IR 05000267/1982002
| ML20041F158 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/05/1982 |
| From: | Dickerson M, Plumlee G, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20041F153 | List: |
| References | |
| 50-267-82-02, 50-267-82-2, NUDOCS 8203160241 | |
| Download: ML20041F158 (10) | |
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APPENDIX
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U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-267/82-02 License DPR-34 Docket:
50-267 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: January 1-31, 1982 Inspectors:
. M-
- h 8-S-82 M. W. Dickerson, Senior Resident Reactor Inspector Date
. YMks h A ' ~6 Q G. L. Plumlee III, Resident Reactor Inspector Date Approved By:
N[
7 '//~U T. F. Westerman, Chief, Project Section A Date Inspection Sumary Inspection conducted January 1-31, 1982 (Report: 50-267/82-02)
Areas Inspected: Routine, announced inspection of Surveillance; Maintenance; Inspection During Long Term Shutdown; Review of Plant Operations; NRC Circulars; Reserve Shutdown System; Core Safety Limit; Follow Up of Previous Inspection Findings; and Review of Periodic and Special Reports. The insoection involved 194 inspection-hours on si^e by two NRC inspectors.
Results: Within the nine areas inspected, no violations or deviations were identified.
3203160241 820216 PDR ADOCK 05000267 O
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1.
Persons Contacted M. Block, Superintendent of Operations T. Borst, Radiation Protection Manager B. Burchfield,- Results Engineerina Supervisor M. Deniston, Shift Supervisor M. Ferris, QA Technical Support Supervisor W. Franek, Nuclear Site Engineering Manager C. Fuller, Technical Services Engineering Supervisor J. Cahm, QA Manager E. Hill, Operations Manager D. Hood, Shift Supervisor J. Liebelt, Senior Maintenance Supervisor M. McBride, Technical / Administrative Services Manager F. Novachek, Technical Advisor T. Orlin, Superintendent QA Services G. Reigel, Shif t Supervisor T. Schleiger, Health Physics 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 Inspection Findings
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(Closed) Unresolved Item (50-267/8008-01): Radio Transmitters Caused Upset in Buffer-Mid-Buffer System. Test T-154 was completed on February 23, 1981, and resulted in finding two additional equipment problem areas.
The results of this test and earlier problems noted have been evaluated by the licensee. This has resulted in administrative 1y controlling areas where transmissions may be a problem.
x(Closbd) Unresolved Item'(50-267/6101-04): Conflicts in Reserve Shutdown Assembly Functional Test.
Changes were made to the required procedures prior to the next scheduled performance of the Reserve Shut-down Assembly Functional Test. The test was reviewed and observed by the NRC inspector and documented in IE Inspection Report: 50-267/81-18.
(Closed) Violation (50-267/8113-04): Technical Specification SR NR 1.1(d).
A revision was made to the Water Chemistry Procedures (WCP 8, effective date December 29, 1981) requiring a weekly calibration of conductivity meters as required by the Technical Specification.
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(Closed) Unresolved Item (30-267/8113-05): Technical Specification Surveillance Procedures / Water Chemistry Procedures. The licensee has determined that the words calibrate and standardize are used inter-changeably.
(Closed) Open Item (50-267/8116-02): Missing Environmental Protective Covers and Missing Iabels.
The missing covers and labels have been installed.
(Closed) Open Item (50-267/8116-04):
Storage Instructions and Locations.
Acceptable visual, meggar and functional tests have been completed on the service water pump and motor replacements and their installation is complete.
(Closed) Open Item (59-267/8116-05):
Incomplete Purchase Order Records.
Records for Purchase Order N-10017 for Aqastat Relays as contained in the records' vault are now complete.
In addition, a random selection of the 10000 series purchase orders were reviewed for completeness.
No additional problams were found for those records examined.
(Closed) Unresolved Item (50-267/8118-03):
Calibration of Hydrogen Supply Regulators.
PCV-4617 and PCV-4618 have been added to the ' aster Calibration schedule and HV-4617 and HV-4618 have been removed from the Master Calibration Schedule.
(Closed) Open Item (50-267/8118-05): Control of Contractor Welding in the Reactor Building and Turbine Building. A daily report of welding in the Reactor Building and Turbine Building is now being issued to the Shift Supervisor.
(Closed) Open Item (50-267/8118-07):
Sounding of Fire Alarm.
Require-ments for immediate reporting fires to the Shift Supervisor have been l
reviewed with contractor workers and revisions were also made inserting
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these requirements into the contractots procedures.
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3.
Inspection During Long Tern Shutdown The NRC inspector reviewed licensee activities during an extended
shutdown to ascertain that the facility is being maintained in conformance with regulatory requirements and that the licensee's
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management control system is effectively discharging its responsibilities for continued safe shutdown.
