IR 05000482/2003007

IR 05000482-03-007, on 06/02/03 - 06/24/03, Wolf Creek Generating Station. Evaluation of Changes, Tests, or Experiments, Heat Sink Performance, and Safety System Design and Performance Capability

ML032100274
Person / Time
Site:	Wolf Creek
Issue date:	07/28/2003
From:	Marschall C NRC/RGN-IV/DRS/EMB
To:	Muench R Wolf Creek
References
IR-03-007
Download: ML032100274 (27)

Text

uly 28, 2003

SUBJECT:

WOLF CREEK GENERATING STATION - NRC INSPECTION REPORT 05000482/2003-007

Dear Mr. Muench:

On June 20, 2003, the NRC completed an inspection at your Wolf Creek Generating Station.

The enclosed report documents the inspection findings, which were discussed on June 20 and 24, 2003, with Messrs. M. S. Larson, B. McKinney, respectively, and other members of your staff.

This 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.

Within these areas, the inspection consisted of selected examination of procedures and representative records, observations of activities, and interviews with personnel.

Based on the results of this inspection, the NRC has identified one finding of very low safety significance (Green). The finding did not present an immediate safety concern. Because of the very low significance and because you entered it into your corrective action program, the NRC is treating it as a noncited violation, consistent with Section VI.A of the Enforcement Policy.

The noncited violation is described in the subject inspection report. If you contest the violation or significance of the noncited violation, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001, with copies to the Regional Administrator, U.S. Nuclear Regulatory Commission, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Wolf Creek Generating Station facility.

Wolf Creek Nuclear Operating Corporation -2-In accordance with 10 CFR 2.790 of the NRCs "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 NRCs 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/

Charles S. Marschall, Chief Engineering and Maintenance Branch Division of Reactor Safety Docket: 50-482 License: NPF-42

Enclosure:

NRC Inspection Report 50-482/03-07

REGION IV==

Docket No.: 50-482 License No.: NPF-42 Report No: 05000482/2003007 Licensee: Wolf Creek Nuclear Operating Corporation Wolf Creek Generating Station Location: 1550 Oxen Lane NE Burlington, Kansas Dates: June 2-24, 2003 Lead Inspector: L. E. Ellershaw, Senior Reactor Inspector, Engineering and Maintenance Branch Inspectors: P. A. Goldberg, Senior Reactor Inspector, Engineering and Maintenance Branch W. M. McNeill, Senior Reactor Inspector, Engineering and Maintenance Branch G. Miller, Reactor Inspector, Engineering and Maintenance Branch R. L. Nease, Senior Reactor Inspector, Engineering and Maintenance Branch C. J. Paulk, Senior Reactor Inspector, Engineering and Maintenance Branch Accompanying D. R. Reinert, Engineering Associate Personnel: J. Leivo, Contractor, Beckman and Associates Approved By: Charles S. Marschall, Chief Engineering and Maintenance Branch Division of Reactor Safety

-2-SUMMARY OF FINDINGS IR 05000482/2003007; 06/02-24/2003; Wolf Creek Generating Station; Evaluation of Changes, Tests, or Experiments, Heat Sink Performance, and Safety System Design and Performance Capability The NRC conducted an inspection with six regional inspectors and one contractor. The inspection identified one green noncited violation. The significance of most findings is indicated by their color (green, white, yellow, red) using IMC 0609, "Significance Determination Process."

Findings for which the significance determination process does not apply may be "green" or be assigned a severity level after NRC management review. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649,

"Reactor Oversight Process," Revision 3, dated July 2000.

Cornerstone: Mitigating Systems

• Green. The inspectors identified a noncited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, regarding internal flooding calculation FL-08, Revision 0.

The calculation improperly credited 0.25 inch gaps under four doors for drainage of Room 3302, which contains vital Train B switchgear equipment. A walkdown of the room confirmed that the gaps were significantly less than the 0.25 inch assumed. Upon a postulated pipe break and subsequent flood in Room 3302, the water level in the room could increase to levels greater than analyzed, potentially affecting the vital equipment.

The finding is greater than minor because it affects the mitigating systems cornerstone objective to ensure reliability and capability of systems that respond to flood hazards.

