IR 05000269/1981019
| ML15224A444 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/30/1981 |
| From: | Bryant J, Jape F, Myers D, William Orders NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15224A443 | List: |
| References | |
| 50-269-81-19, 50-270-81-19, 50-287-81-19, NUDOCS 8110200566 | |
| Download: ML15224A444 (8) | |
Text
UNITED STATES R
o0 NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-269/81-19, 50-270/81-19 and 50-287/81-19 Licensee:
Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name:
Oconee Nuclear Station Docket Nos. 50-269, 50-270 and 50-287 License Nos. DPR-38, DPR-47 and DPR-55 Inspection at Seneca, South Carolina Inspectors:
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F. Jape, 5enior F sident Inspector Date Signed 0?
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9 3 e1,9 W. Orders(/Resid t Inspector Date Signed D. Myers, R~gident Ynspector
'Dat Si ned Approved by:
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el3 4 J. C. BryanV/, Secti Chief, Divigion of Date Si ned Resident and Reactor Inspection SUMMARY Inspection on August 10 - September 10, 1981 Areas Inspected This routine, announced inspection involved 314 resident inspector-hours on site in the areas of plant operations, surveillance testing, maintenance observations, loose parts in reactor followup, LER review,,followup of previous enforcement items,and radioactive gas samplin Results Of the 7 areas inspected, no violations or deviations were identifie PDR ADOCK 05000269 c
DETAILS 1. Persons Contacted Licensee Employees
- J. E. Smith, Station Manager
- J. N. Davis, Superintendent of Maintenance
- J. N. Pope, Superintendent of Operations
- T. B.Owen, Superintendent of Technical Services
- T. Cribb, Licensing Engineer Other licensee employees contacted included 10 technicians, 15 operators, 6 mechanics, 11 security force members and 4 office personne *Attended exit interview Exit Interview The inspection scope and findings were summarized on September 10, 1981 with those persons indicated in paragraph 1 above. The unresolved item on
.radioactive gas sampling was discussed with and acknowledged by licensee management. Other inspection findings were acknowledged without significant commen.
Licensee Action on Previous Inspection Findings (Closed) Violation (269/81-2-2):. Failure to follow procedure. The corrective action described in Duke Power Company's (DPC) response, dated March 20, 1981, has been verified as completed by the inspecto (Closed) Violation (269/270/287/81-7-1): Failure to perform TS surveillanc DPC's June 2, 1981, letter addresses this issu Followup was completed by the inspecto All corrective actions have been incorporated within the plant administrative progra (Closed) Violation (270/81-7-2): Misaligned breakers. Corrective actions described in DPC's response, dated May 26, 1981, have been verfied as completed by the inspecto (Closed) Violations (287/81-10-1): Defeated relief valve. The licensee's response, dated July 17, 1981, was found acceptable and the corrective action on Units 1 and 3 have been completed. Action on Unit 2 is scheduled to be completed during the next refueling outag. Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia tions. New unresolved items identified during this inspection are discussed in paragraph 1.
Plant Operations The inspector reviewed plant operations throughout the report period, August 10 - September 10, to verify conformance with regulatory require ments, technical specifications and administrative controls. Selected portions of control room logs, shift supervisors logs, shift turnover records and equipment removal and restoration records for the three units were reviewed throughout the inspection period. Interviews were conducted with plant operations, maintenance, chemistry, health physics, and per formance personnel on day and night shift Activities within the control rooms were monitored during shifts and at shift changes. Actions and/or activities observed were conducted as prescribed in Station Directives. The complement of licensed personnel on each shift met or exceeded the minimum required Technical Specification Operators were responsibe to plant annunciator alarms and appeared to be cognizant of plant condition Plant tours were taken throughout the reporting period. The areas toured included but are not limited to the following:
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Turbine Building
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Auxiliary Building
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Units 1, 2 and 3 Electrical Equipment Rooms
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Units 1, 2 and 3 Cable Spreading Room
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Station Yard zone within the protected area During the plant tours, ongoing activities, housekeeping, security, equipment status and radiation control practices were observe On the evening of September 8, the inspector verified that motor vehicles parked inside the turbine building were adequately secure Oconee Unit 1 continued a refueling outage throughout the reporting period with no new major difficultie The analysis associated with the previously reported (Report 269/80-18) problems with the thermal shield bolts is ongoing with no new information to report at this tim Oconee Unit 2 operated at virtually full power from the beginning of the report.period until 11:30 p.m. on September 6, when, after a continuous run of 157 days, low oil levels in the 2B2 and 2A2 reactor coolant pump motors forced a maintenance shutdown. The unit remained at 1000 psig and 300 degrees F until September 9 jn anticipation of a short outage which would not require cold shutdow Due to high radiation levels inside the reactor building however, the unit was forced to go to cold shutdown to allow