The review was conducted by direct obser-vation of activities, tours of the facility, and discussions with licensee personnel.
Included in the inspection were observation of control rcom activities, review of operational logs, records, and tours of accessible areas.
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 Como11ance 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 Protection Controls
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Housekeeping
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Physical Security Implementation
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Plant / Equipment Conditions
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Activities in Progress
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Clearance Tags
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Fire Hazards
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Control Room Manning
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The inspection also consisted of:
A.
Review of the licensee's Jumper / Bypass controls (Temporary Configuration Report Log and the System Abnormalities Clearance Log) to verify that there are no conflicts with Technical Speci-fications, the licensee is actively pursuing correction to conditions requiring jumpers, and jumper / bypasses have been installed and removed properl.
B.
Independent verification of clearance number 3078 to verify that a tagout system is in effect and that tagouts are properly conducted.
The NRC inspector informed the licensee that the newly installed valves cleared out under this clearance were not labeled in accordance with the valve numbers on PI-21-6. The licensee is actively pursuing a corrective action program to resolve this problem which appears to involve other valves installed during the Loop Split Modification.
C.
Witnessing portions of the functional test, FT-1314-1, of the Loop 2 Helium Dryer in accordance with CN 1314 prior to the return of the dryer to service to verify the adequacy of the licensee's work.
D.
Witnessing portions of the Cold Checkout Procedure (CCT 1) for the re-installatior, of RT-21251 in accordance with CN 1321 A/
CWP 81-246 prior to the return of the radiation detector to service to verify the adequacy of the licensee's work.
It was brought to the licensee's attention that an old CCT 1 was used which required each circuit drawing to be signed / dated.
A revised CCT 1 had been issued December 2,1981, which deleted this requirement.
No violations or deviations were identified.
4.
Surveillance (Monthly)
The NRC inspector reviewed all aspects of surveillance testing involving safety-related systems. The review included observation
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and review relative tc Technical Specification requirements.
The surveillance tests reviewed and observed were:
SR 5.7.2b-A Fuel Storage Facility Cooling System Instrumentation Calibration and Test SR 5.4.1.3.5.c -R Circulator Drain Pressure Calibration SR 5.2.22-X PGX Graphite Specimen Examination SR 5.2.15-M PCRV Penetration Interspace Pressure Functional Test SR 5.4.1.3.3c-R Circulator Bearing Water Flow Calibration SR 5.1.6-W Core Safety Limit No violations or deviations were identifie.
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5.
Maintenance (Monthly)
The NRC inspector reviewed records and observed work in progress to ascertain that the following maintenance agtivities were being conducted in accordance with approved procedures, Technical Specifications, and appropriate Codes and Standards. The following maintenance activities were reviewed and observed:
Shutdown Maintenance PTR 9-205 Repair SV-2105 in accordance with MP 5," Valve
.10-203 Packing Procedure,"and MP 91-21," Maintenance and Repair of System 91 Hydraulic Valve Actuator" PTR 9-128 Movement of Diesel Engines K-9205X and K-9206X
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in accordance with PM 92.10, " Maintenance and Repair of Emergency Diesel Generator sets K-9201 and K-9202," to allow cleaning of generator windings for "B" Diesel Generator Set.
CN ll10/CWP 81-54 Replace Loop 2 Helium Circulator Buffer-Mid-
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Buffer PDIS's with PDT's CN 1427C/CWP 81-286 Return Steam Generator B-2-3 Interspace
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Discharge Piping to the Original Configuration PTR 12-257 Repair HV-2246 in accordance with MP 4, " Maintenance
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and Repair of Velan Valves," and MP 39, " Installation and Maintenance of Limitorque Valve Operators and Rotork Valve Operators" CN 12708/CWP 81-269 Install Valves on Loop I Reheat Drain Lines
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for Steam Generator Leak Detection
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Loop Split Maintenance CN 1314/CWP 81-238 (ELECT)
Installation of Buffer Helium Dryers
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(S-2111, S-2112) and Associated Equipment
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CN 1319/CWP 81-181 (MECH) Helium Recovery Compressor Station l
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/CWP 81-215 (ELECT)
/CWP 81-241 (ELECT)
CN 1321A/CWP 81-256 (ELECT) System 21 Modification-North Stairs
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l Relocation l
CN 1318/CWP 81-171 (MECH) Low Pressure Separator
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/CWP 81-218 (ELECT) Bypass Line No violations or deviations were identified.
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6.
