IR 05000267/1987013
| ML20215A485 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 06/11/1987 |
| From: | Farrell R, Jaudon J, Michaud P, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20215A462 | List: |
| References | |
| 50-267-87-13, GL-84-24, IEB-79-01, IEB-79-1, NUDOCS 8706160677 | |
| Download: ML20215A485 (8) | |
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APPENDIX U. S. NUCLEAR REGULATORY' COMMISSION
REGION IV
l NRC' Inspection Report:
50-267/87-13 License:
DPR-34-
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h Docket:
50-267 Licensee:
Public Service Company.of Colorado (PSC)
J Facility Name:
Fort St. Vrain Nuclear Generating Station Inspection At:
Fort St. Vrain (FSV) Nuclear Generating Station, Pla tteville.. Colorado and ~PSC Offices, Denver, f
Colorado Inspection Conducted:
May 1-31, 1987
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l Inspectors:
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i R. E. F1rrell, Senior Resident Inspector-(SRI)
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P. W. Michaud,' Resident Inspector (RI)
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N M. E. Skow, Project Engineer, Project Section A Dats Reactor Projects Branch
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Approved:
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J. (P. /J a t/d o'n, Th QF, P f o j e c t S e c t i o n A Rea(tog Projects Branch
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8706160677 870611
PDR ADOCK 05000267
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Inspection Summary Inspection Conducted May 1-31, 1987 (Report 50-267/87-13)
Areas Inspected:
Routine, unannounced inspection of licensee action on previous inspection findings, operational safety verification, maintenance, surveillance, licensee action on 10 CFR 21 reports, IE Bulletins and Generic Letters, ESF system walkdown, and plant operations review committee.
Resul ts: Within the seven areas inspected, no violations or deviations were identified.
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DETAILS.
1.
Persons Contacted Principal Licensee Employees D. Alps, Supervisor, Security F. Borst, Manager, Support Services / Radiation Protection
- L. Brey, Manager, Nuclear Licensing and Fuels R. Burchfield, Superintendent, Betterment Engineering Nuclear Results
- R. Craun, Manager, Nuclear Site Engineering D. Evans, Superintendent, Operations
- M. Ferris, Manager, QA Operations W. Franek, Superintendent, Plan / Scheduling & Stores C. Fuller, Station Manager D. Goss, Coordinator, Nuclear Licensing and Fuels
- J. Gramling, Supervisor, Nuclear Licensing Operations
- M. Holmes, Manager, Nuclear Licensing F. Novachek, Manager, Technical / Administrative Services
- D. Warembourg, Manager, Nuclear Engineering
- R. Williams Jr., Vice President, Nuclear Operations The NRC inspectors also contacted other licensee and contractor personnel during the inspection.
- Denotes those attending the exit interview conducted June 2,1987.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (267/8627-01):
Reactivity Manipulations. This item identified required reactor manipulations which had been missed by various operators during the June 1984 - June 1986 training cycle. During this followup, the NRC inspectors found that all of the missed training manipulations had been made up and that credit for a makeup manipulation was not being taken twice to count for the current cycle.
It also appeared that manipulations for the current cycle were being completed at a higher rate and that this rate appeared to be sufficient to prevent a recurrence.
The licensee also stated that two additional senior reactor operator (SR0) licensed personnel in the training department helped improve the performance of the reactor manipulations. This item is considered closed.
(Closed) Unresolved Item (267/8526-02):
Battery Room Ventilation. This item was a portion of a multipart item, the last remaining portion that had not been previously closed. This item concerned ventilation to the battery rooms for control of buildup of hydrogen concentration and battery temperature control. The licensee issued change notice (CN) 2332 to modify
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battery room ventilation.
Testing was accomplished by Functional Test (FT) 2332 and as part of Controlled Work Procedure (CWP)86-246.
The NRC inspectors discussed two observations with the licensee.
First, the NRC inspector expressed concern that the ventilation flow rate was not tested as part of the FT.
It was subsequently noted, that the flow test was accomplished by the CWP.
While this appeared to be adequate, it was difficult for the work review committee to determine if the appropriate testing for changes specified and accomplished when all testing is not referenced within a single document.
