IR 05000267/1982023
| ML20027E558 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 10/12/1982 |
| From: | Dickerson N, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20027E541 | List: |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR 50-267-82-23, GL-81-07, GL-81-7, NUDOCS 8211150491 | |
| Download: ML20027E558 (12) | |
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APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report:
50-267/82-23 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: September 1-30, 1982 Inspectors:
61. ( u M h
/4 -8-8t M. W. Dickerson, Senior Resident Reactor Inspector Date
.f 0 lo-T-12
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G.' L. Plumlee III, Rdsident Reactor Inspector Date Approved:
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/042-85
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T. F. Westerman, Chief, Reactor Project Section A Date Inspection Summary Inspection Conducted September 1-30, 1982 (Report:
50-267/82-23)
Areas Inspected: Routine, announced inspection of Surveillance; Maintenance; Operational Safety Verification; Follow Up of Previous Inspection Findings; Review of Plant Operations; Follow Up of Written Reports of Nonroutine Events; Follow Up on Regional Request; and Review of Periodic and Special Reports.
The inspection involved 172 inspection-hours onsite by two NRC inspectors.
Results: Within the eight areas inspected, one violation was identified (Failure to follow procedure, Paragraph 3).
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'"8211150491 821018 DR ADOCK 05000
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DETAILS 1.
Persons Contacted M. Block, Superintendent of Operations T. Borst, Radiation Protection Manager W. Craine, Superintendent of Maintenance D. Evans, Shift Supervisor M. Ferris, Supervisor QA Technical Support W. Franek, Nuclear Site Engineering Manager W. Franklin, Shift Supervisor C. Fuller, Technical Services Engineering Supervisor J. Gahm, QA Manager B. Gunnerson, Structural Supervisor of Nuclear Projects J. Ilak, Shift Supervisor E. Hill, Operations Manager J. Jackson, QA/QC Supervisor J. Liebelt, Senior Maintenance Supe visor V. Lucero, Chemistry Supervisor M. McBride, Technical / Administrative Services Manager F. Novachek, Technical Advisor H. O'Hagan, Shift Supervisor J. Reesy, Nuclear Design Manager G. Reigel, Shift Supervisor L. Singleton, Superintendent Operations QA J. Van Dyke, Shift Supervisor R. Wadas, Training 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 Inspecticn Findings (Closed) Violation (50-267/8126-01):
Removal of Emergency Diesel Generator Sets IA and IB From Service Without Demonstrating the Operability of the Alternate Diesel Generator Set. The licensee has revised procedure P-2 which utilizes a new clearance form format to assure consideration of applicable LC0's.
(Closed) Open Item (50-267/7607-01):
Amendments to the FSAR.
The licensee issued a completely revised FSAR, which was effective July 22, 1982.
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3.'
Operational Safety Verification The NRC inspector reviewed licensee activities to ascertain that the facility is being operated safely and in conformance with
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regulatory requirements, and the licensee's management control t
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 discussions with licensee personnel, independent verification of safety system status and limiting conditions for operations, and review of facility records.
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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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:
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 pas verified by walkdown of the accessible portions. The NRC inspector verified the operability of, " System 75 - Turbine Building." The problems identified during the system walkdown are being corrected by the licensee.
Procedures were also reviewed and implementation observed for Gaseous Effluent Releases 688, 690, 691, 697, 698, and 701. The releases appeared to have been made in a satisfactory manner.
On September 23, 1982, the NRC inspector observed implementation of a batch ( >10 gpm) release from the reactor building sump.
Prior to the release, samples were taken and analyzed as required by LC0 4.8.2.
The results of this analysis were reviewed by the NRC inspector as well as the procedure for performing the release (S0P 62). One of the steps in S0P 62 required the operator to verify flow through the sight flow indicator to RT-6212 and 6213 and record this verification in the station log. The NRC inspector determined from the review of this batch release documentation, as well as the documentation for batch releases made on September 15, 1982, and September 21, 1982, that the operator failed to record the verification of flow through RT-6212 and RT-6213 as required by S0P 62. Discussions with some of the licensed operators indicated that they were not aware of this requirement.
The NRC inspector informed the licensee of the above findings and that the failure to follow procedures required by Technical Speci-fications is considered a violation (8223-01).
The NRC inspector had no further questions in this area.
4.
Surveillance (Monthly)
The NRC 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 5.8.labc-M Radioactive Gaseous Effluent System Test (Releases 688, 690, 691, 697, 698, and 701)
SR 5.4.1.1.14.a-M Plant 480V Power Loss Scram Test
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SR 5.4.1.3.1.b-M Circulator Speed (Steam and Water) Test SR-RE-3-M Circulator Seal Malfunction Trip Test SR 5.10.2d-A Halon Fire Suppression System Actuation Signal Circuit Test SR 5.10.2ab-Q Halon Fire Suppression System SR 5.10.2c-A Halon Fire Suppression System No violations or deviations were identified.
5.
Maintenance (Monthly)
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 appropriate Codes and Standards. The following maintenance activities were reviewed and observed:
FHP-5 Fuel Handling Procedure, " Spent Fuel Shipping," Shipments YVB-JXI-063 and YVB-JXI-065 PTR 7-268 P-2105 Mechanical Seal Replacement in accordance with MP 21-2,
" Maintenance and Repair of Gould's Bearing Water Supply Pumps" PTR 9-98 V-21268-2 Repair in accordance with MP 29, " Repair and Adjust-ment of Sage Safety Valves" PTR 9-329 CRS 262 Repair in accordance with MP 98-1, " Repair and/or Testing of Hydraulic Pipe Hangers" No violations or deviations were identified.
