IR 05000254/1980010
| ML19310A751 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/15/1980 |
| From: | Chrissotimos N, Spessard R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19310A748 | List: |
| References | |
| 50-254-80-10, 50-265-80-13, NUDOCS 8006230078 | |
| Download: ML19310A751 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-254/80-10; 50-265/80-13
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Docket No. 50-254; 50-265 License No. DPR-39, DPR-48 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 Facility Name: Quad-Cities Nuclear Power Station, Units 1 & 2 Inspection At: Quad-Cities Site, Cordova, Illinois Inspection Conducted: March 27 thru May 7, 1980 N. f i X P J 2r
, 5~!7e Inspector:
J. Ch ssotimos -
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Approved By:
R. L. Spe sard, Chief
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Reactor Projects Section 1 Inspection Summary Inspection on March 27 thru May 7, 1980 (Report No. 50-254/80-10;
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50-265/80-13)_
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Areas Inspected: Routine, unannounced inspection consisting of operational safety verification, long term shutdown activities, maintenance observation (annual and refuel), surveillance observation, t
licensee event report followup, IE Bulletin followup, IE Circular followup, startup testing-refueling, plant trips, and independent inspection. The inspection involved 195 inspector-hours onsite by one NRC inspector.
Results: No items of noncompliance were identified.
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DETAILS-1.
Persons Contacted j
- N. Kalivianakis, Superintendent T. Tamlyn, Assistant Superintendent Operations
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K. Graesser, Assistant Superintendent Administrative
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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, including shift engineers and foreman, reactor operators, technical staff personnel and quality control personnel.
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- Denotes those present at the exit interview on May 7, 1980.
2.
Licensee Action on Previous Inspection Findings (Closed) Outstanding inspection item (50-254/78-07; 50-265/78-07):
Replacement of G.E. 105X relays. This task has been completed for Unit 2.
Replacement of these relays on Unit I remains to be complet-ed.
This matter remains open and is redesignated (OII 254/80-10-01).
(Closed) Outstanding inspection item (50-265/78-01): Replacement of G.E. 120A Contact Arm Retainers. This task has been completed on the safety.related relays for both units.
'3.
Operational Safety Verification-Unit I and Long Term Shutdown-Unit 2 The inspector observed control room operations, reviewed applicable l
logs and conducted discussions with control room operators during I
the month of April, 1980. The inspector verified the operability of selected emergency systems, reviewed tagout records and verified j
proper return to service of affected components. Tours of Units 1 and 2 reactor buildings and turbine buildings were conducted to
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observe plant equipment conditions, including potential fire hazards, J
fluid leaks, and excessive vibrations and to verify that maintenance i
requests had been initiated for equipment in need of maintenance.
The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan.
.The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the month of April, 1980, the inspector walked down the accessible portions of the Unit 2 RCIC and HPCI 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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.Tb2se reviews and observations were conducted to verify that facil-ity operations were in conformance with the requirements established under technical specifications, 10 CFR, and administrative proce-dures.
No items of noncompliance were identified in this area.
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4.
Maintenance Observation (Annual and Refuel)
Station maintenance activities of safety related systems and com-ponents 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 specifications.
The following items'were considered during this review:
the limit-ing conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initiat-ing the work; activities were accomplished using approved procedures and were inspected.as applicable; functional testing and/or calibra-tions were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were
. properly certified; radiological controls were implemented; and, fire prevention controls were implemented.
Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment maintenance which may affect system performance.
The following maintenance activities were observed / reviewed:
HPCI Valve Repacking Replacement of Control Rod Drives RCIC Valve Replacement Electromatic Relief Valve Repair SBLC Relief Valve Resetting Repair of Condensate Pump Room Vault Penetration Maintenance of Core Spray Manual Isolation Valves
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M.G.-Set Protective Relays Replacement of ASCO Solenoids on the 220-44 and 220-47 Valves Installation of Model 740 Switches on MSIV's Rebuild of Recirculation ~ Pump Seals Maintenance of Control Rod Drives
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Installation and Tensioning of Reactor Vessel Head
Following completion of maintenance on the Unit 2 RCIC, HPCI, and-ADS systems, the inspector verified that these systems had been returned to service properly.
No items of noncompliance were identified in this area.
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. Monthly Surveillance Observation The inspector observed technical specifications required surveil-
.lanceLtesting on the fire protection system and verified that test-ing was performed in accordance with adequate procedures, that test
~ instrumentation was calibrated, that limiting conditions.for opera-tion were met,:that removal.and restoration of the affected com-
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ponents were accomplished, that test results conformed with. tech-r nical specifications and procedure requirements and were reviewed by personnel other than the-individual directing the test, and that any deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
The~ inspector also witnessed portions of the following test activ-ities:. Unit 2 MSIV's and Unit 1 Low Level RPS,.APRM Settings, and Main Steam Line Monitor RPS.
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.No~ items of noncompliance were identified in this area.
'6.
. Licensee Event Reports Followup Through direct' observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine.that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to prevent recurrence had been accomplished in accordance with technical specifications.
Unit 1-
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R0-80-05/03L, dated February 24, 1980, MSIV A0-203-2B Failed to close during surveillance test.
R0-80-07/03L, dated March 8, 1980, Main steam line radiation monitor found to be reading' low.
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R0-80-08/03L, dated March 8, 1980, 1/2 diesel generator would not l
start from control room.
Unit 2 R0-79-09/03L-1, dated April 129,_1979, MSIV limit switch trip posi-
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tion-greater than 10% of closure.
