IR 05000254/2002002
| ML020510278 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/20/2002 |
| From: | Ring M Division of Nuclear Materials Safety III |
| To: | Kingsley O Exelon Generation Co |
| References | |
| IR-02-002 | |
| Download: ML020510278 (16) | |
Text
February 20, 2002
SUBJECT:
QUAD CITIES NUCLEAR POWER STATION NRC INTEGRATED INSPECTION REPORT 50-254/02-02; 50-265/02-02
Dear Mr. Kingsley:
On February 10, 2002, the NRC completed an inspection at your Quad Cities Units 1 and 2 reactor facilities. The enclosed report documents the inspection findings which were discussed on February 11, 2002, with Mr. Tulon and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
No findings of significance were identified.
Immediately following the terrorist attacks on the World Trade Center and the Pentagon, the NRC issued an advisory recommending that nuclear power plant licensees go to the highest level of security, and all promptly did so. With continued uncertainty about the possibility of additional terrorist activities, the Nation's nuclear power plants remain at the highest level of security and the NRC continues to monitor the situation. This advisory was followed by additional advisories and although the specific actions are not releasable to the public, they generally include increased patrols, augmented security forces and capabilities, additional security posts, heightened coordination with law enforcement and military authorities, and more limited access of personnel and vehicles to the sites. The NRC has conducted various audits of your response to these advisories and your ability to respond to terrorist attacks with the capabilities of the current design basis threat (DBT). From these audits, the NRC has concluded that your security program is adequate at this time. In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Mark A. Ring, Chief Branch 1 Division of Reactor Projects Docket Nos. 50-254; 50-265 License Nos. DPR-29; DPR-30
Enclosure:
Inspection Report 50-254/02-02, 50-265/02-02
REGION III==
Docket Nos:
50-254; 50-265 License Nos:
50-254/02-02; 50-265/02-02 Licensee:
Exelon Nuclear Facility:
Quad Cities Nuclear Power Station, Units 1 and 2 Location:
22710 206th Avenue North Cordova, IL 61242 Dates:
December 30, 2001 - February 10, 2002 Inspectors:
K. Stoedter, Senior Resident Inspector J. Adams, Resident Inspector T. Ploski, Emergency Preparedness Inspector Approved by:
Mark Ring, Chief Branch 1 Division of Reactor Projects
SUMMARY OF FINDINGS IR 05000254-02-02, IR 05000265-02-02 on 12/30/2001 - 02/10/2002, Exelon Nuclear, Quad Cities Nuclear Power Station, Units 1 & 2.
The inspection was conducted by resident and regional inspectors. Based on the results of this inspection, there were no findings. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter 0609, Significance Determination Process (SDP). Findings for which the SDP does not apply are indicated by No Color or by the severity level of the applicable violation. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described at its Reactor Oversight Process website at http://www.nrc.gov/NRR/OVERSIGHT/index.html.
A.
Inspector Identified Findings No findings of significance were identified.
B.
Licensee Identified Findings No findings of significance were identified.
Report Details 1.
REACTOR SAFETY Plant Status Unit 1 began the inspection period at full power. On January 6, 2002, operations personnel reduced reactor power to approximately 95 percent for control rod exercising.
Following the rod exercising, Unit 1 operated at full power until January 9 when jet pump #20 unexpectedly failed. Operations personnel entered the appropriate Technical Specifications which required that the unit be shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During the 26 day forced outage, the licensee repaired multiple condenser tube leaks, replaced 16 jet pump beams, removed a previously leaking fuel bundle, replaced the damaged impeller on the 1B reactor recirculation pump, and completed an extensive fuel shuffle.
The licensee returned Unit 1 to full power on February 7, 2002. On the afternoon of February 7, the 1B reactor recirculation pump tripped which resulted in a power reduction to approximately 35 percent. The licensee determined the cause of the pump trip on February 8, and returned the unit to full power for the remainder of the inspection period.
