IR 05000254/1979025
| ML19262C352 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/27/1979 |
| From: | Chrissotimos N, Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19262C351 | List: |
| References | |
| 50-254-79-25, 50-265-79-22, NUDOCS 8002110333 | |
| Download: ML19262C352 (6) | |
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U.S. NUCLEAR REGULATORY CO.TilSSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-254/79-25; 50-265/79-22 Docket No. 50-254; 50-265 License No. DPR-29; DPR-30 Licensee:
Commonwealth Edison Company P. O. 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: November 5 - December 14, 1979
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Inspectors:
N. J. Chrissotimos
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Approved by.
R. L. Spessard, Chief
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Reactor Projects Section 1 Inspection Summary Inspection on November 5 - December 14, 1979, (Report No. 50-254/25; 50-265/22.
Areas Inspected: Routine, an announced resident inspection of maintenance, plant operations, access control, review and followup on licensee event reports, refueling activities, calibration, radiation protection, indepen-dent areas, and an unusual event.
The inspection involved 260 inspec-tor-hours onsite by one NRC inspector.
Results:
Of the nine areas inspected, no items of noncompliance were identified.
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DETAILS
1.
Persons Contacted
- N. Kalivianakis, Superintendent T. Tamlyn, Assistant Superintendent Operations K. Graesser, Assistant Superintendent Administrative D. Bax, Assistant Superintendent Maintenance
- L. Gerner, Technical Staff Supervisor G. Conschack, Senior Operating Engineer
- J. Heilman, Quality Assurance Operations The inspector also interviewed several other licensee employees, in-cluding shift engineers and foreman, reactor operators, technical staff personnel and quality control personnel.
- Denotes those present at the exit interview on December 14, 1979.
2.
Maintenance Station maintenance activities of safety related systems and components were reviewed to ascertain that they are conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Specification requirements.
The following items were considered during this re"iew:
the limiting conditions for operations were met while components or systems were removed from service; approvals were obtained prior to initiating the work; maintenance activities were accomplished using approved procedures; maintenance activities were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to an operating status; quality control records were maintained for maintenance activities; and maintenance activities were accomplished by qualified personnel.
The inspector observed maintenance in progress concerning the fol-lowing work requests: Q01737 refuel bridge, Q01509 service water piping hanger, Q01979 Unit I reactor feed pipe header.
The inspector reviewed the following completed work packages: Q0 1174 - Drywell and torus vent valve, QO 1509 - Service water piping hanger, QO 1604 - N Purge valve, QO 1737 - refuel bridge, QO 1869 -
SBGT flow indicator, Q0 1959 - RHR pipe flange, QO 1979 - Unit I reactor feed pipe header.
No items of noncompliance were identified.
3.
Plant Operations
'The inspector reviewed the plant operations including examinations of control room log books, routine patrol sheets, shift engineer log 1946 118
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book, equipment outage logs, special operating orders, and jumper and tagout logs for the month of November and December, 1979. The inspector observed plant operations during 4 offshifts during the months of November and December, 1979.
The inspector also made visual observations of the routine surveillance and functional tests in progress during the period. This review was conducted to verify that facility operations were in conformance with the requirements established under Technical Specifications, 10 CFR, and Administrative Procedures. A review of the licensee's deviation reports for the period was conducted to verify that no violations of the licensee's Technical Specifications were made.
The inspector conducted tours at an increased frequency due the refueling outage in progress on unit 2 of Units 1 and 2 reactor buildings and turbine buildings throughout the period and noted that the monitoring instrumentation was recorded as required, radiation controls were properly established, fluid leaks and pipe vibrations were minimal, seismic restraint oil levels appeared adequate, equipment caution and~ hold cards agreed with control room records, plant housekeeping conditions / cleanliness were adequate, and fire hazards were minimal. The inspector observed shift turnovers to verify that plant and component status and problem areas were being turned over to relieving shift personnel. The inspector observed sampling and chemical analysis of water chemistry samples to verify that water chemistry was being maintained in accordance with Technical Specifications.
No items of noncompliance were identified.
4.
Physical Protection - Access Control (Identification, Authorization.