Reserve Shutdown System On January 13, 14, and 15, 1982, the NRC inspector reviewed surveillance procedures, operating procedures, records of tests and procedures performed, and inspected the reserve shutdown system to determine that the licensee conformed to Technical Specification, the FSAR and approved procedures.
The surveillance procedures were reviewed to determine whether the pro-cedures:
Require application of test pressure to the reserve shutdown hoppers
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in accordance with the Technical Specifications and the FSAR.
Identify appropriate initial conditions.
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Identify proper valve lineup to each hopper for returning the system
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to normal and require verification of the valve lineup.
Require periodic calibration of the pressure indicators.
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Require testing a hopper and a rupture disc in accordance with
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requirements in the Technical Specifications and the FSAR.
Specify appropriate handling requirements, test conditions, and
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acceptance criteria.
Require inspection of the hopper after the rupture disc ruptures to
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determine whether all the balls were released from the hopper.
Identify appropriate specifications for the replacement rupture disc
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and requirements for inspection of the replacement rupture disc prior to and following installation.
Test results performed during the last year (or last performed as
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required) conform to the requirements of the Technical Specifications, FSAR, and approved procedures.
Inspected the reserve shutdown system to determine whether:
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The volume of the individual hopper helium bottles conforms to the
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requirement in the FSAR.
The pressure on each individual hopper helium bottle exceeds the
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lower limit set forth in the Technical Specifications.
The valve lineup is as required.
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Inspected specifications for procurement of replacement rupture discs and compared with FSAR specifications.
Determined that the distribution of B C was documented and in accordance
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with FSAR requirements.
No violations or deviations were identified.
7.
Review of Plant Operations The NRC inspector reviewed aspects of facility operations to determine if they were being accomplished in accordance with regulatory require-ments.
A.
Training On January 6, 7, and 8,1982, the NRC inspector attended new licensee candidate training lectures covering the Plant Protective System and Emergency Procedures to:
Verify lesson plan objectives were met
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Verify training was in accordance with the approved operator
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training requirements On January 11, 1982, the NRC inspector verified by direct question-ing of one new, one existing, and one temporary employee and one craftsman and one technician that training was provided as required by the licensee's committed training program.
B.
Review and Audit Plant Operating Committee meetings 448 and 449 were attended to determine compliance with the Technical Specification and other regulatory requirements.
No violations or deviations were identified.
8.
IE Circulars The NRC inspector verified by record review, observation and discussion with the licensee, the action taken in response to IE Circulars.
The following Circulars were reviewed:
80-09 Problems with Plant Internal Communication Systems. The source of power for internal communications system is non-interruptible bus No.1 which is provided with redundant feeds to insure operability during loss of offsite power. Tests regarding radio transmission have been completed and susceptible areas administratively controlled.
Additionally, employees receive instruction regardino the areas where operation of radios is not permitted.
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81-01 Design Froblems Involving Indicating Pushbutton Switches Manu-factured by Honeywell Incorporated. The licensee has determined that Series 2 indicating pushbuttons manufactured by Honeywell are not used at Fort St. Vrain.
81-02 Performance of NRC-Licensed Individuals While on Duty. Although not required,the licensee respoaded to this circular in letter P-81077 dated March 2, 1981. Ti.e response has been submitted to NRC headquarters for their review.
81-09 Containment Effluent Water That Bypasses Radioactivity Monitor.
The specifics of this circular do not apply to Fort St. Vrain since it does not have a reactor containment vessel. However, discharges from the Reactor Building Sump are monitored.
81-14 Main Steam Isolation Valve Failures to Close.
Fort St. Vrain experienced problems with respect to failure of MSIV's to close.
However, these problems were related to the Hydraulic 011 System and since it was modified in 1975, to improve oil cleanup, no problems have been experienced. Additionally, Surveillance Tests (full stroke one per year and 10% stroke once per week) are run to reveal problems of the type discussed in the circular.
9.
Core Safety Limit The inspector reviewed surveillance procedures regarding core safety limits to verify that procedures exist requiring (a) periodic review of reactor power and reactor power to flow ratios to assure that undue migration of fuel kernels has not occurred, and (b) calculation of the amount of fuel kernel migration as required by the Technical Specification when the reactor power to flow ratio exceeds a specified valve.
Surveillance Procedure (SR 5.1.6-w) was reviewed by the inspector for the period January 1981 through December 1981. Total migration experienced for core 3 through December 1981, is 0.00069.
No violations or deviations were identified.
10.
Report Reviews The NRC inspector reviewed the following report for content, reporting requirements and adequacy:
Monthly Operating Information Report, December 1981 Monthly Operations Report, November 1981 Monthly Operations Report, December 1981 No violations or deviations were identifie _. -
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11.
Exit Interview Exit interviews were conducted at the end of variour 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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