IR 05000483/1990015
| ML20062B575 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 10/18/1990 |
| From: | Mccormick J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20062B573 | List: |
| References | |
| 50-483-90-15, NUDOCS 9010250224 | |
| Download: ML20062B575 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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REGION III
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Report No.
50-483/90-15(DRP)
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l Docket No.
50-483 License No.
NPF-30 i
Licensee: Union Electric Company
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Post Office Box 149 - Mail Code 400
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L St. Louis, MO 63166 Facility Name: Callaway Plant, Unit 1 Inspection at: Callaway Site, Steedman, MO Inspection Conducted: August 16 through September 30, 1990
Inspectors:
B. L. Bartlett C. H. Brown C. J. Phillips D. Hartland A. T. Gody, Jr.
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W. McCormick-Barger A ting Chief,
/0//9 /40 Approved By:
Reactor Projects Section 3C Da t'e
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Inspection Sumrray Inspection from August 16 through September 30. 1990 (Report No. 50-483/90-15(DRP))
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Areas Inspected:
Routine unannounced safety inspections of plant operations, maintenance / surveillance, follow up of 10 CFR Part 21 reports, and a management meeting were conducted.
Results: Of the areas inspected, no violations or deviations were identified.
For this inspection period, the area of plant operations continued to be strong. Conservative, well planned activities were observed by the inspectors.
In the area of maintenance / surveillance, the preparations for the refueling outage were readily apparent; however, these preparations did not interfere with the normal plant evolutions.
In the area of safety assessment / quality verification, the normal quality verification activities were found to be performed well, with appropriate management follow up. The areas of security, emergency preparedness, and radiological controls were found to be strong based upon routine observations of facilities, equipment, and practices.
9010250224 90101e
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PDR ADOCK 05000483 Q
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OETAILS 1.
persons Contacted
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D. F. Schnell, Senior Vice President, Nuclear
- G. L. Randolph, General Manager, Nuclear Operations
- J. D. Blosser, Manager, Callaway Plant C. D. Naslund, Manager, Operations Support J. V. Laux, Manager, Quality Assurance J. R. Peevy, Assistant Manager, Operations and Maintenance W. R. Campbell, Manager. Nuclear Engineering M. E. Taylor, Assistant.N: nager, Work Control D. E. Young, Superintendent. Operations R. R. Roselius, Superintendent Health Physics T. P. Sharkey, Supervising Enginaer, Site Licensing G. J. Czeschin, Superintendent, Panning and Scheduling G. R. Pendegraff, Superintendent, Tecurity C. E. Slizewski, Supervisor, Qualit/ Assurance Program
- G. A. Hughes, Supervisor, Independer,t Safety Engineer Group
- J. C. Gearhart, Superintendent, Operttions Support, Quality Assurance C. S. Petzel, Quality Assurance Engineer J. A. McGraw, Superintendent, Design Control
- Denotes those present at one or more exit interviews.
In addition, a number of equipment operators, reactor operators, senior reactor operators, and other members of the quality control, operations, maintenance, health physics, and engineering staffs were contacted.
2.
plant Operations (71707) (71710)
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Operational Safety Verification Inspections were routinely performed to ensure that the licensee conducted activities at the facility safely and in conformance with regulatory requirements. The inspections focused on the implementa-tion and overall effectiveness of the licensee's control of operat-ing activities, and on the performance of licensed and non-licensed operators and shift technical advisors.
The inspections included direct observation of activities, tours of the facility, interviews and discussions with licensee personnel, independent verification of safety system status and limiting conditions of operation (LCO), and reviews of facility procedures, records, and reports. The following items were considered during these inspections:
Adequacy of plant staffing and supervision.
- Control room professionalism, including procedure adherence, operator attentiveness, and response to alarms, events, and off-normal conditions.
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Operability of selected safety-related systems, including
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attendant alarms, instrumentation, and controls.
Maintenance of quality records and reports.
The inspectors observed that control room supervisors, shift technical advisors, and operators were attentive to plant
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conditions, performed frequent panel walkdowns, and were responsive to off-normal alarms and conditions.
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Off-shift Inspection of Control Room j
The inspectors performed routine inspections of the control room f
during off-shift and weekend periods, including inspections between the hours of 10:00 p.m. and 5:00 a.m.
The inspections were
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conducted to assess overall crew performance and, specifically,
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control room operator attentiveness during night shifts.
The inspectors determined that both licensed and non-licensed operators were attentive to their duties, and that the administrative controls relating to the conduct of operation were being adhered to, c.
Plant Material Conditions / Housekeeping
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The inspectors performed routine plant tours to assess material
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conditions within the plant, ongoing quality activities, and plantwide housekeeping.
The inspectors also accompanied the
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licensee's management on monthly plant tears.
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Radiological Controls The licensee's radiological controls and practices were routinely
observed by the inspectors during plant tours and during the
inspection of selected work activities.
The inspection included direct observations of health physics (HP) activities relating to raciological surveys and monitoring, maintenance of radiological i
control signs and barriers, and contamination and radioactive waste l
controls. The inspection also included a routine review of the
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licensee's radiological and water chemistry control records and reports.
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Security i
Each week during routine activities or tours, the inspectors monitored the licensee's security program to ensure that observed actions were being implemented according to their approved security plan. The inspectors noted that persons within the protected area
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displayed proper photo-identification badges and those individuals l
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requiring escorts were properly escorted.
