IR 05000254/1979009
| ML19225C492 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 06/12/1979 |
| From: | Chrissotimos N, Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19225C483 | List: |
| References | |
| 50-254-79-09, 50-254-79-9, 50-265-79-07, 50-265-79-7, NUDOCS 7907310096 | |
| Download: ML19225C492 (5) | |
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U.S.: NUCLEAR REGULATORY COMMISSION OFFICE OF INSEICTION AND ENFORCEMENT
REGION III
Report No. 50-254/79-09; 50-265/79-07 Docket No. 50-254; 50-265 License No. DPR-29; DPR-3C
Licensee:
Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: Quad-Cities Nuclear Power Station, Units 1 and 2
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Inspection At: Quad-Cities Site, Cordova, Illinois Inspection Conducted. March 15, 16, 21 and 22, 1979, April 3-5 19, 23, 24 and 27, 1979, and May 8,
-~ e Inspector:
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R. [. Spes]sard, Chief h /lM7 )
Approved By:
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Reactor Projects Section 1 jnspection Summary inspection on March 15-16, 21 and 22, April 3-5, 18-19, 23-24 and 27 1979 and May 8, 1979 (Rep rt ho. 50-254/79-09; 50-265/79-07)
Areas Inspected:
Routine, unannounced inspection of plant operations, maintenance and licensee event report followup. The inspection involved a total of 72 inspector-hour. __ ite by one NRC inspector.
{esults: Of the three areas inspected, no apparent items of noncom-p.iance or deviations were identified in two areas; one apparent ite.m of noncompliance (infraction - automatic function of vacuum breakers not available, Paragraph 4) was identified in one area.
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DETAILS
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1.
Persons Contactea
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Kalivianakis, Superintendent J. Gudac, Assistant Superintendent T. Tamlyn, Lead Operating Engineer
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K. Graesser, Administrative Assistant"
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Gerner, Technical Staff Supervisor D. Bax, Operating Engineer, Unit 2 G. Conschack, Operating Engineer, Unit 1 R. Spear, Maintenance Engineer
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Heilman, Quality Assurance, Operations The inspector also interviewed several other licensee employees, including shift engineers and foreman, reactor operators, technical sta.f personnel and quality control personnel.
- Denotes those present at the exit interview on May 8, 1979.
2.
Maintenance Station maintenance activities of safety related systems and compen.
were reviewed to ascertain that they are conducted in accoraance with approved procedures, regulatory guides and industry codes or standards and in conformance with technical specification requirements.
The following items were considered during ths review: The limiting conditions for operations were met while components or systems were removed from service; Approvals were obtained prior to ini;iating the work; Maintenance activities were accomplished using approved procedures; Maintenance activities were inspectec as applicable; Functional testing and/or cali-brations were performed prior to returning componect.s or systems to an operating status; Quality control records were mait.tained for maintenance activities; and, Maintenance activities were accomplished by qualified personnel.
The review included 25 work requests from various plant systems associated with both units.
The following modifications were also reviewed:
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4-2-76-57 HPCI Start Circuitry (2)
4-1-77-3 Torus Drain Header Penetrations (3)
4-2-74-8 High Point Vent on RHRS to Fuel Pool Piping No items of noncompliai _ were identified.
3.
Plant Operations
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The inspector reviewed facility operations to ascertain whether they are in conformance with requirements established in technical specifications and licensee procedures.
The review included verification that control room logs are filled out and reviewed, that operating ordets and jumper logs do act conflict with technical specification requirements, and that deviations are identified and reported to the NRC.
During a tour of the control room, on a backshift, the inspector observed that an operator who was working a second consecutive shift did not appear to be as alert as could be expected. The inspector expressed his concern to the licensee in regard to operators working consecutive shifts. The licensee stated that this is not a common practice and occurs infrequently. The inspector has no further questions on this matter at this time.
Ne items of noncompliance were identif.ied.
4.
Office / Site Pcview 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 tech-nical specificctions; and that the corrective action was taken as described in the report. The following LERs were reviewed:
Unit 1 R0-79-02/03L, dated Fe bruary 5,1979, " Freon Penetration Through the Charcoal Absorbers in Excess of Technical Specification Limits" R0-79-05/03L, dated February 22,1979, " Pilot Solenoid Valve ' o Air Starting Motors Failed to Operate" The inspector verified that the correct testing for diesel generators had been accomplished.
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R0-79-06/03L, dated February '.1,1979, " Valve A0 1-161-21 Failed to Close Within Specified Time" R0-79-07/03L, dated February 20, 1979, " Main Steam Line Leak Detection Temperature Switches Drifting" R0-79-08/03L, dated February 24, 1979, "RCIC Turbine Area High Temperature Switch Drift"
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R0-79-10/03L, dated February 10, 1979, " Diesel Fire Pump out of Service Longer Than 7 Day Limit" The inspector discussed this occurrence with operational personnel.
The inspector determined that operational personnel were aware of system status, but did not document properly.
R0-79-1:/03L, dated March 1, 1979, "Drywell Vent Valve Clc.
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in Excess of Limits" R0-79-13/03L, dated March 14, 1979, " Check Valves Failed to Check Flow Through Instrument Lines" R0-79-14/03L, dated March 9, 1979, " Automatic Blowdown Timer Timed Out in Excess of Limits" The inspector verified replacement and satisfactory completion of test.
R0-79-16/01T, dated April 2,1979, "Significant Tube Cracking and Loss of B C"
The inspector verified that these conditions do not exist at the facility. Action on this information provided by General Electric is not expected to be required until August 1980.
R0-79-18/01T-0, dated April 27, 1979, " Pressure Switches for Reactor '2ilding to Suppression Chamber Vacuum Breakers Inadever sntly Valved Out" While installing reactor building suppression chamber alarm pressure switches (under a non-safety related work request)
personnel valved out pressure switches 1622A and.B.
This defeated the automatic functional requirements of the vacuum breakers as required by Technical Specifications. The instru-ments were valved out for one hour on April 26, 1979 and for three hours on April 27, 1979. This is contrary to Technical
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Specification 3.7eA.3.a and is an item of noncompliance.
Investigation of this occurrance revealed that personnel on the job were unaware of the fact that any technical specifications related work was involved.
The work of adding an alarm pressu e switch was coded non-safety relat_2 Prior to the conclusion of the inspection the inspector verified that corrective and preventive actions, as described in LER
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79-18/01T were taken; therefore, e response to this ntncompliance is not required.
Unit 2 R0-79-03/03L, dated February 28, 1978, "HPCI Turbine Area High Temperature Switch Drift" RO-79-04/03L, dated March 6, 1979, " Shutdown Cooling Suction Isolation Valve Failed to Close" R0-79-05/03L, dated March 12, 1979, " Recirculation MG Field Breaker Opened" R0-79-06/03L, dated April 11, 1979, "Tip Machine Ball Valve Would Not Close" Except as previously described, no items of noncompliance were identified.
5.
Hydrogen Tank Fire On Tuesday, May 8, 1979, there was a hydrogen tank fire. The tanks, which are non-safety related, are located approximately 200 feet west of the turbine building. An onsite emergency was declared and the Cordova Fire Department was called in for assistance. No radiological or safety related components were involved. The event lasted approximately one hour.
6.
Exit Inte rview The inspector met with licensee representatives (denoted in Paragraph 1) on May 8,1979. The inspector summarized the scope and findings of the inspection ar.d discussed the item of noncompliance. The licensee announcea that Mr. G. Spedl will be replacing Mr. B. Palagi as Leed Faclear Engineer.
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