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reactor building purg As the report period closes the unit is at cold shutdown, in preparation for the ensuing maintenanc Oconee Unit 3 operated at virtually full power from the beginning of the reporting period until 5:QB p.m. on August 15 when a turbine trip/reactor trip occurred which was caused by a turbine control oil leak. The leak was repaired, the unit was restarted and was placed on line at 3:07 a.m. the following day. The unit operated at full power until the morning of August 5 when a feedwater pump tripped initiating an ICS runback to 55%
power. The feedwater problem, a minor maintenance difficulty with a lube oil filter, was rectified and the unit was returned to full power where it remained until 8:53 a.m. on September 5 when, for as of yet Undiscernable reasons, an electrical generator lockout occurred resulting in a reactor'
trip. The unit remained shut down until the next day in an effort to ascertain the cause of the trip and repair a small leak inside the reactor building. The leak was repaired but extensive troubleshooting failed to reveal the cause of the trip. The unit was restarted and placed on line at 11:33 a.m. on September 5 only to trip at 11:44 a.m. as the result of a feedwater perturbation during power escalatio The perturbation was determined to have been caused by an ICS control module for feedwater control valve 3FDW-41. The module was replaced, the unit was restarted and reached full power at 4:00 p.m. on September *
All systems performed as expected during the reactor trips and the ICS runback resulting in relatively unremarkable incident Within the areas inspected no violations or deviations were identifie.
Surveillance Testing The surveillance tests detailed below were analyzed and/or witnessed by the inspector to ascertain procedural and performance adequac The completed test procedures examined were analyzed for embodiment of the necessary test prerequisites, preparations, instructions, acceptance criteria and sufficiency of technical conten The selected tests witnessed were examined to ascertain that current, written approved procedures were available and in use, that test equipment in use was calibrated, that test prerequisites were met, system restoration was completed and test results were adequat The selected procedures perused attested conformance with applicable Technical Specifications, they appeared to have received the required administrative review and they apparently were performed within the surveillance frequency prescribe.
Procedure Title Date IP/0/A/301/03D NI-4 IR Calibration 8/18/81
IP/O/A/305/03D RPS CH-D on-Line Test 8/18/81 IP/O/A/302/4B Incore Monitor Withdrawal 9/9/81 IP/O/A/360/3B Process Radiation Monitor System 9/9/81 R1A48 The inspector employed one or more of the following acceptance criteria for evaluating the above items:
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10 CFR
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ANSI N1 Oconee Technical Specifications
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Duke Administrative Policy Manual Of the areas inspected no violations or deviations were identifie. Monthly Maintenance Observation Maintenance activities were observed and reviewed throughout the inspection period to verify that activities were accomplished using approved procedures or the activity was within the skill of the trade and that the work was done by qualified personne Where appropriate, limiting conditions for operation were examined to ensure that while equipment was removed from service, the TS requirements were satisfied. Also, work activities, procedures, and work requests were reviewed to ensure adequate fire and radiation protection precautions were observed, and that equipment repaired was tested and properly returned to service. Acceptance criteria used for this review were as follows:
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Station directives 3.3.1, 3.3.2, 3.3.5, 3.3.11, 3.3.15
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Administrative Policy Manaul, Section 3.3 and Technical Specifications Maintenance activities observed or reviewed were:
Work Request 19852 Keowee Start Modifications 9/7/81 19640 Repack LP-32 8/27/81 Work Request 50943 3CS114 and 115 Repair 8/28/81 Work Request 18930 Repair of MS-84 9/5/81 Work Request 50942 Repair CS Valves 9/3/81 Outstanding work request #19175 of 8/10/81 to WR 19856 of 9/9/81 that were initiated by the operations group for Unit 3 were reviewed to determine that the licensee is giving priority to safety-related maintenance and not
allowing a degradation of system performance by developing a back log of work item Of the areas inspected no violations or deviations were identifie.
