IR 05000267/1987018
| ML20237F816 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 07/30/1987 |
| From: | Chaney H, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20237F802 | List: |
| References | |
| 50-267-87-18, NUDOCS 8708210575 | |
| Download: ML20237F816 (6) | |
Text
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-267/87-18 License:
DPR-34 Docket:
50-267 Licensee:
Public Service Company of Colorado (PSC)
P. O. Box 840 Denver, Colorado 80201-0840 Facility Name:
Fort St. Vrain Nuclear Generating Station (FSV)
Inspection At:
FSV Site, Weld County, Platteville, Colorado Inspection Conducted:
July 14-17, 1987
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WD/87 Inspector:
[vH.'D. Chaney, Radiation Specialist, Facilities Date Radiological Protection Section 7/
Approved:
h B.' Murray, Chief, facilities Radiological Date Protection Section
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Inspection Summary
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p Inspection Conducted July 14-17, 1987 (Report 50-267/87-18)
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Areas Inspected:
Routine, unannounced inspection of the radioactive material I
transportation program, low level radioactive waste management and storage programs, and the radiological environmental monitoring program.
i Results:
Within the areas inspected, no violations or deviations were
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identified.
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1 8708210575 870818 DR ADDCK 05000267 PDR 1u l-
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DETAILS l
1.
Persons Contacted PSC
- R. O. Williams, Jr., Vice President, Nuclear Operations
- C. H. Fuller, FSV Station Manager
- P. F. Tomlinson, Quality Assurance (QA) Manager
- D. O. Warembourg, Manager, Nuclear Engineering
- M. H. Holmes, Manager, Nuclear Licensing
- M. J. Ferris, Manager, Operations QA
- J. M. Gramling, Supervisor, Nuclear Licensing W. Woodard, Plant Health Physicist
- S. Sherrow, Health Physicist
- D. D. Miller, Supervisor, Radiochemistry
- L. R. Sutton, Supervisor, QA Auditing
- M. Lehr, Supervisor, QA Engineering R. Frye, Instrument and Controls Technician Others R. E. Farrell, NRC Senior Resident Inspector
- P. W. Michaud, NRC Resident Inspector S. J. Clow, Colorado State University Chemist L. L. Gonsalves, Research Associate
- Denotes those individuals present during the exit interview on July 17, 1987.
2.
Followup on Previous Inspection Findings (Closed) Violation 267/8607-01:
" Reporting of Unplanned Effluent Releases" - This item involved the licensee's failure to report an unplanned effluent release that occurred during the January to June 1985 Semiannual Radioactive Effluent Release Report period.
The licensee had implemented administrative controls that include the review of documented unplanned effluent releases for inclusion into the semiannual radioactive effluent release report.
These actions appear to be satisfactory to prevent a recurrence of the problem.
The licensee had also submitted a supplement to the aforementioned effluent report that included a summation of the details of the March 17, 1985, unplanned release.
This item is considered closed.
(Closed) Open Item 267/8128-02:
" Surveillance of Control Room Emergency Filtration Units" - This item involved the licensee's lack of a suitable surveillance program for both the Technical Support Center (TSC) and l
Control Room air filtration units.
That portion dealing with the TSC was closed out in NRC Inspection Report 50-267/83-28 (paragraph 9).
The NRC i
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' accepted the design of the Control Room filtration system (no protection
'from. radionuclides is assumed for this system) and was reported so in Issue 4 of'the Updated Final Safety Analysis Report.
The licensee had the Control' Room closed loop filtration system (HEPA and charcoal filters)
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inspected by a consultant.
The consultant determined that the filtration
. unit was suitable for the removal of. obnoxious odors and fames.
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licensee implemented a surveillance (SR 5.10.3 b-5A/5.4.2-A) of the filtration' system for. identification-of' conditions that indicate the filters / charcoal.needs changing.
This item is considered closed.
(0 pen) Open Item 267/8221-04:
"High Range Noble Gas Effluent Monitors, NUREG-0737, Item II.F.1.1" - This item was most recently updated in NRC Report 50-267/85-02.
The NRC (Heitner) informed FSV (Walker) via~1etter and Safety Evaluation Report, dated January 9, 1986,.that the licensee's proposed design and design improvements to.the currently installed post
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accident' reactor' effluent activity monitor were acceptable.
The licensee
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had committed to installing a dilution system for the monitors so that they could extend the measurement range of the monitor (RT-7324-2).
This dilution system will be installed (design change notice CN-2042) during the Fall 1988 refueling outage.
This item is considered open pending completion of licensee actions.
(0 pen) Violation 267/8420-02:
" Effluent Monitoring Instrumentation" -
This' item' concerned.the licensee's commitment-to. install a continuous reactor building sump liquid release pathway monitor that:would provide monitoring for radionuclides that predominantly decay by. beta radiation.