The ventilation flow rate appeared adequate to preclude high concentrations of hydrogen in the battery rooms and satisfied the regulatory concern of the unresolved item.
Second, when the FT was performed, the "lA" battery pilot cell temperature was noted as 86 F.
The NRC inspectors found the temperature to be 94 F, and it appears that the temperature in the battery room frequently exceeds manufacturer's recommendation of 90 F.
It was noted in the CN that if the average annual operating temperature of the batteries is 92 F that the life expectancy of the battery is reduced from 20 years to 10 years.
This is not a regulatory concern but rather an item of economic concern for the licensee.
This item is considered closed.
(Closed) Unresolved Item (267/8415-01):
Control Room Alarm Index Not Updated.
The item concerned keeping the control room up to date regarding the set point of alarms.
The item also noted that administrative changes had been implemented by tne licensee subsequent to the particular occurrence observed by the NRC inspectors in that report, and that the procedural changes had been made to preclude reoccurrence.
During this followup, the NRC inspector found that control room set point index, which includes the alarm index, is annotated by control room operators prior to the change being made to the plant.
This item is considered closed.
No violation or deviations were identified in this inspection area.
3.
Operational Safety Verification The NRC inspectors reviewed licensee activities to ascertain that the facility is being operated safely and in conformance with regulatory requirements and that 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 discussions with licensee personnel, independent verifications of safety system status and limiting conditions for operation, 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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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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Station service requests (SSR)
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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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No violations or deviations were identified.
4.
Maintenance The buffer helium return flow indication for "A" helium circulator was indicating lower than normal in the control room.
The licensee determined the problem to be in the flow element located in the return line.
SSR 87505593 was issued to replace the flow element, FE-2171, and the NRC inspectors witnessed these activities.
The clearance to perform this work was reviewed, along with the SSR, to ensure that adequate controls were present.
The NRC inspectors observed the replacement of the flow element with an appropriately certified component, and examined the element which had been removed, which appeared to be partially clogged.
Following the replacement of the flow element, the associated flow transmitter, FT-2171, was calibrated.
SSR 87505594 was reviewed along with Procedure RP89E,
" Calibration of ITT Barton Electronic Differential Pressure Transmitters."
No discrepancies were noted.
Replacement of the mechanical seal on Pump P-2105, " Bearing Water Makeup Pump," was observed by the NRC inspectors.
SSR 87505354 provided instructions to replace the mechanical seal in accordance with MP-21.2,
" Maintenance and Repair of Gould's Bearing Water Supply Pumps." These documents were reviewed to ensure applicable limiting conditions for operations (LCOs) had been addressed and administrative approvals and clearances had been obtained before initiating the work.
LC0 4.2.2d allows one of the bearing water makeup pumps to be inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> without the helium circulators being considered inoperable.
Repairs and a functional test of P-2105 were completed and the pump was restored to an operable status within the 24-hour grace period.
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Particular attention was given to ensuring the backup bearing water system, which provides a redundant source of bearing water makeup, was available and operable. The backup bearing water system is supplied from the' emergency feedwater system via a heat exchanger and filter. At low power levels, there is a greater differential pressure between the circulator's main water drain (related to reactor pressure) and the steam / water drain (related to circulator exhaust steam pressure).
This causes more water to be discharged through the' steam / water drain, and this water is not recycled to the bearing water system, because of its low pressure.
This increased water loss (approximately 28 gpm per circulator vs. approximately 4 gpm at full load) exceeds the capacity of P-2108,
" Emergency Bearing Water Makeup Pump, (40 gpm)," and thus the backup bearing water system was needed to provide this makeup at low power condition with P-2105 inoperable.
While verifying the backup bearing water system lineup, the NRC inspectors noticed a small leak (2-3 drops / minute).through a nozzle weld on the secondary (service water) side of E-2101', " Loop 1 Backup Bearing Water Cooler." The cooler was left in service until P-2105 was restored to operable status.
The Cooler E-2101 was then removed from service and the corroded weld was repaired.
Ultrasonic tests were performed on the nozzle, and no further problems were identified.
No violations or deviations were identified in this inspection area.
5.
Surveillance The NRC inspectors witnessed weekly control rod operability tests in accordance with SR 4.1.1.b.1/2-W/4.1.2.A.3-W/5.1.1.b-M.
