IR 05000483/1997021
| ML20199E630 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/27/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20199E627 | List: |
| References | |
| 50-483-97-21, NUDOCS 9802020209 | |
| Download: ML20199E630 (11) | |
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ENCLOSURE U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Docket No.:
50-483 License No.:
NPF-30 Report No.:
-50-483/97-21 Licensee:
Union Electric Company Facility:
Callaway Plant Location:
Junction Highway CC and Highway O Fulton, Missourt Dates:
December 7,1997, through January 17,1998 Inspectors:
D. G. Passehl, Senior Resident inspector F. L. Brush, Resident inspector
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l B. A. Smalldridge, Resident inspector. Wolf Creek l
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Approved By:
W. D. Johnson, Chief, Project Branch B ATTACHMENT:
Supplemental Information i
900202o2o9 900127
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{DR ADOCK 05000483 PDR i
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EXECUTIVE SUMMARY -
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Callaway Plant NRC Inspection Report 50-483/97-21 Operations An operations department self assessment report had good observations, conclusions,
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and recommendations.
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Maintenance Overall, the plant material condition was good. However, there were weaknesses in the
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p licensee's identification of emergent material condition deficiencies.
A maintenance department self assessment was thorough. The assessment team
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identified strengths and opportunities for improvement.
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Enaineerino
- The chemistry department procedure for adding ammonia to the reactor coolant system
was well-written. The procedure had proper safety precautions, limitations, and contingency actions. The Formal Safety Evaluation was thorough.'
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Areas of the auxiliary building not normally accessible because of potentially adverse
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radiological conditions were in good condition. Some minor weaknesses in
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housekeeping, component labeling, and valve packing leakage were noted.
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The briefing and radiological controls implemented for a containment entry were good.
- The purpose of the containment entry was to repair pressurizer vapor space sample
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inboard containment isolation Valve SJHV0012.
Installation of new security fancing and other security modifications were well controlled
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with proper compensatory measures.
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Reoort Details
- Summary of Plant Status The plant began the report period at 70 percent power. On December 9,1997, the licensee increased power to 72 percent. On December 22,1997, the licensee increased power to 74 percent.
I. Operations
Conduct of Operations 01.1 General Comments (71707)
i The inspectors conducted frequent reviews of ongoing plant operations. In general, the conduct of operations was professional and safety-conscious. Plant status, operating problems, and werk plans were appropriately addressed during daily turnover and plan-of-the day meetings. Plant testing and maintenanco requiring control room coordination were properly controlled. The inspectors observed several shift turnovers and noted rio problems. Control room operators were aware of equipment status and the reasons annunciators were lit.
Operational Status of Facilition and Equipment O2.1 Review of Eauinment Teacuts (71707)
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The inspectors walked down the following tagouts:
Workman's Protection Assurance W17792 - Turbine Driven Auxiliary Feedwater
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Pump PALO2; and Workman's Protection Assurance W17783 -Turbine Driven Auxiliary Feedwater
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Pump Trip and Throttle Valve FCHV0312.
The inspectors did not identify any discrepancies. The tagouts were properly prepared and authorized. All tags were on the correct devices and the devices were in the position prescritrd by the tags.
O2.2 Enaineered Safetv Feature System Walkdowns (71707)
The inspectors used Inspection Procedure 71707 to walk down accessible portions of
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the following engineered safety features and vital systems:
Auxiliary Feedwater Train A;
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Turbine-Driven Auxiliary Feeuwater Pump Subsystem; and
Essential Service Water Train B.
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Equipment operability, material condition, and housekeeping were acceptable.
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07 Quality Assurance in Operations 07.1 Reylew_of_Ocerations Deoartment Self-Assessment
a.
Inspection Scooe (71707)
The inspectors reviewed a recently completed self-assessment report for the operations department.
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Observations and Findinas A team of individuals from the Callaway, Arkansas Nuclear One, and Duke Power nuclear plants, and from the institute for Nuclear Plant Operations, conducted a self-assessment for the operations department from November 3-7,1997. The objectives included evaluation of:
procedure adherence, the adequacy of procedures and instructions, and the
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effectiveness of procedure implementation; management effectiveness and personnel performance;
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effectiveness and adequacy of improvement programs;
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whether control room activities were conducted in a professional manner; a
effectiveness of shift tumovers;
whether equipment was effectively operated, released, and returned to service
according to Technical Specification requirements, including maintaining a high degree of awareness for equipment damage and personnel safety; wnether the operations logs and documents completely and accurately described
pertinent sequences of events and activities; and whether communications are highly reliable and effective.
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The inspectors found that the self-assessment report had some very good c/oservations, conclusions, and recommendations. There were no significant deviations from NRC observations and conclusions documented in previous inspection reports.
