IR 05000010/1981003
| ML20003E349 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 03/23/1981 |
| From: | Jordan M, Reimann F, Tongue T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20003E348 | List: |
| References | |
| 50-010-81-03, 50-10-81-3, 50-237-81-05, 50-237-81-5, 50-249-81-03, 50-249-81-3, NUDOCS 8104030065 | |
| Download: ML20003E349 (7) | |
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(~)N U.S. NUCLEAR REGULATORY COMMISSION (
0FFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-10/81-03; 50-237/81-05; 50-249/81-03 Docket Nos.50-010; 50-237; Licenses No. DPR-02; DPR-19; 50-249 DPR-25 Licensee: Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
Dresden Nuclear Power Station - Units 1, 2, and 3 Inspection At: Dresden Site, Morris, IL Inspection Conducted:
Jan" ry 31, 1981 through February 27, 1981 pr <
- m Inspectors:
T. M Ton ue 3 - 4 - ri'/
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3~2]~S']
M. J Jordan V
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d pproved By:
F. b. Reimann, Acting Chief 3 - P 3 - d"/
Reactor Projects Section 1C Inspection Summary Inspection on January 31, 1981 through February 27, 1981 (Reports No. 50-010/81-03; 50-237/81-05; 50-249/81-03)
Areas Inspected: Routine, unannounced resident inspection of Operational Safety Verification', Monthly Maintenance Observation, Monthly Surveillance Observation, Licensee Event Reports Followup, Plant Trips, Surveillance During Refueling, Maintenance During Refueling, and Inspection During Long Term Shutdown. The inspection involved a total of 118 inspector-hours onsite by two NRC inspectors,' including 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> onsite during offshifts.
Results: Of the eight areas inspected, there were no items of noncompliance identified.
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DETAILS 1.
Persons Contacted
- D.
Scott, Station Superintendent
- R. Ragan, Operations Assistant Superintendent J. Eeingenburg, Maintenance Assistant Superintendent
- D.
Farrar, Administrative Services and Support Assistant Superintendent J. Brunner, Technical Staff Supervisor C. Sargent, Unit 1 Operating Engineer J. Wujciga, Unit 2 Operating Engineer
- M. Wright, Unit 3 Operating Engineer E. Budzichowski, Unit Support Operating Engineer D. Adam, Waste Systems Engineer
- G. Myrick, Rad-Chem Supervisor B. Saunders, Station Security Administrator E. Wilmer, QA Coordinator
- H. Cobbs, QA Engineer The inspector also talked with and interviewed several other licensee employees, including members of the technica) and engineering staffs, reactor and auxiliary operators, shif t engineers and foremen, electrical, mechanical, and instrument. personnel, and contract security personnel.
- Denotes those attending one or more exit interviews conducted on Februa ry 13, 1981 and February 27, 1981.
2.
Operational Safety Verification The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the month of January 31 through February 27, 1981. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified proper return to service of affected components. Tours of Unit 3 reactor bui,1 dings 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 inspector by obser-vation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan.
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The inspectors observed plant-housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the period of January 31 through February 27, 1981, the inspector walked down the accessible portions of the Unit 3 LPCI and Core Spray systems to verify operability. The inspector also witnessed portions of the radioactive waste system controls associated with radwaste shipments and barreling.
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These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative procedures.
No items of noncompliance were identified.
3.
Monthly Maintenance Observation Station afintenance activities of safety rela. d systems and ec=pcnents listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with technical specifica ices.
The following items were considered during this review:
the limiting cenditions for operation were met while cc=penents or syste=s were re=cved from service; approvals were obtained prior to initiating the work; ac-tivities were accomplished using approved procedures and were inspected as applicable; functional testing and/cr calibrations were perfor=ed prior to returning cczponents or systems to service; quality control recorcs were
=aintained; activities were accomplished by qualified personnel; parts
.and saterials used were properly certified; radiological centrols were i=ple=ented; and, fire prevention controls were i=plemented.
Work requests were reviewed to determine status of cutstanding jobs and to assure that priority;is assigned to safety related equipment =ainte-nance which =ay affect syste= perf ormance.
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The following maintenance activities were observed / reviewed:
Unit 3 - CRD Accumulator Star valve repacking.
No items of noncompliance were identified.
4.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the Unit 3 LPRM Calibration (TIP Traces), Units 2/3 Standby Gas Treatment System monthly 10-hour run and verified that testing.was performed in accordance with adequate procedures, that test instrumenta-tion was calibrated, that limiting conditions for operation were set, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications and procedure requirements and were reviewed by-personnel other than the individual directing the test, and that any deficiencies identified during the test-ing were properly reviewed and resolved by appropriate management personnel.
The inspectors also witnessed portions of the folicwing test activities:
Unit 3; LPRM Amplifier Gain Calibration, IRM Calibration surveillance, Half Scras Testing, R3M Surveillance, Unit 2/3 Calibration of the Of f-Gas Radiation Monitor.
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While observing LPRM calibrations (TIP Traces) on Unit 3, the Senior Resident Inspector (SRI) noted spiking on the TIP recorder from all five TIP units which could be observed on the TIP instrument.
Information from persons involved indicated the cause was due to the reccrder, but this did not explain the indication in the TIP instrument and raised the possibility of erroneous LPRM calibrations.
It was also found that the condition had existed fer about a year. Licensee personnel exchanged recorders with Unit 2, which eliminated the spiking problem. This is not a noncompliance but is a note worthy concern in that the problem existed for about a year and apparently went unchallenged by numerous personnel involved without considering faulty LPRM calibrations. This was discussed with the Station Superintendent who agreed with the concern.
No items of noncompliance were identified.
5.
Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviused to determine that reportability requirements were fulfilled, immediace corrective action was accomplished, and corrective actica to prevent recurrence had been accenplished in accordance with technical specifications.
LER's TITLE Unit 2 S0-18 EPCI Inboard Steam Isolation Valve failed to
.Close 80-23 Torus Vent Valves Failed to Open 80-25 Isolation Condenser Condensate Hi-Flow Trip Switch Setting High 80-26 Drywell Pressure Switch Found Valved Out 80-27 Diesel' Generator Low Collant Level 80-29 RWCU Line Leakage (weld failure)
On ' Feb rua ry 12, 1531, the licensee verbcIly reported exceeding an LCO requirement that temperature of the Standby Liquid Control (SBLC) Tank be maintained at greater than 83* F.
The inspectors reviewed and found the initial corrective actions to be adequate. Final corrective _ action will be reviewed during a future inspection. This is an open inspection item.
(50-249/81-03-01)
The licensee verbally reported an event, which occured on February 25, 1981, via ENS phone and to the resident inspectors-identifying an un-authorized.cirase of radioactive saterial.
The release was unsampled water-that resulted from simultaneously filling and discharging from the "A" Floor Drain Sample ' Tank. The resident inspectors reviewed the initial actions of stopping the discharge, sampling the tank, shutting the. manual fill valves-of the tank being Ilscharged and placing a cover J over' the. switch for selecting the tank to be filled, ~as adequate.
Initial
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evaluations by the SRI, Region III Specialists, and the licensee indi-cates that no radioactivity releases approaching technical specification or regulatory limits resulted from this event. Final evaluations of activity releases and licensee seasures to prevent future occurrences will be addressed in a future inspection report. This is an open item.
(50-249/81-03-02)
No items of nonc:mpliance were identified.
6.
plant Trips Following the plant trips on Unit 3 on February 23, 1981, the inspectors ascertained the status of the reactor and safety systems by observation of control room indicators and discussions with licensee personnel con-cerning plant parameters and emergency system status. The inspectors verified the establishment of proper communications and reviewed the corrective actions taken by the licensee.
.All systems responded as expected, and the plant was returned to opera-tien on February 23,.1981.
No items of noncompliance were identified.
7.
Surveillance - Refueling The inspectors observed the diesel generator surveillance and the 250-volt DC battery discharge testing on Unit 2 to verify that the tests were covered by properly approved procedures; that the procedures used were consistant with regulatory requirements, licensee co=mitments, and administrative controls; that minimum crew requirements were met, test prerequisites were completed, special test equipment was calibrated and
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in service, and required data was recorded for final review and analysis; that_ the qualifications of personnel conducting the test were adequate; and that the test results were adequate.
No items of noncompliance were identified.
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Maintenance'- Refueling The inspector verified maintenance procedures include administrative
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inspection / audit and signoff by QA or other licensee personnel; provisions-for operational testing following maintenance; provisions for special authorization and fire watch responsibilities for activities involving velding, open flame, and other ignition sources; reviews of material
' certifications; provisions for assuring LCO requirements were met -during repair; provisions for housekeeping during and following maintanence; and responsibilities for reporting defects to management.
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The inspector observed the maintenance activities listed below and verified work was accomplished in accordance with approved procedures and by qualified personnel.
Unit 2 Fuel Channeling Diesel Generator CRD Exchange-Mark I Containment Modification Feedwater Sparger Replacement Isolation Condenser Work 2B LPCI Heat Exchanger No items of noncompliance were identified.
9.
Inspection During Long Term Shutdown The inspector observed control room operations, reviewed applicable logs and conducted discussions with controi. room operators during the period of January 30 through February 27, 1981. The inspector verified surveil-lance tests required during the shutdown were accomplished, reviewed tagout records, and verified applicability of containment integrety.
Tours of Units 1 and 2 accessible areas, including exterior areas were made to make independent assessments of equipment conditions, plant conditions, radiological controls, safety, and adherence to regulatory requirements and to verify that maintenance requests had been initiated for equipment in need of maintenance. The inspector observed plant housekeeping / cleanliness conditions, including potential fire hazards, and verified implementation of radiation protection controls. The in-spector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan. The inspectors reviewed and verified the implementation of radio-active waste system controls. The inspector witnessed portions of the radioactive waste systems controls associated with radwaste shipments and barreling.
No-items of noncompliance were idertified.
10. Headquarters Request At the request of NRC Headquarters, the Senior Resident Inspector, with the assistance of several licensee personnel, summarized reactor shutdown time since October, 1979. The sumoary was a comparison of down time caused by NRC requirements versus time down for other reasons. The data was compiled and forwarde d to Region III on February 10, 1981. The resident inspector responded to NRC Headquarters requests via Region III with respect to ENS phone power supply, results of nondestructive testing of isolation condenser and shutdown cooling system piping safe-ends, and possiblef generic problems with ATVS-ARI valves in relation to other parts of.the system.
No items of' noncompliance were identified.
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Meetings. Training, and Of f-Site Functions During this report period, the resident inspector attended a one week training course on SWR Simulator Training in Chattanooga, Tennessee and a coe week training course on Fundamentals
'of Inspection at the NRC Regica III office in Glen Ellyn, Illinois.
-The senior. resident inspector spent three days at the Quad Cities Nuclear Generating Station in_Cordova, Illinois with the NRC _ senior resident inspector at that site.
The purpose of the trip was for comparison of Dresden with Quad-Cities with respect to NRC activities and licensee activities.
12.
Exit Interview
.The inspector met with licensee representatives (denoted in Para-
. graph 1) throughout the period and at the conclusion of the inspection on February 27, 1931 and summarized the scope and findings of the inspection activities. The licensee acknowledged the findings of the
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