Review of Licensee Event Reports The inspector performed an in-office review of nonroutine event reports to verify that the report details met license requirements, identified the cause of the event, described corrective actions appropriate for the identified cause, and adequately addressed the event and any generic implication In addition, the inspector examined selected operating and maintenance logs, and records and internal incidents investigation report Personnel were interviewed to verify that the report accurately reflected the circumstances of the event, that the corrective action had been taken or responsibility assigned to assure completion, and that the event was reviewed by the licensee, as stipulated in the Technical Specification The following event repors were reviewed:
Report Number Title RO-269/81-7 Fire Barrier Breached Without Proper Fire Watch Maintained RO-269/81-10 TDEFWP Declared Inoperable RO-269/81-12 Hydraulic Snubber Inoperable RO-269/81-13 Deficiency Discovered in Normal Power Procedure RO-270/81-1, Non-Existence Flow to HPI Pump Motor Bearing Cooler RO-270/81-8 Solenoid Valve 2FDW-316 Inoperable RO-270/81-10 TDEFWP Declared Inoperable RO-270/81-11 Subcooling Monitor Inoperable RO-270/81-12 TDEFWP Inoperable due to Low Oil Level RO-287/81-4 Failure of 3FDW-105 to Close RO-287/81-5 Failure of ES Valve 3CS-5 RO-287/81-6 RPS High Pressure Trip out of Calibration RO-287/81-7 RB Personnel Hatch Inner Door Inoperable
.RO-287/81-1 One MDEFWP Inoperable RO-287/81-11 Mechanical Snubber Inoperable
RO-87/81-12 3PR-8 Failed in Closed Position RO-287/81-13 Breach of Fire Barrier in Control Room RO-269/80-34 EWST Level Indication Failure RO-269/80-36 EWST and Part of HPSW Loop Removed from Service RO-269/80-37 CBAST Pump Inoperable RO-269/80-38 Loss of Overhead Power Path from Keowee RO-269/80-39 Fire Detector String Removed from Service RO-270/80-21 TDEFWP Auto Start Circuit Failed RO-270/80-25 HPI Inoperable due to Motor Bearing Failure RO-270/80-26 LBAST Pump Inoperable RO-287/80-11 SG Cracked Studs, Primary Manway RO-287/80-12 Time Exceeded for TS Sampling of LBAST RO-287/80-16 Fire Detector String B-2 Out of Service RO-287/80-17 Fire Detector String No. 8 Inoperable RO-287/80-19 CRD Breaker Delays in Tripping RO-287/80-20 Breach of Fire Barrier, Cable Room Floor Training and Procedure for Station Blackouts Duke Power Company (DPC) response to NRC Generic Letter 81-04 dated 7/1/81 detailed the stations training and procedures for mitigation of a station blackout even NRC letter to DPC of 8/18/81 acknowledged the existence of the stations training and procedures for the event and delegated technical review to the Office of Inspection and Enforcemen Inspectors reviewed the 7/1/81 response, emergency procedures EP/O/A/1800/31 Loss of 3 KI Bus, EP/O/A/1800/25 Loss of 4160V Power and BWST, EP/O/A/1800/16 Loss of Power, and conducted interviews with training personnel on 8/27/8 The review verified that the station program was as stated in the licensee's response and that the program adequately addresses the applicable technical concerns listed in the generic letter. Modifi cations described in the response regarding the turbine driven emergency feedwater pump are ongoing and covered by the resident inspectors routine inspection progra.
Radioactive Gas Sampling On the morning of September 4, prior to day shift turnover a licensee health physics technician attached and aligned applicable equipment to facilitate taking a sample of the contents of an Oconee Unit 3 waste gas tank. The sampling technique involved connecting a piece of Tygon tubing to the gas tank and venting a volume of gas through a gas sample bottle to the waste gas vent heade The technician attached and aligned the applicable equipment and departed the area in order to participate in shift turnove In the interim in which the first technician left and another came to retrieve the sample bottle, the Tygon tubing parted, resulting in an inadvertent gas release to the auxiliary building and ultimately to the atmosphere of 1.13 curies of noble ga Inspector perusal of the applicable procedure, HP/O/B/1000/60A, revealed a lack of specificity in that the details of the sampling procedure are, at best, spars The inspector discussed his concerns with the licensee who in turn stated that the referenced procedure is intentionally non-specific to allow the exercise of the skill of the trade, specific training, and other general directives. The inspector will analyze the reference training and directives to determine their adequac The licensee is currently reviewing the procedure and technique to determine if changes need be mad This item is unresolved as of the end of this report perio (Unresolved item 81/19-01)