Unit 2 also began the inspection period at full power. On January 2, 2002, operations personnel reduced reactor power to 98.5 percent due to oscillations on the #2 turbine control valve. Reactor power was restored to 100 percent later the same day. On January 6, reactor power was reduced to approximately 65 percent for turbine valve testing and a control rod pattern adjustment. Following the testing and control rod pattern adjustment, the reactor operated at full power until January 23 when the unit entered a coastdown condition in preparation for the upcoming refueling outage. On January 24 operations personnel reduced reactor power to approximately 70 percent at the request of the MidAmerican Energy Company load dispatcher. Operations personnel returned the reactor to the maximum achievable power later the same day. Due to entering coastdown, Unit 2 reactor power decreased gradually over the remainder of the inspection period.
1R04 Equipment Alignments (71111.04)
a.
Inspection Scope The inspectors verified the system alignment of the following mitigating systems during the period:
Unit 1A core spray system,
Unit 1/2 emergency diesel generator,
Unit 2 reactor core isolation cooling system, and
Safe shutdown makeup pump.
The inspectors conducted walkdowns while redundant equipment was out-of-service for maintenance activities. The inspectors verified that the as-found system configuration and operating parameters supported the continued ability of the system to perform its
intended functions. The inspectors accomplished the verifications by comparing the as-found configuration of the accessible portions of the listed systems to the configuration specified in the respective Quad Cities operating procedures. The inspectors reviewed design and licensing information and discussed system configuration and performance with licensee personnel.
b.
Findings
No findings of significance were identified.
1R05 Fire Protection (71111.05)
a.
Inspection Scope The inspectors conducted fire protection walkdowns of the Unit 1 and Unit 2 station blackout diesel generator rooms (Fire Zones SBO-3 and SBO-4) and the Unit 1 and 2 emergency diesel generator rooms (Fire Zones 9.1 and 9.2). These zones contained equipment related to the mitigating systems cornerstone. These inspections verified the proper control of transient combustibles and ignition sources, the material condition of fire detection and suppression systems, the operational lineup of fire detection and suppression systems, the maintenance of fire protection equipment, and the material condition and operational status of fire barriers. The inspectors also discussed issues associated with each fire zone with the fire marshall.
b.
Findings No findings of significance were identified.
1R07 Heat Sink Performance (71111.07)
a.
Inspection Scope The inspectors reviewed the design, performance, and maintenance of the 2B residual heat removal heat exchanger as part of the heat exchanger performance test conducted on January 30, 2002. The inspectors reviewed industry documents and discussed the testing procedure with engineering personnel to ensure that test acceptance criteria appropriately considered differences between testing conditions and design considerations, test results were appropriately categorized against pre-established acceptance criteria, and that the frequency of the performance test was acceptable. The inspectors also reviewed the test results and verified that test instrument inaccuracies and differences were also included in the test results.
b.
Findings No findings of significance were identified.
1R11 Licensed Operator Requalification (71111.11)
a.
Inspection Scope On January 9, 2002, the inspectors observed and assessed Crew F licensed operator performance during simulator training sessions. The training sessions required the operators to use the new digital feedwater control system, which will be installed during the upcoming refueling outages, and recall power uprate modification information. The first scenario involved a reactor recirculation flow controller failure, a condensate pump trip, a spurious Group 1 isolation, a failure of the reserve auxiliary transformer, and a loss of coolant accident. The second scenario included a loss of feedwater heating, the failure of the B feedwater regulating valve controller upscale, a turbine trip without bypass valves, and an anticipated transient without scram.
During the observations, the inspectors focused on the operators response to alarms, the command and control of crew activities, communications practices, and implementation of emergency plan requirements. The inspectors observed the training evaluators assessment of crew performance ensuring deficiencies were identified and corrected.
b.
Findings
No findings of significance were identified.
1R12 Maintenance Rule Implementation (71111.12)
a.