Additionally, this finding is similar to Inspection Manual Chapter 0612, Appendix E, Example 3i. The licensees engineering staff had to recalculate the maximum flood level in Room 3302 because Calculation FL-08, Revision 0, improperly credited drainage under doors. The team considered this finding to be of very low safety significance because it did not represent an actual loss of safety function since the new analysis demonstrated that the maximum flood level in Room 3302 (approximately 5 inches)

would not damage the vital electrical equipment located in that room. Thus, the capability to safely shut down the plant would not be compromised. (Section 1R21.5)

Report Details 1. REACTOR SAFETY Introduction The NRC conducted an inspection to verify that the licensee adequately preserved the facility safety system design and performance capability and that the licensee preserved the initial design in subsequent modifications of the system selected for review. The scope of the review also included any necessary nonsafety-related structures, systems, and components that provided functions to support safety functions. This inspection also reviewed the licensees programs and methods for monitoring the capability of the selected systems to perform the current design basis functions. This inspection verified aspects of the initiating events, mitigating systems, and barrier cornerstones.

The licensee based the probabilistic risk assessment model for the Wolf Creek Generating Station on the capability of the as-built safety systems to perform their intended safety functions successfully. The inspectors determined the area and scope of the inspection by reviewing the licensees probabilistic risk analysis models to identify the most risk significant systems, structures, and components. The inspectors established this according to their ranking and potential contribution to dominant accident sequences and/or initiators. The inspectors also used a deterministic approach in the selection process by considering recent inspection history, recent problem area history, and all modifications developed and implemented.

The team reviewed in detail the component cooling water system. The primary review prompted parallel review and examination of support systems, such as, electrical power, instrumentation, and related structures and components.

The team assessed the adequacy of calculations, analyses, engineering processes, and engineering and operating practices that the licensee used for the selected safety system and the necessary support systems during normal, abnormal, and accident conditions. Acceptance criteria used by the NRC inspectors included NRC regulations, the technical specifications, applicable sections of the Updated Safety Analysis Report, applicable industry codes and standards, and industry initiatives implemented by the licensees programs.

1R02 Evaluations of Changes, Tests, or Experiments (71111.02)

a. Inspection Scope The team reviewed four licensee-performed 10 CFR 50.59 evaluations to verify that the licensee had appropriately considered the conditions under which the licensee may make changes to the facility or procedures or conduct tests or experiments without prior NRC approval. The licensee had performed only four evaluations since the last NRC inspection of 10 CFR 50.59 activities.

-2-The team reviewed an additional 13 licensee-performed 10 CFR 50.59 screenings in which the licensee determined that evaluations were not required, to ensure that the licensees exclusion of a full evaluation was consistent with the requirements of 10 CFR 50.59. The team also reviewed five licensee-performed 10 CFR 50.59 applicability determinations in which the licensee determined that screenings, as allowed by the regulations, were not required.

The team reviewed and evaluated the most recent licensee 10 CFR 50.59 program self assessment and 5 of the 28 corrective action documents written since the last NRC 10 CFR 59 inspection to determine whether the licensee conducted sufficient in-depth analyses of their program to allow for the identification and subsequent resolution of problems or deficiencies.

b. Findings No findings of significance were identified.

1R07 Biennial Heat Sink Performance (71111.07B)

.1 Performance of Testing, Maintenance, and Inspection Activities a. Inspection Scope The team reviewed the licensee's test and cleaning methodology for the residual heat removal heat exchanger, the component cooling water heat exchanger, the positive displacement pump room coolers, and the safety injection pump room coolers. In addition, the team reviewed test data for the heat exchangers and design and vendor-supplied information to ensure that the heat exchangers were performing within their design bases. The team also reviewed the heat exchanger inspection and test results.

Specifically, the team verified proper extrapolation of test conditions to design conditions, appropriate use of test instrumentation, and appropriate accounting for instrument inaccuracies. Further, the team verified that the licensee appropriately trended these inspection and test results, assessed the causes of the trends, and took necessary actions for any step changes in these trends. The team reviewed the methods and results of heat exchanger inspection and cleaning, and verified that the methods used to inspect and clean were consistent with industry standards and as-found results were appropriately dispositioned such that the final condition was acceptable.

b. Findings No findings of significance were identified.

.2 Verification of Conditions and Operations Consistent with Design Bases a. Inspection Scope For the selected heat exchangers, the team verified that the licensee established heat sink and heat exchanger condition, operation, and test criteria were consistent with the

-3-design assumptions. Specifically, the team reviewed the applicable calculations to ensure that the thermal performance test acceptance criteria for the heat exchangers were being applied consistently throughout the calculations. The team also verified that the appropriate acceptance values for fouling and tube plugging for the component cooling water heat exchangers remained consistent with the values used in the design-basis calculations. Finally, the team verified that the parameters measured during the thermal performance tests for the component cooling water heat exchangers were consistent with those assumed in the design bases.

b. Findings No findings of significance were identified.

