IR 05000265/1978022
| ML20062E051 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/30/1978 |
| From: | Charles Brown, Jackiw I, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20062E040 | List: |
| References | |
| 05-265-78-22, 5-265-78-22, 50-254-78-21, NUDOCS 7812040046 | |
| Download: ML20062E051 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
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Report No. 50-254/78-21; 50-265/78-22
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Docket No. 50-254; 50-265 License No. DPR-29; DPR-30 Licensee: Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Quad Cities Nuclear Power Station, Units 1 and 2 Inspection At: Quad Cities Site, Cordova, IL Inspection Conducted: August 21-25, 31, September 1, 6, 7, 13, 14, and October 3 and 4, 1978 Inspectors:
I. N.jdackiw
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Re id4 Approved By:
R. C. Knop, Chief N[E[7[
Reactor Projects Section 1
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Inspection Summary Inspection on August 21-25, 31, Sept embe r 1, 6, 7, 13, 14, and October 3 and 4, 1978 (Report No. 50-254/78-21; 50-265/78-22)
Areas Inspected: Review of station records, audits and review function, plant operations; fire protection program evaluation; IEB and IEC followup; and licensee event report followup. The inspection involved 15S inspector-hours onsite by three NRC inspectors.
Results: Of the six areas inspected, no apparent items of noncompliance were identified in these areas; one deviation was identified in one area (Paragraph 9).
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1.
Persons Contacted
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Kalivianakis, Station Superintendent J. Gudac, Assistant Superintendent
- i L. Gerner, Technical Staf f Supervisor T. Tamlyn, Lead Operating Engineer
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R. Bax, Operating Engineer, Unit 2
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r G. Conschack, Operating Engineer, Unit 1
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Flessner, Assistant Technical Staf f Supervisor
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R. Spear, Maintenance Engineer J. Heilman, Quality Assurance Engineer, Operations D. Thayer, Quality Assurance Engineer, Maintenance
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Gamprel, Quality Assurance Engineer, Maintenance The inspector also interviewed several other licensee employees including shif t engineers and foremen, reactor operators, technical staff personnel, and quality assurance and control personnel.
- Denotes those present at the exit interview.
2.
Review and Audits The inspector reviewed the records relating to onsite review committee meetings and determined requirements had been met, proposed tests and experimm_?.s which affect nuclear safety or whose performance may constitute an unreviewed safety question as defined in 10 CFR 50.59 were reviewed as required, violation of facility technical specifications were reviewed as required and proposed changes to the technical specifications were reviewed in accordance with the f acility technical specifications. No items of noncompliance or deviations were identified.
A review of the records relating to all offsite audits conducted during this year verified that audits were conducted in accord-ance with written procedures and checklists, by trained personnel not having direct responsibility in the area being audited, audit results were documented and reviewed by site management and corporate management, followup action has been initiated and audit frequency was in conformance with the technical specifications. No concerns were identified.
3.
Records The stations' program for the control, storage, retention and retrieval of records and documents was reviewed to ascertain-2-
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that the program is in conformance with Technical Specifications and approved procedures. The inspector confirmed the rollowing:
Selected record samples conform to Technical Spe*cifications a.
requirements with respect to control, storage, retention and retrieval.
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b.
Record-keeping of reactor operations and equipment perfor-mance is sufficient to permit review to detect long-term
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equipment degradation or adverse trends that could result in potential safety hazards.
No items of noncompliance or deviations were identified.
4.
Plant Operation Plant operation activities were reviewed to verify that they atu being conducted in accordance with station procedures and Technical Specification requirements. Also, plant tours were conducted to observe that safety related work is being properly performed.
No items of noncompliance or deviations were identified.
5.
IEB and IEC Followup The inspector reviewed action taken by the licensee with regard to bulletins and circulars to verify that responses to IE Bulletins represent the action taken by the licensee and that IE Circulars sent to the licensee were received and reviewed. The following bulletins are considered closed:
Malfunctioning of Circuit Breaker Auxiliary Contact Mechanism-GE CR105X. The inspector confirmed that the licensee has identified the above contact mechanisms and is planning to replace them by the end of the next outage for each unit.
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Defective Cutler-Hammer Type M Relays with DC Coils. An investigation revealed that no Cutler-Hammer Type M relays are used in safety-related systems at the plant.
Bk'R Drywell Leakage Paths Associated with Inadequate Closures. The inspector verified the following with regard to this bulletin:
The procedure for installing the drywell head details the a.
installation instructions and ensures bolts are torqued in the same manner each time.
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Head-flange metal to metal contact is verified after bolt tightening per procedure.
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Drywell head gaskets are required to be inspected'by the procedure.
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The maximum allowable bolt torques comply to applicable codes.
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e.
No problems have been encountered with excessive drywell head flange leakage during two C1LRTs performed on Units 1 and 2.