Inspection Scope The inspectors reviewed the following risk significant system associated with the Mitigating Systems Cornerstone:
Unit System Maintenance Rule Function
High Pressure Coolant Injection Z2300 The inspectors reviewed one problem documented in the following condition report for appropriate disposition with respect to the Maintenance Rule:
Q2001-02784, 2-2301-4 Failed to Stroke Closed During QCOS 2300-06.
The inspectors reviewed the licensees implementation of the maintenance rule, including the disposition of other condition reports, a review of scoping, performance criteria, performance monitoring, expert panel meeting minutes, short-term and long-term corrective actions, and current equipment performance status. The inspectors discussed system problems and maintenance rule classifications with engineering personnel.
b.
Findings No findings of significance were identified.
1R14 Non-routine Evolutions (71111.14)
a.
Inspection Scope The inspectors observed operator performance following the failure of Unit 1 jet pump #20 on January 9, 2002, and a trip of the 1B reactor recirculation pump on February 7, 2002. The inspectors reviewed operations procedures, control room strip charts, equipment drawings, and industry information; and interviewed licensee personnel to independently verify the cause of each transient and evaluate licensed operator response.
b.
Findings No findings of significance were identified.
1R15 Operability Evaluations (71111.15)
a.
Inspection Scope The inspectors reviewed the operability evaluations associated with the failure of the drywell ventilation booster fan, a torus high level switch, a leak on the 1A residual heat removal system heat exchanger, and the potential for degraded jet pumps on Quad Cities Unit 2. A list of documents reviewed by the inspectors can be found in the List of Documents Reviewed section of this report.
The inspectors verified that operability evaluations were performed when required and that completed evaluations were technically adequate, justified continued operation, considered other degraded conditions where applicable, and referenced applicable sections of the Updated Final Safety Analysis Report and other design basis documents.
b.
Findings
No findings of significance were identified.
1R19 Post Maintenance Testing (71111.19)
a.
Inspection Scope The inspectors reviewed the post-maintenance test data for the following activities associated with Initiating Event and Mitigating Systems Cornerstone equipment:
Work Order 00323496, Unit 2 Diesel Generator Cooling Water Pump Maintenance;
Work Order 00397798, Replace 1B Reactor Recirculation Pump Impeller; and
Work Order 00397374, Troubleshoot and Repair Unit 1 Fuel Mast.
The inspectors verified that the post-maintenance tests demonstrated that the systems and components were capable of performing their intended function. Included in the review were the applicable sections of Technical Specifications, the Updated Final Safety Analysis Report, and vendor manuals. Following the completion of the tests, the inspectors verified that any test equipment used was removed and that equipment was returned to the proper configuration.
b.
Findings No findings of significance were identified.
1R20 Refueling and Outage (71111.20)
a.
Inspection Scope The inspectors observed shutdown activities following the failure of Unit 1 jet pump #20 on January 9, 2002. The inspectors monitored the licensees cooldown process and ensured that Technical Specifications were followed during the transition into Modes 3, 4, and 5. The inspectors were present during the licensees initial inspection of the failed jet pump to independently verify the jet pumps condition and the location of loose parts in the reactor vessel. As part of the 26 day forced outage, the inspectors monitored outage configuration management on a daily basis by verifying that the licensee maintained appropriate defense in depth to address all shutdown safety functions and satisfy Technical Specification requirements. Due to the large amount of work performed on the jet pumps and the 1B reactor recirculation pump, the inspectors closely monitored the reactivity and inventory control systems in addition to radiation protection practices.
Proper operation of the decay heat removal system was verified during multiple control room tours and observations. Between February 1 and 6, 2002, the inspectors conducted multiple startup observations including a drywell closeout, startup testing, preparations for generator sychronization, troubleshooting of a combined intermediate valve, and control rod scram time testing.
b.
Findings No findings of significance were identified.
1R22 Surveillance Testing (71111.22)
a.