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3-II. Maintenance M1 Conduct of Maintenance M1.1 General Comments - Maintenance a.
insoection Scoce (62707)
The inspectors observed or reviewed portions of the following work activities:
Work Authorization P603290 - perform periodic MOVATS testing of chemical and
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volume control system to safety injection Pump A suction isolation Valve EMHV88078; Work Authorization P609000 - change oil, inspect belts, and clean Emergency
Diesel Generator B starting air Compressor CKJ01D; Work Authorization W192722 - adjust position indication for the Pressurizer
Vapor Sample inboard Containment isolation Valve SJHV0012; and Work Authorization W191513 - Replace Pressunzar Vapor Sample Outboard
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Containment Isolation Valve SJHV0013.
b.
Observations and Findinas
The inspectors found no concerns with the maintenance observed. All work observed was performed with the work packages present and in active use. The inspectors
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frequently observed supervisors and system engineers monitoring job progress, and quality control personnel were present when required.
M1.2 General Comments - Surveillance a.
Insoection Scoce (61726)
The inspectors observed or reviewed all or portions of the following test activities:
Instrumentation and Control Loop Calibration / Functional Test Surveillance
Procedure ISL-BB-0T42) " Loop-Temp: Loop 2 Delta-T/Tavg," Revision 37; and Instrumentation and Control Loop Calibration Surveillance Procedure
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ISL-NF-NB02D," Loop Mise; NB02D Degraded & UV to LSELS," Revision 11.
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Observations and Findinas Surveillance testing observed during this inspection period was conducted satisfactorily in accordance with the licensee's approved programs and the Technical Specifications.
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a 4-M2 Maintenance and Material Condition of Facilities and Equipment M2.1 Review of Material Condition Durina Plant Tours -
a.
Insoection Scooe (62707)
The inspectors performed routine plant tours to evaluate plant material condition.
b.
Observations and Findings Overall, the plant material condition was good. The licensee's corrective maintenance work request backlog was low. As of December 31,1997, the licensee's statistics showed the number of nonoutage corrective maintenance work requests was 76. The number of nonoutage corrective maintenance work requests greater than 6 months old was 25. The licensee classified a maintenance work request as " corrective"if the work was on safety-related equipment or on equipment that affected power generation.
Although the licensee identified many material deficiencies and initiated the appropriate work requests, the inspectors identified some deficiencies not previously identified by the licensee. Some notable deficiencies are described below.
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The inspectors identified that the ultimate heat sink cooling tower Train A sump
heater elements were not properly heating the water in the ultimate heat sink cooling tower Train A sump. The heater elements prevent ice buildup to maintain
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an unobstructed path for essential service water retum flow. Although the Train A sump was not frozen, the licensee later found open circuits in two of the three heater elements. The licensee initiated action to repair the heaters.
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The inspectors identified that an argon gas cylinder was secured to a portable
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welding rig stored in the auxii.ary building. Request for Resolution 16086A,
" Placement of Welding Machines in the Auxiliary /Radwaste Building," allowed storage of the portable welding rig at that location. However, Request for Resolution 16086A had not evaluated securing the cylinder to the welding rig.
The licensee removed the gas bottle. The gas bottle had a cap installed as required and was chained to the welding rig. The rig was not in the vicinity of any safety-related equipment. The licensee was reviewing storage of other cutting and welding rigs with gas bottles.
The inspectors identified that auxiliary building demineralizer vault drain header
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upstream isolation Valve LFV0090 had boric acid packing leakage. This valve -
was not included in the licensee's boric acid leak tracking program. The licensee initiated action to clean the boric acid and appropriately track the valve.
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The inspectors identified a nitrogen gas packing leak on nitrogen sparging supply
to condensate storage tank isolation Valve APV0042. The purpose of the nitrogen sparge was to keep oxygen from entering the condensate system. The licensee repaired the leak.
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Conclusions The inspectors concluded that, overall, plant material condition was good. However, there were weaknesses in the licensee's identification of emergent material condition deficiencies.
M7 Quality Assurance in Maintenance Activities a.
Insoection Scone Q2707)
The inspectors reviewed a recently completed self assessment report for the maintenance department.
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Observations and Findinas A team of individuals from the Callaway, Arkansas Nuclear One, Grand Gulf, and South
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. Texas Project nuclear stations conducted a self-assessment for the maintenance department from December 8-12,1997. The objectives included evaluation of:
nuclear and personnel safety during maintenance activities;
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quality of work practices;
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. efficiency of work practices;
s worker identification and implementatior. of maintenance performance
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improvements; and personnel development.
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The inspectors found that the scope of the self assessment was thor. ugh. The assessment team identified strengths and opportunities for improvement. The inspectors did not identify any significant deviations from NRC observations and conclusions documented in previous inspection reports.