The inspectors also i
verified that checked vital areas were locked and alarmed.
Additionally, the inspectors also verified that observed personnel and packages entering the protected area were searched by appropriate equipment or by hand.
At the end of the inspection period, the licensee had initiated a planned
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refueling outage.
During tha refueling outage, the plant was required to go to a reduced inventory or mid-loop operation for needed plant maintenance.
Prior to the start of the refueling outage, the inspectors verified that for mid-loop operations:
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Containment closure capability was maintained
At least two independent, continuous temperature indications representative of core exit conditions were operable
At least two independent, continuous water level indications were operable
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Unnecessary water level perturbations were avoided
At least two additional means of adding water to the reactor were I
available
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The order in which nozzle dams were placed was properly specified
"rmal and alternate power supplies to vital busses were available The inspectors' review of the licensee's preparation and conduct of reduced inventory activities determined that the licensee is aware of the safety significance of mid-loop operations and had taken appropriate
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safety measures to compensate.
No violations or deviations were identified.
3.
Maintenance / Surveillance (62703) (61726)
Selected portions of the plant surveillance, test, and maintenance activities on safety-related systems and components were observed or i
reviewed to ascertain that the activities were performed in accordance l
with approved procedures, regulatory guides, industry codes and-standards, and the Technical Specifications.
The following items were considered during these inspections: _ the_ limiting conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibration was performed prior to returning'
the components or systems to service; parts and materials that were used were properly certified; and appropriate fire prevention, radiological, and housekeeping conditions were maintained.
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Maintenance
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The reviewed maintenance activities included:
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Work Reouest No.
Activity I
I P457136 Detension and remove reactor vessel head
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studs.
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R136285 Perform MOVATS testing on valve BB-HV-00130, reactor coolant pump "A" thermal barrier cooling water.
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l W136604 Remove and repair power operated relief valve (PORV) BB-PCV-0455A.
W124652 Remove and repair PORV BB-PCV-0456A.
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W481346 Replace insulating link in feeder breaker to
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DSGN018.
W129879 Diesel generator KKJ018 replace gasket on i
S457873 Install and remove freeze seal.
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S453339 Verify set pressure of relief AB-V078 l
main steam line code safety, b.
Surveillance The reviewed surveillances included:
Procedure No.
Activity OSP-SF-00002 Control rod partial movement.
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ISF-AE-0L529 Functional test steam generator "B" narrow range level.
During the performance of ISF-AE-OL529, the technicians were observed to be well prepared and alert to plant conditions'. The technicians
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behaved in a professional manner and were careful to prevent mistakes I
prior to executing each step.
For example, one. technician went to
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adjust voltage on the wrong transmitter and the other technician-pointed it out.
No violations or deviations were identified, t
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4.
Follow up of Part 21 Reoorts (92701)
A letter dated January 28, 1990 to the NRC from Anchor / Darling valve company reported that backup rings furnished in spare parts of. seal kits and, possibly, in the 25 gallon per minute four-way valve of the feedwater isolation valve actuators were made of Buna N instead of Viton.
The licensee tested the seal kits and a spare actuator that were on hand by using a specific gravity test that wts recommended by the vendor.
The materials were found to be satisfactory.
The licensee also tested a seal kit that was part of a complete valves actuator overhaul kit and found a backup ring of the wrong material. The licensee performed a 10 CFR Part 21 evaluation and determined another report was unnecessary, since Anchor / Darling had reported the problem already. An engineering analysis was performed to determine operability of the actuators that were installed, in the event that they have rings made of the wrong materials.
It was determined that monthly stroke time tests would detect any degradation in performance and, if backup rings of the wrong material existed in the installed valve actuators, it would not affect operability.
The licensee has work requests outstanding to overhaul AE-FV0040 and AE-FV0042. The work includes testing the backup rings that exist in
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these valves.
The licensee also has work requests outstanding to open AE-FV0039 and AE-FV0041 to test the backup rings.
The NRC received a letter, dated September 4, 1990, from Coltec Industries.
It stated that parts and instructions, required for an inspection of the engine driven lube oil pump bosses for cracks or breakage and to change all of the adapters to a straight thread design, had been shipped to the Callaway plant. The licensee was not listed on the distribution for this letter. The September 4, 1990 letter referenced an April 9,1990 letter that stated Coltec's course of action for these inspections. The licensee was unaware of any inspections to be performed by Coltec Industries, of any problems with the diesel lube oil pumps, or of any shipments of parts and instructions.
It was speculated that the problems may have been corrected during construction. The licensee has written a work request to have the parts inspected for proper installation and leakage during the Refuel IV Outage with a Coltec representative present.
5.
Management Meeting (30702)
On August 28, 1990, a management meeting, which was requested by the licensee, was held between Mr. G. L. Randolph, General Manager, Nuclear Operations, Union Electric Company and Mr. Edward Greenman, Director, Division of Reactor Projects, and their respective staffs. The meeting addressed recent plant events, the status of the Callaway design basis update, rotation and staffing plans, and a preview of what is planned for the refueling outage.
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Exit Meeting (30703)
.I The inspectors met with licensee representatives (denoted under Persons
Contacted) at intervals during the inspection period. The inspectors i
summarized the scope and findings of the inspection.
The licensee representatives acknowledged the findings as reported herein. 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 / processes as proprietary.
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