IR 05000155/1989006
| ML20247A643 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/15/1989 |
| From: | Jackiw I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20247A633 | List: |
| References | |
| 50-155-89-06, 50-155-89-6, IEIN-89-044, IEIN-89-44, NUDOCS 8905230229 | |
| Download: ML20247A643 (8) | |
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U.5 NUCLEAR REGULATORY COMMISSION
REGION III
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- Report.No. 50-155/89006(DRP)
Docket'No. 50-155 License Noi DPR-6-Licensee:
Consumers Power Company -
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_212 West' Michigan Avenue
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Jackson, MI 49201 Facility Name: Big Rock Point Nuclear Plant r
Insp'ection At:
Charlevoix, MI 49720 Inspection Conducted: March 26 through May 6, 1989 Inspectors:
E. Plettner E6 -O Date N. Williamsen E'#'U Date NOM Approved By:
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actor P jects Section 28 Inspection Summary
- Inspection ~on March 26 through May 6, 1989 (Report No. 50-155/89006(DRP)
Areas Inspected:
The inspection was routine, unannounced, and conducted by
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the Senior Resident Inspector and the Resident Inspector. The functional areas inspected consisted of the following: management meetings;' refueling preparations; surveillance activities including weekly, monthly, and pre-refueling tests on' various components; maintenance activities on various components including removing and replacing the'No. I circulating water pump and motor, cal.ibrating the wide range monitors, adjusting the gland seal packingL on the No. I reactor feedwater pump, and unloading the new reactor fuel assemblies; operational safety verification, including the liquid poison system; and licensee event reports.
Results: The licensee has demonstrated a desire to respond in a timely manner to issues and concerns presented to them by the NRC.
The management meetings, refueling preparations, surveillance, maintenance, and operational safety programs appeared to be performed in a manner to ensure public health and
safety. No significant safety items were identified in this report.
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8905230229 890516 gDR ADOCK 05000155 PDC
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.r DETAILS 1.
Persons Contacted
- T. Elward, Plant Manager
- R. Abel, Production and Performance Superintendent
- G. Withrow, Engineering Superintendent
- H. Hoffman, Maintenance Superintendent W. Trubilowicz, Operations Supervisor M. Bielinski, Senior Engineer, Plant Performance
- R. Krchmar, Acting Quality Assurance Superintendent
- D. Lacroix, Acting Nuclear Training Administrator
- P. Donnelly, Nuclear Assurance Administrator
- J. Beer, Chemistry / Health Physics Superintendent
- R. Alexander, Technical Engineer E. Zienert, Director Human Resources The inspectors also contacted other licensee personnel in the Operations, Maintenance, Engineering, Radiation Protection, and Technical Departments.
- Denotes those present at the exit interview.
2.
Management (30703)
The senior resident inspector conducted a conference call with the licensee and the project manager to discuss the changes in the licensee's Integrated Living Schedule Update Number 10. The discussion was informative and led to a better understanding'of what the licensee was trying to accomplish. A similar discussion was held between the senior resident inspector and the licensee on the Simulator Facility Plans.
3.
Refueling Activities (60710)
Preparations for refueling were observed / reviewed to ascertain that the activities were meeting approved procedures and were in conformance with Technical Specifications.
In preparation for the refueling outage scheduled for June 3,1989, the licensee procured a reload of twenty-two assemblies (or " bundles") of reactor fuel from the vendor. The resident inspector reviewed procedure MFHS-6, " Advanced Nuclear Fuel Unloading Procedure (Formerly RE-17)",
Rev. 9, dated March 30, 1989, and System Operating Procedure (SOP) 2,
" Refueling Operation", Rev.127, dated October 26, 1987, and found them adequate. The inspector verified that the prerequisites were met prior to unloading the fuel. The inspector observed the unloading, inspection, and storage of the fuel bundles during the three-day task. The task was performed in a professional manner and satisfied the acceptance criteria.
No violations or deviations were identified in this area.
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4.