This test involves deenergizing the scram brake for an individual control rod drive for approximately nine to ten seconds and recording the distance the control rods dropped in that time.
Additionally, control rod position instrumentation operability was checked by comparing digital and analog indications.
Back EMF readings are also taken on each control rod drive in conjunction with the partial scram test.
The surveillance procedure was reviewed for conformance to Technical Specification requirements and to verify proper licensee review and approval.
The inspectors verified the test instruments were calibrated and observed the conduct of the surveillance test. The test results were reviewed and verified to be within the acceptance criteria.
The NRC inspectors also witnessed the retest of PV-22167, " Loop 1, Main Steam Power Pop," following maintenance which replaced the solenoid assembly on the valve operator. SSR 87505133 was reviewed along with Surveillance Procedure SR 5.3.3-A1X to verify proper requirements and approvals. On the first attempt of this test, the valve functioned properly, but the open position indicating light on the control board did not work. The limit switches on the valve were adjusted and the valve was retested satisfactorily.
No violations or. deviations were identified in this inspection are....
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6.
Licensee Action on 10CFR 21 Reports
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The NRC regional office has provided the licensee with several Part 21 reports. The licensee has not normally received these reports directly, but the information in the reports is often distributed to the licensees by generic letters, information notices, or bulletins.
These reports were provided to the licensee in advance of other notification to enable earlier evaluation by the licensee.
Item R86-003, " Terry Corporation Defective Emergency Head Lever Supplied for Auxiliary Feed Pump," does not apply to FSV.
This item is considered closed.
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Licensee Action on IE Bulletins and Generic Letters (Closed) IE Bulletin 79-001 and Generic Letter 84-024.
These documents related to Environmental Qualification of Class 1E are important to safety electrical equipment.
This area was the subject of several NRC inspections to review licensee action to meet the requirements of 10 CFR 50.49.
The inspection effort culminated with NRC Inspection Report 50-267/87-12, which closed the last remaining EQ issues.
The Bulletin and Generic Letter are considered closed.
8.
ESF System Walkdown The NRC inspectors performed a complete walkdown of the emergency feedwater and emergency condensate systems to verify their status and operability.
Applicable sections of the FSAR, Technical Specifications, and reference design manual were reviewed to ensure familiarity with the system and requirements.
The licensee's system lineup procedure and P&I drawings were utilized to trace the systems and to check for agreement with the as-found configuration.
Included in the walkdowns were:
Observations of equipment conditions and items which might degrade
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A check of instrumentation properly valved in and functioning.
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Verification of valves in their proper position, sealed as required,
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identified correctly with metal tags.
The overall condition of these systems was good. With the exception of some minor discrepancies which had been identified previously by the
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licensee, the NRC inspectors found no conditions which would impact system performance or operability.
No violations or deviations were identified in this inspection area.
9.
Plant Operations Review Committee The NRC inspectors attended a plant operations review committee (PORC)
meeting on May 19, 1987.
There were 45 items on the agenda and the meeting lasted 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 10 minutes.
The NRC inspectors observed the
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amount of discussion each item received to be fairly proportional to'its-relative safety significance.
The PORC generally used the engineering / licensing safety evaluation of an issue as a basis for determining if it is an unreviewed safety question by_ either agreeing or disagreeing with that safety evaluation.
There were a significant number of less-than-vital safety issues on the PORC agenda which could possibly have been addressed at a subcommittee level.
(i.e., editorial or typographical changes).
After the meeting, the NRC inspectors discussed
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this with the PORC chairman, who agreed that utilizing subcommittees to
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handle less.significant safety issues would enhance the review process and allow the PORC to focus more time on safety concerns.
He indicated to the NRC inspectors that the program and associated Technical Specifications
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are being revised and will be formally submitted to the NRC at a later date.
No violations or. deviations were identified in this inspection area.
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10. Management and Exit iteeting i
Several meetings were held between the NRC inspectors and licensee senior
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and executive management.
Licensee progress to meet regulatory i
requirements for operation at power evals up to 82 percent of rated power were. reviewed.
An exit interview was conducted on June 2, 1987; it was attended by those personnel indicated in paragraph 1.
At this meeting, the NRC inspectors reviewed the scope and findings of the inspection.
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