The licensee. committed to providing quarterly ~ progress reports on the development of the. monitoring system.
The licensee's most recent progress report (June 22,1987) indicates that the development of the beta monitor (beta scintillation cell) had encountered difficulties due to the oil contamination within the sump and its deleterious effect on the monitor's scintillation crystals (calcium fluoride).
The licensee is improving controls over discharges of oily contaminated wastes into the sump and improvements in filtration of the effluent samples.
This item remains open pending licensee completion of remaining actions to implement a continuous online beta monitoring system for the reactor building sump.
3.
Inspector Observations The following are observations the NRC inspector discussed with the licensee during the the exit interview on July 17, 1987.
These observations are not violations, deviations, unresolved items or open items. These observations were identified for licensee consideration for program improvement, but the observations have no specific regulatory requirement.
The licensee stated that the observations would be reviewed.
Monitoring Instrumentation Background - The procedure (HPP-26) used for surveying potentially radioactively contaminated materials for unrestricted release does not include a quantitative numerical value for background limits on frisking and high sensitivity instruments, but only states that background should be low, i
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4, Program Areas Inspected
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The following program areas were inspected.
Unless otherwise noted, the inspection was completed and revealed no violations, deviations, unresolved items, or open items.
Notations after a specific inspection item are used to identify the following:
I = item not inspected or only partially inspected; V = violation; O = deviation; U = unresolved item; and 0 = open item.
Procedure Inspection Requirements 80721 Radiological Environmental Monitoring 02.01 - Audits and Appraisals 02.02 - Changes 02.03 - Implementation of the Radiological Environmental Monitoring Program 02.04 - Implementation of the Meteorological Monitoring Program 02.05 - Quality Assurance (QA) Program 02.06 - Contractor Activities 83722 Radiation Protection, Plant Chemistry, and Radwaste:
Organization and Management Controls 02.01 - Organization 02.02 - Staffing 02.03 - Radiation Protection Manager 02.04 - Identification and Correction of Weaknesses 02.05 - Audits and Appraisals 83723 Training and Qualifications:
General Employee Training, Radiation Safety, Plant Chemistry, Radwaste, and Transportation 02.01 - Training Adequacy 02.02 - Employee Knowledge Retention 02.03 - Transportation /Radwaste Training 02.04 - Staff Qualification Requirements 02.05 - Replacement Personnel
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02.06 - Accreditation Status I
02.07 - Audits and Appraisals j
02.08 - Identify Training Not Covered by Accreditation
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i 84722 Solid Wastes l
02.01 - Audits and Appraisals
02.02 - Changes 02.03 - Processing and Storage 02.04 - Disposal of Low-Level Wastes
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84850
. Radioactive Waste Management - Ins)ection of Waste Generator Requirements of 10 CFR 20 and 10 C;R 61 02.01 - Management Controls 02.02'- Quality Control-(QC)
02.03 - Waste Manifests 02.04 - Waste Classification 02.05 - Waste Form and Characterization 02.06 Waste Shipment Labeling l
02.07 - Tracking of Waste Shipments
'02.08 - Disposal Site License Conditions 65051 Low-Level Radioactive Waste Storage Facilities 02.01 - Basis for Construction 02.02 - Quality Assurance 02.03 - Procedures for Construction 02.04 - Review of Construction 02.05 - Organization and Staffing 02.06 - Training and Qualifications 02.07.- Stertup and Operations Procedures 02.08'- Effluent Monitoring Changes 86721 Transportation
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02.01 - Audits and Appraisals
02.02 - Procedures 02.03 - Procurement and Reuse of Packagings 02.04 - Implementation 02.05 - Transportation Incidents 90713 Review of Periodic and Special Reports 02.01 - Report Content 02.02 - Verify Test Results 02.03 - Ascertain Adequacy of Corrective Actions 02.04 - Determine Classification of Report Contents 02.05 - Document Review and Closeout'- see paragraph 5 TI 2500/22 Collection of Collocated TLD Measurement Results 04.01 - Collection of Environmental TLD Data
.04.02 - Collocated NRC/ State / Utility TLD Stations 04.03 - Monitoring Location Identification j
04.04 - Documentation of Information
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5.
Followup on Licensee Event Reporting (LER)
j (Closed) LER 267/87-012: Functional Test for Radioactive Effluent I
Monitors not Completely Performed - The event the LER describes involves
' the failure of the licensee's surveillance procedures for functional l
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testing gaseous and liquid effluent monitors to properly verify control room annunciation alarm upon circuit failure.
The NRC inspector reviewed
the licensee's corrective actions and found them to be acceptable to
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prevent a recurrence of the problem.
6.
Exit Interview
'The NRC inspector met with the NRC resident inspector and licensee representatives denoted in paragraph 1 on July 17, 1987, and summarized the scope and findings of the inspection as presented in this report.
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