Monthly Surveillance Observation (61726)
Station surveillance activities listed below were observed to verify that the activities were conducted in accordance with the Technical Specifications and surveillance procedures. The applicable procedures were reviewed for adequacy, test and process instrumentation was verified to be in their current cycle of calibration, personnel performing the tests appeared to be qualified, and test data was reviewed for accuracy and completeness. The NRC inspectors ascertained that any deficiencies identified were reviewed and resolved. The NRC inspectors observed the licensee's performance of the following surveillance tests on the indicated dates:
March 29, 1989, T30-29, " Reactor Depressurization System Cabinet Test (Sensor Cabinet B/ Actuation Cabinet 2)", Rev. 24, January 29, 1988.
April 5, 1989, T7-20, " Diesel Fire Pump Auto Start", Rev. 20, October 4, 1988.
April 7,1989, T180-01A, " Containment Ventilation Valves Leak Rate
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Test", Rev. 36, December 23, 1988.
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April 12, 1989, T90-17 " Control Room Caution Tag Ledger /JLB Quarterly Review", Rev. 3, January 13, 1989.
April 17, 1989, TR-07, " Fuel Handling Equipment Safety Check", Rev.16, February 2, 1989.
April 27, 1989, T30-14, " Monthly Core Spray Heat Exchanger Leak Test", Rev. 16, October 3, 1987.
May 3, 1989, T30-26, " Electric and Diesel Fire Pump L2 Module Test", Rev. 17, February 2, 1989.
May 3, 1989, T7-33, " Weekly Test of ASD System Equipment", Rev. 1, February 1, 1989.
l No violations or deviations were identified in this area.
5.
Monthly Maintenance Observation (62703)
i Station maintenance activities of safety related systems and components
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listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Specifications.
The following items were considered during this review:
the limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the
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work;. activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were
. performed prior.to returning components or systems to service; quality control records were maintained; activities were accomplished by' qualified personnel; parts and materials used were certified; radiological and fire prevention controls were implemented.
The resident inspectors did a detailed inspection of the control rod drive hydraulic pump room and the fuel pool heat exchanger room. Some minor deficiencies were reported to the licensee who took corrective actions.
The licensee had performed sufficient decontamination to allow entry into the rooms without special clothing. This was an improvement in the material condition of the plant.
On April 4, 1989, the licensee re-installed the No. I condenser circulating water pump and motor which had been removed for repairs. The pump was tested for operability, failed the test, and was removed for further
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repair. The repair involved the reversing of the pump impeller. The equipment was re-installed, successfully tested, and returned to service.
Work requests were reviewed to determine the status of outstanding jobs and to assure that priority was assigned to safety related equipment maintenance which may affect system performance.
The NRC inspectors observed the licensee's performance of the following maintenance work orders on the indicated dates:
April 3, 1989, No. 89-RDS-0007, dated February 1, 1989, to fabricate a topworks test facility for Target Rock RDS valves on trains C and D.
April 4, 1989, No. 89-CWS-0017, dated April 4, 1989, to install the No. 1 (condenser) circulating water pump and motor.
April 5,1989, No. 89-FPS-0049, dated March 7,1989, to replace the battery lead on the diesel fire pump battery bank "B".
April 7,1989, No. 89-VAS-0047, dated April 5, 1989, to repair a heating and cooling air-handling unit inside containment.
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April 10, 1989, No. 89-NMS-0036, dated April 10, 1989, to calibrate the the wide range neutron monitors.
April 7, 1989, No. 89-CWS-0022, dated April 7, 1989, to remove.the No.1 circulating water pump and motor.
April 15, 1989, No. 89-FWS-0033, dated April 15, 1989, to adjust the packing on the inboard gland seal of the No. I reactor feedwater pump, to minimize steaming.
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April 19, 1989, No. 89-FWS-0034, dated April 18, 1989, to clean the instrument air-nozzles in the feedwater control system.
-April 20, 1989, No. 89-FHS-0004, dated February _ 16, 1989, to unload, inspect, and store twenty-two new fuel assemblies.
No violations or deviations were identified in this area.
6.
Operational Safety Verification (71707)
The NRC inspectors observed control room operations, reviewed applicable logs, and conducted discussions with control room operators during the-inspection period.
