IR 05000454/1987043
| ML20147C392 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/08/1988 |
| From: | Hinds J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20147C368 | List: |
| References | |
| 50-454-87-43, 50-455-87-40, NUDOCS 8801190202 | |
| Download: ML20147C392 (6) | |
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I U.S. NUCLEAR-REGULATORY COMMISSION
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- REGION III Reports No.
50-454/87043(0RP); 50-455/87040(DRP).
Docket Nos.
50-454;;50-455 Licenses No. NPF-37; NPF-66 Licensee:
Commonwealth Edison Company
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Post Office Box 767 Chicago, IL 60690
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Facility Name:. Byron Station, Units 1 and 2 Inspection At:
Byron Station, Byron, Illinois Inspection Conducted:
December 1 through 31, 1987 Inspectors:
P. G. Brochman N. V Gilles
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Approved By:
J.
Hinds, Jrry f ef 01 06 61S
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Reactor Projects Section IA Date Inspection Summary
Inspect; n_from December 1 through 31, 1987 (Report Nos. 50-454/87043(DRP);
50-4SS/87040(DRP)
l Areas Inspected:
Routine, unannounced safety inspection by the resident inspectors of licensee action on previous inspection findings; bulletins; Licensee Event Reports (LERs); operations summary; training; local leak rate testing; surveillance; maintenance; operational safety; and event followup.
- Results: No violations or deviations were identified, nor were any items identified which could affect the public's health and safety.
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l DETAILS 1.
Persons Contacted Commonwealth' Edison Company-R. Querio, Station Manager
- R. Pleniewicz, Production Superintendent R. Ward, Services Superintendent W. Burkamper,- Quality Assurance Superintendent
- T. Joyce, Assistant Superintendent, Operating G. Schwartz, Assistant Superintendent, Maintenance L. Sues, Assistant Superintendent, Technical Services D. St. Clair, Assistant Superintendent, Work Planning T. Higgins, Operating Engineer, Unit 0 J. Schrock, Operating Engineer, Unit 1 D. Brindle, Operating Engineer, Unit 2 T. Didier, Operating Engineer, Rad-Waste
'F. Hornbeak, Senior Staff Engineer M. Snow, Regulatory Assurance Supervisor
- R. Flahive, Technical Staff Supervisor S. Barret, Radiation / Chemistry Supervisor P. O'Neil, Qtility Control Supervisor
- G. Stauffer, Regulatory Assurance Assistant Supervisor W. Pirnat, Regulatory Assurance Staff
- E. Zittle, Regulatory Assurance Staff
- W. Dean, Nuclear Safety Group
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The inspector also contacted and interviewed other licensee and contractor personnel during the course of this inspection.
- Denotes those present during the exit interview on December 31, 1987.
2.
Action on Previous Inspection Findings (92701)
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(Closed) Open Item (454/85042-03(DRP)):
Corrections to Final Safety
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Analysis Report (FSAR) Figure 6.3-2a.
The inspector reviewed Amendment No. 49 to the Byron FSAR and verified that the. valve identification and
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injection positions for the valves labeled as "22, 23, 24, 25, and 26" in FSAR Figure 6.3-2a were correctly revised.
Based on this action, this item is considered closed.
3.
Licensee Event Report Followup (90712)
(Closed) LER (455/87020-LL)):
An in-office review of one LER was conducted to determine that the reportability requirements were fulfilled, that immediate corrective action was accomplished, and that corrective i
l-action to prevent recurrence had been accomplished in accordance with l
Technical Specifications.
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LER No.
. Title 455/87020
_ Unanticipated water discharge into the primary system, from the safety injection (SI) accumulators due to a
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procedural inadequacy.
No violations or deviations were identified.
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4.
Review of NRC Compliance Bulletins (25026)_
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(0 pen) Bulletin (454/87002-BB; 455/87002-88):
Inspection of fasteners for applicable material specifications.
The inspector witnessed the collection of a random sample, in accordance with the guidance provided in Temporary Instructio* 2500/26, of steel fasteners which are to be tested for their chemi al and material properties.
The licensee will document the results of the testing in its response to the bulletin.
The review of this bulletin will be completed after the licensee's response has been issued.
No violations or deviations were identified.
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Summary of Operations
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Unit 1 operated at pcwer levels up to 98% for the entire repart period.
Unit 2 was shut down for a scheduled surveillance outage for the majority of the report period.
Following~ completion of the outage, the unit was taken critical at 1:54 p.m. on December 21, 1987, three days ahead of the
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original outage schedule.
The unit was connected to the grid at 2:33 a.m.
on December 22, 1987.
Unit 2 operated at power levels up to 95% for the rest of the report period.
6.
Training (41400 and 41701)
The effectiveness of training programs for licensed and nonlicensed personnel was reviewed by the inspectors during witnessing of the
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licensee's performance of routine surveillance, maintenance, and operational activities and during review of the licensee's response to events which occurred during December 1987.
Personnel appeared to be knowledgeable of the tasks being performed, and nothing was observed which indicated ineffective training.
No violations or deviations were identified.
7.
Containment Local Leak Rate Testing (LLRT) (61720)
The inspectors witnessed performance of portions of the LLRT procedures in order to verify that testing was conducted in accordance with the technical specifications and procedural requirements, that t.est data was
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properly recorded, that test equipment was properly calibrated, and that the performance of licensee personnel conducting the tests demonstrated an understanding of assigned duties and responsibilities.