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-6-111. Engineering E8 Miscellaneous Engineering Issues (92903)
E8.1 (Ocen) Insoection Foll,^wo item 50-483/9714-03: review licensee actions associated with the axial offset anomaly.
On December 2,1997, the licensee began to add ammonia to the reactor coolant system as a means to mitigate the axial offset anomaly. The licensee determined that the most likely cause of the axial offset anomaly was a buildup of crud on the outside of the fuel pins in the upper spans of the core. The licensee also r'atermined that the crud contahed a high percentage of nickel. The licensee d stermined that the artmonis would act to dissolve the nickel compounds in a slow manner As the ammonia cissolved the nickel, the crud would undergo changes to release trapped boron and a;iow more power generation from the upper half of the core.
The inspectors reviewed Chemistry Technical Procedure CTP-BB-ST001, " Operation
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with Elevated Reactor Coolant System Ammonia Concentrations," Revision 1. The inspectors also reviewed the associated Formal Safety Evaluation. Procedure CTP 88-ST001 was well written, with the proper precautions, limitations, and contingency actions described. The Formal Safety Evaluation was thorough. The licensee determined that there was not an unreviewed safety question as a result of adding ammonia to the reactor coolant system.
l IV. Plant Suncort R1 Radiological Protection and Chemistry Controls R1.1 General Comments (71750; The inspectors observed health physics personnel, including supervisors, routinely touring the radiologically controlled areas. Licensee personnel working in radiologically controlled areas exhibited gooo radiation worker practices.
Contaminated areas and high radiation areas were properly posted. Area surveys posted outside rooms in the auxiliary building were current. The inspectors checked a sample of doors, required to be locked for the purpose of radiation protection, and found no problems.
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-7-R2 Status of Radiological Protection and Chemistry Facilities and Equipment-R2.1 Auxiliary Buildina Tour a.
lasc; Mon Scooe (71750)
The inspectors accompanied !icensee personnel on a tour of radiologically controlled -
areas in the auxiliary building that were not normally accessible with the plant at power.
b.
Observations and Findinas The inspectors found material condition to bo good. The radiologically controlled areas were generally clean, although some minor housekeeping problems were identified. The inspectors and licensee personne! noted a few valves which had boric acid packing leaks and a few valves that were not properly labeled. The licensee initiated the appropriate work requests and temporary labeling tags.
R4 Staff Knowledge and Performance R4.1 Reactor Buildina Entry at Power a.
Insoection Scooe (71750)
The inspectors attended the radiological protection briefing and observed the health physics technician's coverage of a reactor building entry at 74 percent power. This was to effect repairs on pressurizer vapor space sample inboard containment isolation Valve SJHV0012.
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Observations and Findinas The briefing, conducted by a health physics supervisor, was very thorough. The radiological hazards at the job site were fully explained. Health physics personnel issued proper dosimetry for the entry. The health physics technician at the job site ensured that personnel were aware of the dose leveis in the area. The technician also continuously monitored the area dose in the event that radiological conditions changed. Overall, the health physics support of the maintenance effort was good. The inspector did not note any problems.
S2 Status of Security Facilities and Equipment S2.1 Plant Security Modifications a.
Insoection Scooe (71750)
The inspectors observed contract personnel installing new security fencing and other security modifications.
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Observations and Findinas The work was well controlled and proper compensatory measures were taken when personnel were working in the perimeter exclusion zone. The inspectors also reviewed.
other aspects of planned security modifications with the Security Supervisor and did not have any concems.
Vi Management Meetings X1 Exit Meeting Summary The exit meeting was conducted on January 16,1997. The licensee did not express a position on any of the findings in the report.
The inspectors asked the licensee whether any materials examined during the inspection
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ATTACHMENT SUPPLEMENTAL INFORMATION
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J PARTIAL LIS.T OF PEF: SONS CONTACTED Licensee K. C; Day, Maintenance Supervisor M. S. Evans, Superintendent Health Physics l
R. E. Fernam, Supervisor Health Physics, Operations D. T. Fitzgerald, Superintendent, Security J. M. Gloe, Supervisor, Maintenance J. V. Laux, Maneger Quality Assurance J. A. McGraw, Superintendent, Engineering C. D, Naslund, Manager, Nuclear Engineering D. W. Neterer, Assistant Superintendent, Operations G. L. Randolph, Vice President, Nuclear M. A. Reidmeyer, Engineer, Quality Assurance Regulatory Support R. R. Roselius, Superintendent, Chemistry and Radwaste
- T. P. Sharkey, Supervising Engineer, Systems
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W. A. Witt, Superintendent, Systems Engineering INSPECTION PROCEDURES USED 61726 Surveillance Observations 82707 Maintenance Observations 71707-Plant Operations 71750 Plant Support Activities 92903 Followup - Engineering ITEMS DISCUSSED Discussed 9714-03 IFl Review actions associated with axial offset anomaly (Section E8.1)