6.
Reserve Shutdown System Public Service Company (PSC) has been operating Fort St. Vrain in accordance with Operations Order 82-14, which contains a graph titled, " Control Rod Bank 3D Allowable Positions VS Average Core Outlet Temperature for Cycle 3 with Reserve Shutdown Material in Region 27," since September 2, 1982. This resulted from an analysis performed by General Atomic Company (GAC) on the effects of reserve shutdown material being present in Region 27 that indicated a potential for operating in a mode outside the limits specified in LC0 4.1.3.
The analysis indicated that due to the flux tilt created by the suspected presence of reserve shutdown material in Region 27, the calculated reactivity worth of the control rod pair in Region 11 may exceed the maximum allowable worth of.0124k to as much as 01350 r
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The licensee identified that the basis for Specification LC0 4.1.3 does state that, "A value larger than.012d k for a single rod pair can be safely accommodated if fuel temperatures are lower than 15000 F and/or the temperature defect between refueling temperature (2200 F)
and uperating temperature (1500 F) is greater than.0284 k."
From daily core performance monitoring, the NRC inspector has verified average core outlet temperature to be less than 15000 F.
PSC intends to operate in accordance with Operations Order 82-14 until such time as reserve shutdown material is not present in Region 27 or until a future analysis reveals another acceptable operating strategy.
The above is documented in the licensee's letter P-82370 dated September 3, 1982.
The NRC inspector has no further questions in this area.
7.
Control of Heavy Loads Resulting from the follow up of Generic Letter 81-07, " Control of Heavy Loads," the NRC inspector participated in an NRR conference call on September 8,1982, in which draft technical evaluation report comments on the licensee's response to Section 2.1 of the December 22, 1980, gensric letter were discussed.
An additional response will be forthcoming from PSC based on the above discussion in an effort to resolve the above draft technical evaluation report comments provided in the letter Clark to Lee, dated July 21, 1982. Additionally, based on the above telephone discussion, PSC has submitted in letter P-82385 dated September 10, 1982, their statement of compliance with the intent of the five interim action items given in the December 22, 1980, letter.
The NRC inspector had no further questions in this area.
8.
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 F
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The following reports were reviewed by the NRC inspector:
81-066 82-023 81-067 82-025 81-075 81-026 82-012 82-027 82-015 82-028 82-016 82-029 82-017 82-030 82-019 82-031 82-020 82-034 82-021 9.
Review of Plant Operations The NRC inspector reviewed aspects of facility operations to determine if they were being accomplished in accordance with regulatory requirements.
a.
Corrective Action Reviewed were all of the licensee event reports generated which had not been closed prior to this report.
Included in the review were trends and recurring failures and the resolution of discrep-ancies involving safety-related equipment.
b.
Training The NRC inspector verified by direct questioning one new, one existing, and one temporary employee that administrative controls and procedures, radiological health and safety, industrial safety, controlled access and security procedures, emergency plan, and quality assurance training was provided as required by licensee's committed program.
The NRC inspector also verified by direct questioning one craftsman and one technician that on-the-job training, formal technical training commensurate with job classification, and fire fighting training was provided as required by licensee's committed program.
c.
Review and Audit The NRC inspector is reviewing the licensee's audit QAA-1101-82-01 titled, " Audit of FSV Calibration Activities," and dated September 8, 1982, which is in progress. The NRC inspector has verified the following:
Audit personnel are qualified and independent of the
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organization being audite.
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That an audit entrance meeting was made with management
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heads of the departments concerned.
That the audit was being performed in accordance with the
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required frequency.
No violations or deviations were identified.
10.
Weld Qualifications To ascertain whether the licensee has developed controls and procedures to assure that welding associated with maintenance or modifications is in accordance with regulatory requirements and/or industry approved codes and standards, the NRC inspector performed the following:
Observed an in-process welding operation that consisted of the
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weld qualification of a Babcock and Wilcox welder as required by Fort St. Vrain welding procedures prior to welding during a modification on one of the plant's auxiliary boilers.
Verified that the Babcock and Wilcox weld procedure used in the
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above procedure conformed to the applicable codes and standards required for this type weld.
Reviewed the welder performance and procedures qualification records
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for the weld performed above to ensure conformance with the provi-sions of Section IX of the ASME Code and licensee established requirements.
Visually examined the above weld quailificatior. test coupon to
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verify conformance with the completed weld visual standards.
Witnessed setup and radiography of the above test coupon and
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visually examined the completed radiographs to verify qualification of the weld in accordance with applicable codes, standards, and licensee procedures.
No violations or deviations were identified.
11.
Report Reviews The NRC inspector reviewed the following reports for content, reporting requirements, and adequacy:
Monthly Operating Information Report, August 1982 Monthly Operations Report, August 1982 Semi-Annual Effluent Release Report, January 1,1982 through June 30, 1982
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The review of the operations report revealed that it did not include reported problems with the reserve shutdown system for Region 27.
Because of this the licensee has been asked to supplement the report with information on the dropped Region 27 boron balls.
No violations or deviations were identified.
12.
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 inspectors discussed the findings indicated in the previous paragraphs.
The licensee acknowledged these findings.
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