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A list of bolted containment closures which open outward from the containment has been provided.
Bergen-Patterson Hydraulic Shock Suppressor Accumulator Spring Coils. The inspector confirmed that the licensee plans to examine the spring coils during routine inspections and replace them with teflon coated springs as necessary.
The following IE Circulars were reviewed and are considered closed:
IE Circular No. 78-02.
Proper Lubricating 011 for Terry Turbines.
IE Circular No. 78-04.
Installation Error that Could Prevent Closing of Fire Doors.
IE Circular No. 78-06.
Potential Common Mode Flooding of ECCS Equipment Room at BWR Facilities.
IE Circular No. 78-07.
Damaged Components on a Bergen-Patterson Series 25000 Hydraulic Test Stand.
IE Circular No. 78-09.
Arcing of GE Company Size 2 Contactors.
IE Circular No. 78-11.
Recirculation M-G Set Overspeed Stops.
No items of noncompliance or deviations were, identified.
6.
Site Review of Licensee Event Reports Licensee Event Reports were reviewed to verify that details were accurately reported; that the cause was. identified; that the event was reviewed and evaluated in accordance with Technical Specifi-cations; and that corrective action was taken as described in the report. The following LER's were reviewed:
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Unit 1 RO 78-06/03L dated March 6,1978, " Main Chimney Pump Egilure." On two occasions the selected plant chimney sample pump was discovered not running. A damaged power-supply cable leading to the main chimney sampler was the immediate cause of this event. The inspector
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confirmed that the damaged cable was repaired.
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.,c RO 78-24/03L dated September 5, 1978.
"RCIC Turbine Inoperable."
While performing the quarterly RCIC Flow Rate Test, the RCIC turbine tripped prematurely. The cause of this event is attributed to the failure of the mechanical overspeed trip mechanism. The inspector confirmed that the ball and tappet assembly and the nut and tensioning spring were replaced on the turbine mechanical overspeed mechanism.
Unit 2 RO 78-02/03L dated February 9, 1978. " Main Steam Isolation Valve Failed to Give 1/2 Scram." During functional testing, a limit switch for MSIV 203-2D f ailed to give a Reactor Protection System channel trip. The occurrence was caused by component failure due to the limit switch contacts being stuck in the closed position.
The inspector confirmed that the licensee has initiated an inves-tigation program and is planning to replace the existing limit switches with new high temperature switches.
No items of noncompliance or deviations were identified.
7.
Office Review of Licensee Event Reports The inspector reviewed licensee's event reports to ascertain i
whether corrective actions discussed in the reports appear appro-priate and whether information reported to the NRC satisfies
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reporting requirements. The following event reports rare reviewed-l and are considered closed:
Unit 1 RO 78-19/03L dated July 5, 1978, "Drywell to Torus Digital AP Not Installed by Required Date."
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RO 76-22/03L dated August 16,1978, " Reactor Building Suppression l
Chamber Vacuum Breaker Switch Drif t."
RO 78-23/03L dated August 31, 1978, " Suppression Chamber Purge
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Valve 1601-56 Failed to Open."
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3.
Other Inspection Findings During the course of this inspection the inspectors (Aentified the following items which require further review:
I Technical Specifications require that after about 5ecember
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1976, operability of the SBGT eystem inlet heater at rated
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power be demonstrated. The inspectors were unable to confirm that the rated power conditions are being met.
This item
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remains open and will be reviewed during a subsequent inspection.
b.
Technical Specifications require that a scram be initiated on main steamline isolation valve closure at < 10*.
In discussions
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with the licensee the inspectors requested a review of the valve closure settings. This item will be reviewed during a sub-sequent inspection.
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Fire Protection a.
Fire Protection Evaluation Team
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The Fire Protection Evaluation Team was accompanied by the inspector during their tour of the facility on August 21-25, 1978. The team provided the licensee with the list of items that resulted from the inspection of the facility and eval-uation of the facility's " Fire Protection Analysis" submittal.*
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Housekeeping During the tour and evaluation of the site several areas were noted where housekeeping was a problem and storage of flammable fluids was excessive. The licensee was informed that this was considered a deviation from the CE-1-A Topical Report in that the controlling procedures did not provide sufficient guidance
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to prevent storage of excessive amounts of flammable materials.
The inspector requested the licensee to develop procedures to control storage of flammable material which includes the evaluation and acceptance criterion of the area to be used for storage. Housekeeping procedures appear to need an updating review to conform with the Topical Report.
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Exit Interview The inspector cet with licensee representatives (denoted in Paragraph 1) on August 25, and October 4, 1978. The inspectors summarized the scope and findings of the inspection and discussed the deviation.
With regard to the SBGT inlet heater rated power item and the 15IV closure setting, the licensee stated that both of these items will be reviewed.
- Refer to the Headquarter report for details.
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