IR 05000454/1992025
| ML20034F400 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/15/1993 |
| From: | Farber M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20034F394 | List: |
| References | |
| 50-454-92-25, 50-455-92-25, NUDOCS 9303030095 | |
| Download: ML20034F400 (8) | |
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t U.S. NUCLEAR' REGULATORY COMMISS10'i
REGION III
Report Nos. 50-454/92025(DRP); 50-455/92025(DRP)
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Docket Nos. 50-454; 50-455 License Nos. !PF-37; NPF-56
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Licensee:
Commonwealth Edison Company Opus West III
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1400 Opus Place Downers Grove, IL 60515
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Facility Name: Byron Station, Units 1 and 2 Inspection At:
Byron Site, Byron, Illinois Inspection Conducted: December 19, 1992 through February 1, 1993 Inspectors:
C. H. Brown W"L
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Approved By:fttMartin'J. Farber, Chief
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Reactor Projects Section IA Date inspection Summary Inspection from December 19.1992 throuch February 1.1993 (Recort Hos. 50-454/92025(DRP): 50-455/92025(DRP1).
Areas Inspected: Routine, unannounced safety inspection by ths resident inspector of actions on previous inspection findings, o;eratic al safety
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verification, onsite event followup,' current material ccnditic,. housekeeping
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and plant cleanliness, radiological controls, security, TI 2515-91 PWR moderator dilution, maintenance activities, surveillance activities, and fJel
handling.
Results: In the 11 areas reviewed no violations or deviations ere identified.
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The following is a summary of the licensee's performancs durir; this inspection period:
plant Operations The licensee continues to operate the units in a good ranner. The operatcrs maintain the plant within specified parameters during and afte-lcad follcaing
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maneuvers.
Unit I has been removed from the load follo-ing m>:e most of the '
report period as the core is at end-of-life and boron is at a'.ery' low concentration. The " dark board" is generally maintaine.
Go t.: operator
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performance was noted during off-normal conditions.
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9303030095 930219 ~
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Safety Assessment /0uality Verificatio_q The licensee's performance in this area during this inspection period was not evaluated due to the inspector's limited review of this area.
Maintenance and Surveillance The activities reviewed by the inspector were observed to be performed in an acceptable manner. The surveillances were performed in a timely manner and maintenance " rework" remains at a very low level.
Enaineerina and Technical Supoort The licensee's performance in this area during this inspection period was not evaluated due to inspector s limited review of this area.
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- V DETAILS
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1.
Persons Contacted Commonwealth Edison Company (CECO)
- K. Schwartz, Station Manager M. Burgess, Technical Superintendent
- M. Snow, Services Director T. Tulon, Operations Manager
- T. Gierich, Assistant Superintendent, Planning D. Brindle, Regulatory Assurance Supervisor P. Johnson, Maintenance Superintendent
- B. Wegner, Assistant Superintendent Operations
- R. Colglazier, Compliance Engineer
- P. Enge, NRC Coordinator
- W. Dean, Safety Quality Verification Engineer
- W. Dijstelbergen, Modification Design Supervisor
- A. Javorik, Technical Staff Supervisor
- S. Barrett, Radiation Protection Supervisor
- D. Johnson, Master Instrument Maintenance
- Denotes those attending the exit interview conducted on February 1, 1993.
The inspector also had discussions with other licensee employees, including members of the technical and engineering staffs, reactor and auxiliary operators, shift engineers and foremen, and electrical, mechanical and instrument maintenance personnel, and contract security
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personnel.
2.
Action on Previous inspection Findinas (92701 & 92702)
(Closed) Inspector Followup Item 454/92015-02(DRP); 455/92015-02(DRP):
Byron Station was notified that discrepancies in the type of Agastat "G" series relays installed at Byron were found during a walkdown inspection of a similar diesel generator control panel installation.
Byron Station
performed a similar inspection and identified the same sort of discrepancies:
standard duty relays were installed where design documents or the mant'facturer indicated a heavy duty relay.