Instrumentation and recorder traces were examined for abnormalities and discussed with the control room operators, as were the status of cor. trol room annunciators. Reviews were conducted to confirm that the required leak rate calculations were performed and within Technical Specification -limits. A system walkdown was performed to verify the operability of.the Liquid Poison system. Tours of the.
containment sphere and turbine building were conducted to observe plant equipment conditions,' including potential fire hazards, fluid leaks, and excessive vibrations and to verify that maintenance requests had been initiated for equipment in need of maintenance. Radiation protection controls were inspected, including radiation work permits, calibration of radiation detectors, and proper posting and observance of radiation-and/or contaminated areas. The inspectors observed site security measures including access control.of personnel and vehicles, proper display of identin cation badges for personnel within the protected area, and compensatory measures when security equipment had a failure or -
l impairmer.t.
On April 16, 1989, with the reactor at normal power, steam pressure began to increase, resulting in the automatic actuation of the turbine bypass valve. The control room staff took appropriate corrective actions to stabilize plant conditions. There were no safety system actuations. The
' licensee investigated and determined that one of seven steam admission valves had failed in the closed' position. The failed valve did not compromise safety but reduced the electrical power output. The licensee decided to continue operating at reduced power and is making plans to repair the failed steam admission valve during the forthcoming outage scheduled for June 3,1989.
The NRC issued Information Notice No. 89-44, " Hydrogen Storage on the Roof of the Control Room", on April 27, 1989. The purpose of this notice
.was to alert recipients to potential generic problems pertaining to the storage of hydrogen in the vicinity of safety-related structures and in the vicinity of safety-related structures and/or where either the l.
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hydrogen storage or the discharge from hydrogen system pressure-relief valves are in the vicinity of air pathways into safety-related
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structures.
NRC Management requested the licensee to promptly respond to the qt.estions in the information notice. The following response was verified by the resident inspectors: (a) the hydrogen storage facility is external to the turbine building (b) the control room ventilation intake structure is far removed from the storage facility, (c) the minimum distance between the hydrogen bottle storage area and any safety-related equipment is about forty feet and is separated by a concrete wall.
No violations or deviations were identified in this area.
7.
Systemrtic Assessment of Licensee Performance (SALP) Conference 0n March 28, 1989, Messrs. C. Norelius, Deputy Regional Administrator, W. Forney, Deputy Division Director of the Division of Reactor Projects, I. Jackiw, Section Chief in the Division of Reactor Projects W. Scott, Licensing Project Manager, and E. Plettner, Senior Resident Inspector, conducted a SALP conference with the licensee at the Edgewater Inn in Charlevoix, Michigan. A plant inspection was conducted prior to the conference with NRC management noting an improved material condition of the plant.
Consumers Power Company was represented by Messrs. G. Heins, Senior Vice President, R. Nicholson, Vice President of Energy Supply Services, K. Berry, Director of Nuclear Licensing, and T. Elward, Plant Manager of the facility.
V6rious members of the plant staff were present along with interested members of the public including the press. The licensee responded positively and expressed a determination to continue plant improvement in all areas.
8.
Public Officials Meeting Regarding Big Rock Point Facility (94600)
On the evening of March 28, 1989, Mr. J. Foster, Acting Chief of State and Government Affairs, conducted a meeting with public officials within the vicinity of the Big Rock Point facility. NRC participants included Messrs. W. Forney, I. Jackiw, W. Scott, E. Plettner, and N. Williamsen.
The following public officials attended: Messrs. G. Gordon, City Manager of Petoskey, T. Postelnick, Director of Safety for Petoskey, R. Frykberg, City Manager of Boyne City, D. Halverson, Chief of Police for Charlevoix, L. Schomberger, Emergency Services Director for Emmet County, and D. Hahn, Michigan Division of Public Health. After brief presentations by the NRC staff, local officials asked a number of questdons in the general areas of radiological releases at the Big Rock Point facility, NRC's relationship with the licensee to insure objectivity of the inspectors, general safety
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of nuclear power plants, the Three Mile Island accident, plant life
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extension, low-level radioactive waste disposal, and emergency response.