.3 Identification and Resolution of Problems a. Inspection Scope The team verified that the licensee had entered significant heat exchanger/heat sink performance problems into the corrective action program.

b. Findings No findings of significance were identified.

1R21 Safety System Design and Performance Capability (71111.21)

.1 System Requirements a. Inspection Scope The team inspected the following attributes of the component cooling water system: (1)

process medium (water, steam, and air), (2) energy sources, (3) control systems, and (4) equipment protection. The team examined the procedural instructions to verify instructions as consistent with actions required to meet, prevent, and/or mitigate design basis accidents. The team also considered requirements and commitments identified in the Updated Safety Analysis Report, technical specifications, design basis documents, and plant drawings.

b. Findings No findings of significance were identified.

.2 System Condition and Capability a. Inspection Scope The team reviewed the periodic testing procedures for the component cooling water system to verify that the licensee periodically verified the capability of the system. The

-4-team also reviewed the systems operations by conducting system walkdowns; reviewing normal, abnormal, and emergency operating procedures; and reviewing the Final Safety Analysis Report, technical specifications, design calculations, drawings, and procedures.

b. Findings No findings of significance were identified.

.3 Identification and Resolution of Problems a. Inspection Scope The team reviewed a sample of component cooling water system problems identified by the licensee in the corrective action program to evaluate the effectiveness of corrective actions related to design issues. The sample included open and closed condition reports for the past three years and are listed in the attachment to this report. Inspection Procedure 71152, "Identification and Resolution of Problems," was used as guidance to perform this part of the inspection. Older condition reports that were identified while performing other areas of the inspection were also reviewed.

b. Issues and Findings No findings of significance were identified.

.4 System Walkdowns a. Inspection Scope The team performed walkdowns of the accessible portions of the component cooling water system and required support systems. Inspectors focused on the installation and configuration of switchgear, motor control centers, manual transfer switches, field cabling, raceways, piping, components, and instruments. During the walkdowns, the team assessed:

• The placement of protective barriers and systems;

• The susceptibility to flooding, fire, or environmental conditions;

• The physical separation of trains and the provisions for seismic concerns;

• Accessibility and lighting for any required local operator action;

• The material condition and preservation of systems and equipment; and

• The conformance of the currently-installed system configurations to the design and licensing bases.

-5-b. Findings No findings of significance were identified.

.5 Design Review a. Inspection Scope The team reviewed the current as-built instrument and control, electrical, and mechanical design of the component cooling water system. These reviews included an examination of design assumptions, calculations, required system thermal-hydraulic performance, electrical power system performance, protective relaying, control logic, and instrument setpoints and uncertainties. The team also performed selected single-failure evaluations of individual components and circuits to determine the effects of such failures on the capability of the system to perform its design safety functions. The team also reviewed the licensees calculations and methodology for ensuring the component cooling water system was protected against seismic, flooding, fire, and high energy line break events.

The team reviewed calculations, drawings, specifications, vendor documents, Final Safety Analysis Report, technical specifications, emergency operating procedures, and temporary and permanent modifications.

b. Findings Introduction The team identified a finding of very low safety significance involving a noncited violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control. Specifically, the team identified that the assumptions used in Calculation FL-08, Revision 0 for the drainage of Room 3302 did not agree with the as-built condition of the plant.

Description The team noted in Section 3.6.1.1 of the Wolf Creek Final Safety Analysis Report, that typically no credit is taken for drainage under doors. However, Calculation FL-08, Revision 0, stated that flow out under doors will be treated like flow out of a drain by assuming a 0.25 inch gap between the floor and the door. Although flooding calculations for most of the rooms analyzed in the calculation chose to ignore flow from under doors, the calculation for Room 3302 (Train B, engineered safety features switchgear room)

credited drainage under four doors each having 0.25 inch gaps between the bottom of the door and the floor of the room.

The team observed the engineered safety features switchgear rooms and verified that there were no gaps under doors 33011, 33023, and 32012. Additionally, the calculation took credit for drainage under door 33051. This door, however, sits on a 10-inch high curb, essentially permitting no drainage. The team determined that no credit from drainage out under doors could be assumed. During an internal flooding event, drainage of Room 3302 through the floor drains alone might not have removed enough water to prevent flooding of the safety-related electrical equipment.

-6-In response to the teams concerns regarding the lack of gaps beneath the doors of the engineered safety features switchgear room, the licensee initiated Problem Identification Report (PIR) 2003-1868 on June 20, 2003.

