
On May 21, 1982, the NRC inspector monitored an unplanned release of radioactive gases that resulted from the inadvertent closure of V-63232, C-6301/6301S Discharge Tie Line, which occurred at approximately 1:22 p.m.
MDT. This event was subsequently reported to the NRC as an Unusual Event at 3:15 p.m. MDT, resulting in the issuance of PNO-IV-82-19 by Region IV on May 24, 1982.
The reactor building was administrative 1y evacuated of all nonessential personnel at 1:25 p.m. MDT, and at 3:45 p.m. MDT, unlimited access to the reactor building was authorized.
This event resulted in three workers receiving minor contamination and a release out of the plant stack of approximately 52 microcuries of Cs 138 and Rb 88, whose MPC is 1 E-6 microcuries per milliliter.
The maximum activity indicated inside the reactor building was reported at 1:40 p.m. MDT, to be 5.6 E-7 microcuries per milliliter.
The NRC inspector determined that this event was apparently caused from a lack of the same type of controls that the licensee places on safety-related activities.
System 63, " Radioactive Gas Waste System," is classified by the licensee as nonsafety-related and is not afforded the same controls as does a safety-related system.
As a result, the NRC inspector determined that the failure to use a procedure to vent the "A" Gas Waste Compressor Containment Tank had resulted in the inadvertent closure of the cross connect valve V-63232 and the opening of a valve which was under clearance control to be in the shut position.
This resulted in the release of gaseous radioactivity through the manhole of the containment tank and into the reactor building.
The inspector determined that the licensee does not have a procedure for venting the gas waste compressor containment tanks.
The NRC inspector informed the licensee of the above problems.
The licensee stated that the issuance of a newly approved administrative procedure for nonsafety-related maintenance work control would resolve the problems noted above.
The NRC inspector has no further questions in this area.
On June 3, 1982, G. L. Madsen met with 3. R. Lee, Vice President Electric Production to discuss the Region IV concerns regarding past radioactive gas releases which were attributable to personnel error or lack of control for activities on systems other than those normally classified as safety-related.
Mr. Lee indicated a similar concern and that corrective actions were being considered.
No violations or deviations were identified.
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The NRC inspektor reviewed all astscts of surveillance testing j'* 4
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involving safety-related systems. s.The review included observation
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and review relative to Technicd) $becification requirements.
The
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surveillance tests reviewed and observe,d were:
i SR 5.8.2b'c-M Radio' active lit [uid Effluent Svstem Instrumentation
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rdrctional Test (Reiene Ho. 553)
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SR 5.8.labcjM Radioactive Gaseous Effluent Syst'em Test
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(Releases No. 618 and 623)/,s
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,,SR 5.4.1.3.1.'c-M Circuldtor Speed (Steam and Water) Test ',.
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SR 5-3.16.a-M PCRV C1'4sure leskage Determination,
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'. The NR,dtain th3t' the folloWiC' inspector /rgkievpd records and o
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to ase ng maintenance activities were being
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condu'cledi@accordancp',with'approvedprocedures.'luchnical
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Specifit.aticy,, 'and appropriate Cedes and Standafds. The following
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N mainrenanrMctivities w,ere re, viewed and obseeved:
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,-CN'1495/CWPU?-68 Cap Tubb4FT2'rmnd Instail, Sample Lines f
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s Calibrating 480 V ITE K Line Bre/Fdket"Ovesyrre1t Trip
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Devices for N 9213, K-9202 "B" Diesel, Gerydator Breaker
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PTR 5-2p.
Replace Worn Coupling on P-910lX in Accordance With
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MP-201, " System 91 Pump Coupling Maintenance and Lubrication"
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PM 92.,]0
" Inspection and Preventivy Maintenance of Caterpiller Diesel-Emergency Generator Units." Preventive Maintenance
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on "A" Diesel. Generator Set
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. CN 1242 l/CWP 81-271 Provide Airbo&iie Radiation Monitoring in the
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Technical Support BuO ding RIT,;7937, RIT-7937-1,
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' RIT-7936, and RT,T-79364 '
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6.
Review of Plant Operations The NRC inspector reviewed one aspect of facility operations to determine if it was being accomplished in accordance with regulatory requirements.
Emergency Preparedness (Training)
On May 21, 1982, the NRC inspector verified by discussions and attendance at a training session for plant personnel concerning the Technical Support Center that the licensee's training program for emergency preparedness is being implemented.
No violations or deviations were identified.
7.
IE Circular The NRC inspector verified by record review, observation,and discussion with the licensee, the action taken in response to IE Circulars.
The following Circular was reviewed:
81-12 Inadequate Periodic Test Procedure of PWR Protection System.
Fort St. Vrain does not utilize undervoltage relays on their D. C. Systems.
Fort St. Vrain uses overcurrent devices only.
No violations or deviations were identified.
8.
Report Reviews The NRC inspector reviewed the following reports for content, reporting requirements, and adequacy:
Monthly Operating Information Report, April 1982 Monthly Operations Report, April 1982 No violations or deviations were identified.
9.
Review of Licensee Event Reports The NRC inspector reviewed licensee event reporting activities to verify that they were in accordance with Technical Specification, Section 7, including identification details corrective action, review,and evaluation of aspects relative to operations and accuracy of reportin.
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The following reports were reviewed by the inspector:
81-41 82-06 81-60 82-07 81-70 82-08 82-01 82-09 82-02 82-10 82-03 82-11 82-04 82-13 82-05 82-14 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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