Discrepancies were also identified in the non class IE circuits. The licensee's engineering department recommendations for the change-out of relays in question were performed.
The inspector reviewed the Onsite Review (OSR)92-102 that pertained to the operability assessment of the site's Emergency Diesel Generators and noted the similarity of the Part Numbers (Standard Duty Relay EGPDR-C2008-003 versus Heavy Duty Relay EGPDNR-C2008-003, just the one extra letter (N) in the relay type code). The inspector inquired into the use of this relay in other plant systems control circuits and if there were any similar installation problems. The licensee's review of
the safety related component list and the Byron Unified List did not
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identify any other systems using Agastat type'"EGP" or "EGPDR" relays.
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This item is considered closed.
No violations or deviations were identified.
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Plant Ooerations Unit 1 operated at power levels up to 100% in the load following mode.
In January the unit was removed from load following mode due to approaching the end of core life with low boron concentration.
Unit 2 operated at power levels up to 100% in the load following mode.
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a.
Operational Safety Verification (71707)
The inspector verified that the facility was being operated in conformance with the licenses and regulatory requirements, and that the licensee's management control system was effectively carrying out its responsibilities for safe operation.
On a sampling basis the inspector verified proper control room staffing and coordination of plant activities; verified operator adherence with procedures and technical specifications; monitored control room indications for abnormalities; verified that electrical power was available; and observed the frequency of plant and control room visits by station management.
The control room was noted to be prope j staffed and personnel continued to perform in a professional manner. Alarms and off normal conditions witnessed were quickly and effectively handled.
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Onsite Event Follow-uo (93702)
On December 14, 1992, during the performance of IBVS 6.3.3-15 FW Isolation Valve Partial Strokes, Valve IFW0090 failed'to return to its full open position after performance of the
"A" train partial stroke. Trouble shooting revealed that the valve was unable to be
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closed in the period allowed by Technical Specification (TS) LCO
3.6.3; a plant shutdown was required. The GSEP unusual event i
declaration and termination were discussed in the previous inspection report, 454/92022(DRP); 455/92022(DRP).
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The "A" train hydraulic solenoid was thought to be-leaking, resulting in the low hydraulic pressure which was unable to reopen the valve. The solenoid was replaced but the low pressure problem
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remained. The addition of 3 quarts of oil and pressurizing the
oil reservoir to " prime" the hydraulic. pump (normal method of.
priming the pump). corrected the low pump discharge pressure and the valve was reopened. The surveillance procedure was revised to clarify the oil level in the reservoir and priming of the oil pump. A complete inspection of'the hydraulic system of this valve i
is planned for the upcoming refueling outage.
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c.
Current Material Condition (71707)
The inspector performed general plant as well as selected system and component walkdowns to assess the general and specific material condition of the plant, to verify that Nuclear Work Requests (NWRs) had been initiated for identified equipment problems, and to evaluate housekeeping. Walkdowns included an assessment of the buildings, components, and systems for proper identification and tagging, accessibility, fire and security door integrity, scaffolding, radiological _ controls, and any unusual conditions. Unusual conditions included but were not limited to water, oil, or other liquids on the floor or equipment;
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indications of leakage through ceiling, walls or floors; loose insulation; corrosion; excessive noise; unusual temperatures; and abnormal ventilation and lighting. The material condition of both units has been well maintained.
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Housekeepina and Plant Cleanliness The inspector monitored the status of housekeeping and plant cleanliness for fire protection and protection of safety-related equipment from intrusion of foreign mattar.
The housekeeping in both units remains acceptable.
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Radioloaical Controls (71707)
The inspector verified that personnel were following health physics procedures for dosimetry, protective clothing, frisking, posting, etc. and randomly examined radiation protection instrumentation for use, operability, and calibration. The ALARA results continued to demonstrate the program's effectiveness.