Analysis The team determined that this condition affected the mitigating systems cornerstone objective to limit the likelihood of a flooding event. The finding was greater than minor because the licensees engineering staff had to re-perform the calculation to ensure that enough flood water would drain from the room to prevent flooding of the safety-related electrical equipment. Additionally, the team considered this finding more than minor since the finding was similar to Example 3.i of Appendix E of Manual Chapter 0612. The team also considered this finding to be of very low safety significance because it did not represent an actual loss of safety function since the new analysis demonstrated that the maximum flood level in Room 3302 (approximately 5 inches) would not damage the vital electrical equipment located in that room; thus, the capability to safely shut down the plant would not be compromised.

The team assessed this finding as green because it does not represent an actual loss of a safety function due to flooding. The licensee implemented corrective actions to address this issue.

Enforcement 10 CFR Part 50, Appendix B, Criterion III states that the design basis must be correctly translated into specifications, drawings, procedures, and instructions. Contrary to the above, the licensee did not correctly translate the design basis into the internal flooding calculations for engineered safety features Switchgear Room 3302. Gaps beneath doors 33023, 33011, 33051, and 32012 were not of adequate size. Consequently, the actual flood height in the room could have exceeded the value found in Calculation FL-08, Rev. 0. This could have resulted in a failure of electrical components in Room 3302.

Because of the very low safety significance of the finding and because the licensee entered this issue into their corrective action program as PIR 2003-1868, on June 20, 2003, the team considered this to be a noncited violation, consistent with Section VI.A.1 of the NRC Enforcement Policy. (NCV 05000482/2003007-01)

.6 Safety System Inspection and Testing a. Inspection Scope The team reviewed the program and procedures for testing and inspecting selected components in the component cooling water system. The review included the results of surveillance tests required by the technical specifications and selective review of Class 1E control circuits for capability to test system functions.

b. Findings No findings of significance were identified.

-7-4. OTHER ACTIVITIES (OA)

4OA2 Problem Identification and Resolution During review of corrective actions, a minor violation for failure to identify and correct a condition adverse to quality was identified during the review of PIR 2001-2804. This PIR was initiated in response to a previous NRC inspection observation that the operating bands marked on the component cooling water control board temperature indicator did not correspond with the design documents. In response to that observation, licensee personnel initiated a PIR to correct the operating bands on the indicator. They failed, however, to identify that the condition adverse to quality was a human performance error in which directions for changing the indicator operating bands were omitted from the setpoint change request (EG 01 031). This caused the incorrect operating bands to be marked on the indicator. As a result of the failure to identify the condition adverse to quality, the licensee did not take actions to correct the human performance error.

Licensee personnel initiated PIR 2003-1802 to address the failure to identify and correct a condition adverse to quality.

4OA6 Management Meetings Exit Meeting Summary The team leader presented the inspection results in the areas of evaluations of changes, tests, or experiments, and safety system design and performance capability to Mr. M. S. Larson, Acting Plant Manager, and other members of licensee management and staff at the conclusion of the onsite inspection on June 20, 2003. Additionally, the biennial heat sink performance inspection results were telephonically presented to Mr. B.

McKinney, Site Vice President, and other members of licensee management and staff on June 24, 2003. Licensee management acknowledged the inspection findings.

At the conclusion of each inspection results presentation, the team asked licensee management whether any materials examined during the inspection should be considered proprietary. Proprietary information was reviewed by the team and left with the licensee at the end of the inspection. The licensee identified that the team had no proprietary information.

ATTACHMENT PARTIAL LIST OF PERSONS CONTACTED Licensee:

T. Anselmi, Manager, Design Engineering S. Fellers, Licensing Engineer B. McKinney, Site Vice President K. Scherich, Director, Engineering B. Smith, Supervisor, System Engineering J. Stamm, Assistant to Director Engineering S. Comstock - Inservice Test Engineer S. Hedges - Integrated Plant Scheduling Manager J. Gilmore - Scheduling Superintendent B. Kopecky - Outage Superintendent L. Brosch, Senior Operations Specialist S. Chaudhuri, Senior Engineer S. Collins, Floor and Equipment Drains System Engineer M. Ferrel, Maintenance Rule Coordinator D. Mosebey, Supervisor System Engineering V. Quach, Senior Engineer W. Selby, Acting Mechanical/Civil Engineering Supervisor R. Traudt, Technical Staff Engineer D. Womelsdorf, Component Cooling Water System Engineer LIST OF ITEMS OPENED, CLOSED AND DISCUSSED Opened 05000482/2003007-01 NCV Failure to correctly translate a design basis into the internal flooding calculations for engineered safety feature Switchgear Room 3302; thus the assumptions used in Calculation FL-08 did not agree with the as-built condition of the plant.