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During observation of the LLRT for containment isolation valves in the steam gererator blowdown system, the inspector noted that the pressure gage being used on the testing rig had exceeded its calibration date.
The inspector informed the lead test engineer of this fact, and the test engineer'promptly halted the test and located another pressure gage, which was within its calibration interval. The old gage was removed and replaced with the new ont, and the LLRT was repeated for the valves in question. A review of records indicated that. the gage had also been used earlier that day for testing several other valves. A post-calibration test was subsequently performed on the pressure gage, and it was found to be within the its required accuracy; consequently, repeating the LLRTs was not required for the valves which had been tested with this gage.
The inspectors discussed this matter with licensee management, and based on the prompt corrective actions initiated by management, the NRC has decided not to take any enforcement action for this event.
No violations or deviations were identified.
8.
Monthly Surveillance Observation (61726)
Station surveillance activities of the safety-related systems and components listed below were observed or reviewed to ascertain that they were conducted in accordance with approved procedures and in conformance with Technical Specifications.
2C5009 valve timing
The following items were considered during this review:
the limiting conditions for operation were met while affected components or systems
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were removed from and restored to service; approvals were obtained prior to initiating the testing; testing was accomplished in accordance with approved procedures; test instrumentation was within its calibration interval; testing was accomplished by qualified personnel; test results conformed with Technical Specifications and procedural requirements and were reviewed by personnel other than the individual directing the test; and any deficiencies identified during the testing were properly documented, reviewed, and resolved by appropriate management personnel.
No violations or deviations were identified.
9.
Monthly Maintenance Observation (62703)
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Station maintenance activities of the safety-related systems and components listed below were observed or reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides, I
and industry codes or standards and in conformance with Technical Specifications, Replacement of the solenoid for valve 2FWOO9A l
Meggering of the 28 diesel generator
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The'following. items were c'onsidered during this review:
the limiting conditions for operation were met while components or systems were removed from and restored to service; approvals were obtained prior to initiating the 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 properly certified; radiological controls were implemented; and fire prevention controls were implemented.
Work requests were reviewed to determine the status of outstanding jobs and to assure that priority is assigned to safety-related equipment maintenance which may affect system performance.
No violations or deviations were identified.
10.
Operational Safety Verification (71707, 71709, and 71881)
The inspectors observed control room operation, reviewed apolicable logs,
and conducted discussions with control room operators during December 1987.
During these discussions and observations, the inspectors ascertained that the operators were alert, cognizant of plant conditions, and attentive to changes *n those conditions, and that they took prompt action when appropriate.
The inspectors verified the operability of selected emergency systems, reviewed tagout records, and verified the proper return to service of affected components.
Tours of the auxiliary, fuel-handling, rad-waste, and turbine buildings 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.
The inspectors verified by observation and direct interviews that the physical security plan was being implemented in accordance with the station security plan.
The inspectors observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls.
The inspectors also witnessed portions of the radioactive waste system controls associated with rad-waste shipments and barreling.
The observed facility operations were verified to be in accordance with the requirements established under Technical Specifications, 10 CFR, and administrative procedures.
No violations or deviations were identified.
11.
Onsite Followup of Events at Operating Reactors (93702)
The inspectors performed onsite followup activities for an event which occurred during December 1987.
This followup included reviews of
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operating logs, procedures, Deviation Reports, Licensee Event Reports (where available), and interviews with licensee personnel.
For the event, the inspector developed a chronology, reviewed the functioning of safety systems required by plant conditions, and reviewed licensee actions to verify consistency with procedures, license conditions, and the nature of the event.
Additionally, the inspector verified that the licensee's investigation had identified the root causes of equipment malfunctions and/or personnel errors and had taken appropriate corrective actions prior to restarting the unit.
Details of the event and the licensee's corrective actions developed through inspector followup are provided below:
Unit 1 - Unusual Event Jeclared due to Inoperable SI Accumulator At 4:09 a.m. on December 3, 1987, with reactor power at 98%, a low pressure alann was received for the 1C safety injection accumulator.
Technical Specification 3.5.1 requires that each Reactor Coolant System accumulator be operable with a pressure greater than 602 psig.
Attempts to restore accumult. tor pressure to greater than 602 psig were unsuccessful.
Technical Specification 3.5.1 requires that with one accumulator inoperable for greater than one hour, the unit be placed in hot standby (Mode 3) within the next six hours.
At 5:09 A.M. a power reduction to place the unit in Mode 3 was initiated, and an Unusual Event was declared.
By 5:52 a.m., the safety valve on the accumulator (1518855C) had been adjusted and the accumulator was repressurized to greater than 602 psig.
At 6:00 a.m. the Unusual Event was terminated, and the unit was returned to rated power.
No violations or deviations were identified.
12.
Exit Interview (30703)
The inspectors met with the licensee representatives denoted in Paragraph 1 at the conclusion of the inspection on December 31, 1987.
The inspectors summarized the purpose and scope of the inspection and the findings.
The inspectors also discussed the likely informational content of the inspection report with regard to documents or processe, reviewed by the inspectors during the inspection.
The licensee did not identify any such documents or processes as proprietary.
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