Inspection Scope The inspectors observed surveillance testing activities and/or reviewed completed packages for the tests listed below related to systems in the Mitigating Systems Cornerstone:
QCOS 0202-07, Jet Pump Flow Distribution Comparison, Revision 14, on multiple dates;
QCOS 2300-11, Contaminated Condensate Storage Tank/Torus Level Switch Functional Test, Revision 18, on January 4, 2002;
- QCOS 2300-04, High Pressure Coolant Injection System Cold Shutdown Valve Test, Revision 14, on January 19, 2002; and
QCOS 2900-04, Safe Shutdown Make Pump Reactor Vessel Injection Test at Cold Shutdown, Revision 13, on January 28, 2002.
The inspectors verified that Technical Specifications, Updated Final Safety Analysis Report, and licensees procedure requirements were met during each testing evolution.
Vibration and valve timing results were compared against In-Service Testing requirements for those components subject to the program. The inspectors also verified that the testing demonstrated that the structure, system, or component was capable of performing its intended function.
b.
Findings No findings of significance were identified.
1EP4 Emergency Action Level and Emergency Plan Changes (71114.04)
a.
Inspection Scope The inspector reviewed Revision 12 and Revision 13 of the Quad Cities Stations Annex to the Exelon Emergency Plan to determine whether changes identified in these revisions reduced the effectiveness of the licensees emergency planning, pending onsite inspection of the implementation of these changes.
b.
Findings No findings of significance were identified.
4.
OTHER ACTIVITIES (OA)
4OA3 Event Follow-up (71153)
a.
Inspection Scope The inspectors observed the licensees response to the January 9, 2002, jet pump failure. The inspectors monitored plant parameters and operator performance during the transient and verified the status of mitigating systems. This information was provided to regional management to help in determining the need for an additional inspection. A regional specialist conducted a special inspection of the engineering issues associated with the jet pump failure from January 15 - 17, 2002. The results of the special inspection will be documented in Inspection Report 50-254/2002003. The inspectors also validated that the licensee corrected the cause of the jet pump failure and all associated equipment condition issues prior to restarting Unit 1.
b.
Findings No findings of significance were identified.
4OA6 Meetings
.1 Inspection Period Exit Meeting The inspectors presented the inspection results to Mr. Tulon and other members of licensee management at the conclusion of the inspection on February 11, 2002. No proprietary information was identified.
PARTIAL LIST OF PERSONS CONTACTED Licensee T. Tulon, Site Vice President M. Perito, Acting Plant Manager D. Barker, Radiation Protection Manager W. Beck, Regulatory Assurance Manager G. Boerschig, Engineering Manager R. Gideon, Work Control Manager T. Hanley, Acting Operations Manager A. Javorik, Maintenance Manager K. Leech, Security Manager K. Moser, Chemistry/Environ/Radwaste Manager M. Snow, Nuclear Oversight Manager NRC M. Ring, Chief, Reactor Projects Branch 1 ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None
LIST OF DOCUMENTS REVIEWED 1R04 Equipment Alignment Number Subject/Title Date/Revision QCOP 1400-01 Core Spray System Preparation for Standby Operation Revision 13 QCOP 6600-04 Diesel Generator 1/2 Preparation for Standby Operation Revision 19 QCOP 1300-01 Reactor Core Isolation Cooling System Preparation for Standby Operation Revision 18 QCOP 2900-01 Safe Shutdown Makeup Pump System Preparation for Standby Operation Revision 16 1R05 Fire Protection Number Subject/Title Date/Revision Fire Hazards Analysis for Fire Zone SBO-4 Revision 12 Fire Hazards Analysis for Fire Zone SBO-3 Revision 12 Fire Hazards Analysis for Fire Zone 9.2 Revision 12 Fire Hazards Analysis for Fire Zone 9.1 Revision 12 1R07 Heat Sink Performance Number Subject/Title Date/Revision QCOS 1000-29 Residual Heat Removal Heat Exchanger Thermal Performance Test Revision 6 EPRI NP-7552 Heat Exchanger Performance Monitoring Guidelines Generic Letter 89-13 Service Water System Problems Affecting Safety-Related Equipment
1R11 Licensed Operator Requalification Number Subject/Title Date/Revision 04LORT7/EPU Dynamic 1 Reactor Recirculation Flow Controller Failure, Condensate Pump Trip, Group 1, Loss of T-12, and LOCA.