R0-80-03/03L,. dated.Februa ry 13, 1980, Reactor building ventilation
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system.would not reset following test isolation.
R0-80-05/03L, dated March 3, 1980, Relay K21A failed to energize during RHR logic test.
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Unit 2 Con't.
R0-80-06/01T,' dated March 8,1980, Performance of the vessel pres-sure. test prior to startup revealed indications in the core spray p
piping.
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Details of IE's inspection findings are contained in Inspect _ ion Report 50-265/80-11.
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RO-80-07/03L, dated' March 16, 1980, Jet pump beam assembly indica-tion.
The affected assembly was. fixed, and the licensee will ultrasonical-ly examine the beam assemblies on Unit I during the next refueling outage (OII-254/80-10-02).
R0-80-08/03L, dated March 5, 1980, Performance of RHR logic test revealed failure of timer contacts.
- RO-80-09/03L, dated March 22, 1980, TIP machine failed to withdraw
TIP automatically.
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No items of noncompliance were identified in this area.
7.
IE Bulletin Followup-For the IE Bulletins listed below the inspector verified that the written response was within the time period stated in the bulletin, that the written response included the information required to be
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reported,'that the written response included adequate corrective
action commitments based on information presentation in the bulletin and the licensee's response, that licensee management forwarded copies of the written response to the appropriate onsite management
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representatives, that information discussed in the licensee's writ-ten response was accurate, and that corrective action taken by the licensee was as described in the written response.
IEB-79-08: Events Rclated to BWR's Identified During TMI Incident.
The NRC staff evaluation concluded.that the appropriate actions to meet the requirements were taken.
(Reference:
Letter Ippolito to Peoples, dated March 10, 1980).
IEB-80-03: - Loss of Charcoal From Standard Type II, 2 Inch, Tray Adsorber Cells.
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. Visual examination of a cell disclosed adequate contact between casing.and screen. No further concerns were identified.
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LIEB-80-02:
Inadequate Quality Assurance for Nuclear Supplied Equip-
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'The-inspector reviewed **.e final documentation package (Reference:
Inspection Report' 50-254/80-11 for details). No further concerns were identified.
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IEB-78-12: Atypical Weld Material in Reactor Pressure Vessel Welds.
NRR has completed the era 7uation of the licensee's response and has determined'it's acceptability. No further concerns were identified.
No items of noncompliance were identified in this area.
8.
-IE Circular Followup For the IE Circulars listed below, the. inspector verified that the Circular was received by the licensee management, that a review for applicability was performed,.and that if the circular were applic-able to the facility, appropefste corrective actions were taken or were scheduled to be taken.
IEC-80-01, dated ~ January 17, 1980, Service Advise for General Electric Induction Disc Relays.
The licensee does not have any of the subject relays.
Operator relays areichecked during outages and cleaned, if necessary.
IEC-80-02, dated January 28, 1980, Nuclear Power Plant Staff Work
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- The inspector' verified that the circular is being reviewed by Common-
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wealth Edison's Corporate Office.
IEC-80-03, dated March l6, 1980, Protection From Toxic Gas Hazards.
The licensee has installed emergency breathing air in the control room. The inspector has no other concerns in this arc.
IEC-80-04, dated March 14, 1980, Securing of Threaded Locking Devices on Safety-Related Equipment.
The licensee has reviewed and evaluated this circular.
No items of noncomp1'iance were identified in this area.
9.
Plant Trips Following-the plant-trip on May 1, 1980 of Unit 2, the inspector ascertained-the status of the reactor and safety systems by obser-vation of control room indicators and discussions with licensee-6-
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personnel concerning plant parameters, emergency system status and reactor coolant chemistry. The inspector verified the establishment of proper communications and reviewed the corrective actions taken by the licensee.
All systems responded as expected, and the plant was returne_d to
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operation on May 1, 1980.
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The inspector was present in the control room at the ?.ime of the trip and observed proper.and timely actions of the operators involv-ed with the trip. Emergency system actuation was not required.
No items of noncompliance were identified in this area.
10.
Startup Testing - Refueling On May 6, 1980 core thermal power calculations, LPRM/APRM calibra-tion calculations, and LHGR,-MCPR, and APLHGR calculations were examined for Unit 2 (computer calculations OD-1, P-1, OD-3, and OD-6).
As a result of the above examination, observation of select-ed tests, and verification of calibrations and adjustments, the inspector determined that the following items were accomplished in accordance with the technical specifications using approved proce-dures which were techcially adequate:
LPRM gain adjustments and settings.
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APRM gain adjustments and settings.
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LHGR within limits.
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MCPR within limits.
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APLHGR within limits.
Tests observed were: Turbine overspeed (both electrical and mechanical), auto blowdown, CRD friction testing, scram timing and ECCS logic testing.
No items of noncompliance were identified in this area.
11.
Independent Inspection The inspector witnessed the preoperational testing of the Dow Chemical Radioactive Waste Solidification System. The inspector verified _that properly approved procedures were utilized, qualified individuale conducted the test and results were documented. The inspector also verified that the licensee had conducted and document-ed a 10 CFR 50.59 review.
No items of noncompliance were identified in this area.
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12. ~ Exit' Interview
' The inspector met with licensee' representatives (denoted in Para-
- graph 1) throughout the month and at'the conclusion of the inspec-tion on May 7, 1980 and summarized the scope and findings of the
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' inspection activities. The licensee acknowledged the inspector's
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comments.
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