The local officials indicated that the meeting was beneficial to them, and recommended such meetings be continued in the future.
9.
Licensee Event Reports Followup (92700)
Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that deportability requirements were fulfilled, timely immediate corrective action was accomplished, and corrective action to prevent recurrence haa been accomplished in accordance with Technical Specifications.
In addition, each event was evaluated for previous similar events, root cause, and potential generic applicability.
(Closed)LER 155/88001:
" Upscale /Downscale Reactor Trip - Personnel Error". On February 2,1988, a plant shutdown was in progress and the reactor power was near zero percent. A Reactor Protection System (RPS)
trip occurred, due to a combination of operator error in switching to the incorrect range of the nuclear monitoring system's picoammeters, and susceptibility of the picoammeters to electrical noise. All withdrawn control rods were inserted successfully.
No other engineered safety features were actuated by the trip. A new Wide Range Neutron Monitoring system was installed during the June,1988, refueling outage. The new system has proven to be more reliable. This LER is closed.
(Closed) LER 155/88002: " Manual Reactor Trip - Loss of Forced Recirculation Flow". On February 5, 1988, plant operators failed to properly synchronize the generator with the grid, resulting in the tripping of the 138 kV transmission breaker and both recirculation pumps.
Per procedure, the operators manually scrammed the reactor in response to the loss of forced recirculation flow. All withdrawn control rods were inserted successfully.
No other engineered safety features were actuated.
Inspection of all associated equipment (relays, breakers, transformers)
revealed no equipment problems.
Permission was given for restart and which was successfully completed on February 7, 1988.
This LER is closed.
(Closed) LER 155/88003: " Reactor Shutdown - High Primary System Unidentified Leak Rate". On February 7, 1988, a primary system leak rate
calculation determined an unidentified leak rate in excess of the one i
gallon per minute limit in the Technical Specifications. An " Unusual Event" was declared, timely notifications were made, and a reactor shutdown was initiated. Cold shutdown was achieved on February 8, 1988, terminating the Unusual Event. The leakage was from one of the reactor recirculation pump seal coolers.
The cause of failure was attributed to the age of the component which was twenty-six years. The failed cooler was replaced and the plant was successfully restarted on February 11.
This LER is closed.
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(Closed) Informational LER 155/88004: " Informational LER - Control of
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Limitorque Operator Lubricants".
The report was written to inform other licensees of a potential problem in interpreting Limitorque lubrication
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information during valve-operator overhauls.
In 1983, Limitorque specified Nebula EP-0 as the only approved lubricant for qualified safety-related operators.
However, the recommendation was intended fcr the main gear-box, only, and not the limit switch assembly. The licensee, unaware of the problem, used the same lubricant, Nebula EP-0,
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in both the gear-box and the limit switch assembly of three Limitorque operators. Subsequent analysis showed that Nebula EP-0 was acceptable for use in the limit switch assembly under the plant's environmental conditions. Limitorque recommended Beacon 325 or Mobil 28 be used in the limit switches. The licensee decided to implement the recommendation and l
replaced the limit switch lubricant in the three operators with Mobil 28.
Plant procedures were revised to reflect the correct information. This informational LER is closed.
(Closed) LER 155/88005:
" Reactor Depressurization Timers Out of Specification". Duririg the 1988 refueling outage on June 26, 1988, on of four timers in the Reactor Depressurization System (RDS) was found inoperable and two others had setpoints slightly above the required,
setpoint in the Technical Specifications. The failed timer was replaced and all timers were calibrated within specification. The RDS system operates on a two out of four logic scheme. Under the conditions described with one timer failed and two timers out of specification, a safety evaluatica was required to determine if a safety limit would have been exceeded Liuring a worst possible scenario. The evaluation concluded that no safety limits would have been exceeded. This LER is closed.
10.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1)
throughout the month and at the conclusion of the inspection period and summarized the scope and findings of the inspection activities. The licensee acknowledged these findings. The inspectors also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspectors during the inspection.
The licensee did not identify any such documents or processes as proprietary.
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