November 29, 2001 04LORT7/EPU Dynamic 2 Loss of Feedwater Heating, Feedwater Runout, Turbine Trip Without Bypass, and Anticipated Transient Without SCRAM.
November 29, 2001 1R12 Maintenance Rule Implementation Number Subject/Title Date/Revision Q2001-02784 2-2301-4 Failed to Stroke Closed During QCOS 2300-06 September 5, 2001 1R14 Non-routine Evolutions Number Subject/Title Date/Revision Strip Charts for Main Chimney, Offgas Radiation Monitor, Main Steam Line Radiation Monitor, and Reactor Recirculation Pump Parameters January 9, 2002 GE Service Information Letter 330 Jet Pump Beam Cracks June 9, 1980 February 1981 October 27, 1993 QCOS 0202-09 Reactor Recirculation Single Loop Operations Outage Report Revision 11 QCOP 0202-07 Reactor Recirculation Single Loop Operation Determination of Total Core Flow Revision 10 QCOA 0202-04 Reactor Recirculation Pump Trip - Single Pump Revision 17 1R15 Operability Evaluations Number Subject/Title Date/Revision Condition Report #
90738 Extent of Condition Review for BWR-3 Jet Pump Hold Down Beams January 16, 2002
Supporting Operability Evaluation for Condition Report #
90738 Extent of Condition Review for BWR-3 Jet Pump Hold Down Beams Revision 0 and Revision 1 Condition Report #
87785 Unit 1 Drywell Booster Fan Trip December 20, 2001 Supporting Operability Evaluation for Condition Report #
87785 Continued Ability to Maintain Drywell Temperature with a Failed Drywell Ventilation Booster Fan.
Revision 0 Condition Report #
88262 1B Torus Level Switch Failed to Reset During QCOS 2300-11 December 27, 2001 Supporting Operability Evaluation for Condition Report #
88262 Impact of Potential Crud/Debris on the Safety function of the 1B Torus Level Switch Revision 0 Supporting Operability Evaluation for Condition Report #
Q2001-03159 Leak from Residual Heat Removal Heat Exchanger 1A Revision 1 1R19 Post Maintenance Testing Number Subject/Title Date/Revision QCOS 6600-06 Diesel Generator Cooling Water Pump Flow Rate Test Revision 20 Work Order 00397798 Replace 1B Reactor Recirculation Pump Impeller Apparent Cause for Condition Report 90000, 1B Reactor Recirculation Pump Trip January 31, 2002 QCOS 0202-19 Unit 1 Reactor Recirculation System Post Maintenance Startup Revision 3 QCOP 0202-08 Reactor Recirculation Pump Seal Vent Revision 11 TIC-0325 Temporary Procedure for Uncoupled Run of 1B Reactor Recirculation Pump Motor January 25, 2002 Condition Report #
93517 1B Recirc Motor Tripped During Uncoupled Run January 31, 2002
Work Order 00397374 Troubleshoot and Repair Unit 1 Refueling Mast QCFHP 0500-08 Refueling Interlocks Revision 9 1R22 Surveillance Testing Number Subject/Title Date/Revision QCOS 0202-07 Jet Pump Flow Distribution Comparison Revision 14 QCOS 2300-04 HPCI System Cold Shutdown Valve Test Revision 14 QCOS 2900-04 Safe Shutdown Makeup Pump Reactor Vessel Injection Test at Cold Shutdown Revision 13 QCOS 2300-11 Contaminated Condensate Storage Tank/Torus Level Switch Functional Test Revision 18 1EP4 Emergency Action Level and Emergency Plan Changes Number Subject/Title Date/Revision Quad Cities Annex to the Exelon Emergency Plan Revision 12 Quad Cities Annex to the Exelon Emergency Plan Revision 13