Badging, Search, and Escorting)
The inspector verified that all persons and packages were identified and authorization checked prior to entry into the protected area (PA),
all vehicles were properly authorized prior to entry into a PA, all persons authorized in the PA were issued and displayed identification badges, records of access authorized conformed to the PSP, and all personnel in vital areas were authorizel access; verified that all persons, packages, and vehicles were searched in accordance to regu-latory requirements, the PSP, and security procedures; verified that persons authorized escorted access were accompanied by an escort when within a PA or vital area; verified that vehicles authorized escorted access were accompanied by an escort when within the PA; and verified by review of the licensee's authorization document that the escort observed above was authorized to perform the escott function.
No items of noncompliance were identified.
5.
Review and Followup on Licensee Event Reports Through direct observations, discussions with licensee persc.' 1, and
. review of records, the following event reports were reviewed to deter-mine that reportability requirements were fulfilled, immediate correc-tive action was accomplished, and corrective action to prevent recur-rence had been accomplished in accordance with Technical Specifications.
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Unit 1 R0 - 79-30/03L, dated October 12, 1979, MAPLGHR found to be noncon-servative.
RO - 79-31/03L, dated October 20, 1979, SBGT declared inoperable as a result of IEB-79-02 inspection.
RO - 79-32/03L, dated October 26, 1979, SBGT declared inoperable as a result of IEB-79-02 inspection.
RO - 79-33/03L, dated October 25, 1979, diesel generator failed to accept full load.
RO - 79-34/03L, dated October 30, 1979, suppression pool level below technical specification limit.
RO - 79-35/03L, dated November 9, 1979, pipe restraint declared in-operable as a result of IEB-79-14 inspection.
Unit 2 RO - 79-23/03L, dated October 16, 1979, level switch failed to trip during surveillance test.
RO - 79-24/03L, dated October 25, 1979, vacuum breaker failed to open during surveillance test.
R0 - 79-25/03L, dated October 26, 1979, RHR valve breaker thermal overload trip.
RO - 79-26/03L, dated October
.2, 1979, turbine pressure switch trip in excess of technical specifications during testing.
No items of noncompliance were identified.
6.
Refueling Activities The inspector verified that prior to the handling of fuel in the core, all surveillance testing required by the Technical Specifi-cations and licensee's procedures had been completed; verified that during the outage the periodic testing of refueling related equipment was performed as required by Technical Specifications; observed 3 shifts of the fuel handling operations (removal) non STD and verified the activities were performed in accordance with the Technical Speci-fications and approved procedures; verified that containment integrity was maintained as required by Technical Specifications; verified that good housekeeping was maintained on the refueling area; and, verified that staffing during refueling was in accordance with Technical Speci-fications and approved procedures.
No items of noncompliance were identified.
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Calibration of Safety-Related Components Not Required by Technical Specifications The inspector verified the calibration of all APRM's associated with the environmental stations and that the calibrations were performed in accordance with technically adequate procedures.
No items of noncompliance were identified.
8.
Radiation Protection - Operations On November 28, 1979, the inspector examined radiation protection instruments in use and verified operability and currency of calibra-tion, examined 4 SWP's and verified operations conducted under the SWP's were in accordance with licensee procedures and verified that high radiation area posting and control and 10 CFR 19 posting re-quirements were met.
The inspector also witnessed six radioactive waste shipments and veri-fied that inspections were being conducted in accordance with licen-see procedures.
No items of noncompliance were identified.
9.
Independent Areas of Inspection a.
The inspector witnessed and was involved in a general site emer-gency drill conducted December 4, 1979. The drill emphasized proper communications. The resident inspector verified that the direct communications line to NRC Headquarters was operational.
b.
The licensee reported (LER) an inaccurate instrument calibration of ECCS level setpoints due to improper temperature compensation.
Completion of recalibration was accomplished within hours of discovery.
No items of noncompliance were identified.
10.
Unusual Event On December 3, 1979, the licensee reported to the resident inspector that during a valve verification check it was discovered that two valves (core spray pump section valves) were found mispositioned for no apparent reason.
A Region III investigator and the resident in-spector are continuing an investigation into this matter, and a separate report will be submitted on this matter. Additionally, the licensee requested and received assistance from the Federal Bureau of Investigation.
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11.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) throughout the month and at the conclusion of the inspection on December 14, 1979 and summarized the scope and findings of the inspec-tion activities.
The licensee acknowledged the inspectors comments.
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