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Security Each week during routine activities or tours, the inspector monitored the licensee's security program to ensure that observed actions were being implemented according to the approved security plan. The inspector noted that persons within the protected area displayed proper photo-identification badges and those individuals requiring escorts were properly escorted. The inspector also verified that checked vital areas were locked and alarmed.
Additionally, the inspector also observed that personnel and packages entering the protected area were searched by appropriate i
equipment or by hand.
No violations or deviations were identified.
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4.
Reaional Reauest (92701)
TI2515-94 PWR Moderator Dilution The region requested a review of T12515-94: Moderator dilution occurred.
at a plant because the Na0H tank gravity drained into the decay heat removal system. The calculations showed that a possible criticality could have resulted from this moderator dilution in a cold shutdown condition.
Licensees were requested to review their units for a similar
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occurrence.
Byron plant design does not cross-connect or inter-connect the containment spray system and the decay heat removal system except that the two systems have a common suction line from the containment recirculation sump. The common piping is protected from cross-connecting by interlocked isolation valves and check valves in each of the system's pump suction lines. The surveillances performed on the Na0H tank and associated piping are procedurally controlled through interlocked valves.
The possibility of a moderator dilution event occurring by this path appears to be very remote and is not specifically addressed in.the UFSAR. This TI is closed.
No violations or deviations were identified.
5.
Maintenance / Surveillance (62703 & 61726)
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Maintenance Activities (62703)
Routinely, station maintenance activities were observed and/or 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 also considered during this review:
approvals were obtained prior to initiating the work; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; and activities were accomplished by qualified personnel.
Portions of the following maintenance activities were observed and
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reviewed:
- NWR 84378 - Replace 1A Diesel Generator crankcase high pressure trip switch
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- NWR 886581 - Firewrap on diesel fuel day tank overflow lines for a minor change
- NWR B98061 - 2TZ-VD001BB, Damper dripping oil - repair
- NWR B98062 - 2TZ-VD001BA, Damper dripping oil - repair
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t Proper safety precautions were taken, required signatures were obtained and work areas were generally maintained.
b.
Surveillance Activities (61726)
During the inspection period, the inspector observed technical specification required surveillance testing and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that results conformed with technical specifications and procedure requirements and were reviewed, and that any deficiencies identified during the testing were properly resolved.
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The inspectors also witnessed portions of the following surveillances:
- 2BVS7.1.5-2
- Main Steam Isolation Valves Partial Stroke Test
- 280S8.1.1.2.A-1 - 1A Diesel Generator Monthly Surveillance Surveillances continue to be performed in a timely manner.
Procedures were followed and good communications were maintained.
No violations or deviations were identified.
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Fuel Handlina On several occasions the inspector witnessed the receipt and storage of new fuel in the fuel handling building. The inspector verified the appropriate documentation of new fuel and that station procedures were followed in unloading, lifting, moving, lowering, and inspecting new fuel assemblies. Appropriate cleanliness controls were implemented.
Efficient communications and coordination was noted between fuel handlers, crane operators, rad-chem technicians, and the fuel handling foremen facilitated the fuel handling operations. The assemblies were stored in designated new fuel storage positions.
No violations or deviations were identified.
7.
Report Review
During the inspection period, the inspector reviewed the licensee's Monthly Performance Report for December 1992. The inspector confirmed that the information provided met the requirements of Technical Specification 6.9.1.8 and Regulatory Guide 1.16.
The inspector also reviewed the licensee's Monthly Plant Status Report for November and December 1992.
No violations or deviations were identified.
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8.
Meetinas and Other Activities
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Exit Interview (30703)
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The inspector met with the licensee representatives denoted in paragraph I during the inspection period and at the conclusion of the
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inspection on February 1, 1993. The inspector summarized the scope and i'
results of the inspection and discussed the likely content of this
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inspection report. The licensee acknowledged the information and did.
not indicate that any of the information disclosed.during the' inspection
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could be considered proprietary in nature.
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