DOCUMENTS REVIEWED Procedures AI 28A-011, PIR Initiation, Revision 3 AI 28A-012, PIR Screening, Revision 4 AI 28A-013, PIR Evaluation, Action Plans, and Follow Up, Revision 6 AP 28A-001, Performance Improvement Request, Revision 23 INC L-1000, Calibration of Miscellaneous Loops, Revision 9

-2-INC C-1003, Calibration of Transmitters, Revision 7 STN IC-251, Calibration of CCW to the Reactor Coolant Pump Flow Loop, Revision 3 STS IC-508B, Calibration of Refueling Water Storage Tank Level Instrumentation, Revision 7 AP 25C-001, WCGS Leak Reduction of Primary Coolant Sources Outside of Containment, Revision 6 STS EG-100A, Component Cooling Water Pumps A/C Inservice Pump Test, Revision 19 STS EG-100B, Component Cooling Water Pumps B/D Inservice Pump Test, Revision 16 INC L-1000, Calibration of Miscellaneous Loops, Revision 9 AP 29B-002, ASME Code Testing of Pumps and Valves, Revision 4 AP 29B-003, Surveillance Testing, Revision 5 STN EG-001A, Train A Component Cooling Water System Flow Verification, Revision 1 STN EG-001B, Train B Component Cooling Water System Flow Verification, Revision 1 AP 23D-001, Motor Operated Valve Program, Revision 2 AP 23L-002, "Heat Exchanger Program," Revision 0 WCRE-09-EG, IST Design Basis Document, System: EG, Revision 1 WCOP-02, Inservice Testing Program for Pumps and Valves, Revision 12 STS KJ-001A, Integrated D/G and Safeguards Actuation Test - Train A, Revision 26 OFN SG-003, Natural Events, Revision 9 Surveillance Test and Verification Procedures STN-EG-001B, Train B Component Cooling Water System Flow Verification, dated December 16, 1997 STN-PE-033, CCW Heat Exchanger Performance Test, dated March 24, 2002 STN-PE-036, Safety Related Room Cooler Heat Transfer Verification and Performance Trending, October 11, 2002 STN-PE-033, CCW Heat Exchanger Performance Test, October 1, 2000 STN-EG-001A, Train A Component Cooling Water System Flow Verification, dated February 27, 1998

-3-TMP-EN-173, ESW Train B Post-LOCA Flow Balance, dated October 19, 1994 TMP-EN-171, ESW Train A Post-LOCA Flow Balance, dated October 21, 1994 SU3-EJ02, Residual Heat Removal System Preoperational Test Procedure, dated April 29, 1984 STS VT-001, Verification of OMN-1, MOV Exercise Requirements, Revision 2 STN-100A, Train A Component Cooling Water System Flow Verification Test Results, December 16, 1997 Calculations CN-PRRA-90-165-R1, Concurrent Initiating Events for Flooding, Revision 1 FL-05,Control Building Flooding, Revision 1 J-EG47,Stress Analysis of Instrument Lines System: EG - Component Cooling Water, Revision

LE-M-002, Flood Level in Aux. Bldg Rooms 1206 & 1207 due to Pipe Break, Revision 0 AN-96-126, Wolf Creek Generating Station Probabilistic Safety Assessment Flooding Analysis, Revision 0 E-H-8, System NB Protective Relays, Revision 5 F-2, Cable Sizing, Revision 0 F-3, Cable Sizing, Revision 4 XX-E-004, AC Motor Operated Valve Minimum Terminal Voltage, Revision 13 XX-E-006, AC System Analysis, Revision 5 XX-E-012, Safety-Related MCC Control Circuit Allowable Wire Lengths, Revision 1 J-K-EG01, Instrument Uncertainty Estimate and Safety Related Setpoints: System EG, Loops 1

& 2, Revision 1 J-K-EG03, Instrument Uncertainty Estimate and Safety Related Setpoints: System EG, Loop 62, Revision 1 J-K-GEN, Methodology for determination of instrument loop uncertainty estimates and safety related setpoints, Revision 0 J2C01, Accuracy: Pressure Transmitters, Rosemount 1153 Series B, Revision 1

-4-J2F01, Accuracy of Standard Orifice Plates, Revision 0 J-435, Orifice Type Flow Elements, Revision 1 BN-20, RWST Volumes/Level Setpoints, Revision 2 BN-J-002, Total Loop Uncertainty Calculation System BN, Loops 0930, 0931, 0932, and 0933, Revision 0 M-EG-5, Component Cooling Water System, Revision 1 GL-03-W, Auxiliary Building HVAC, Revision 1 GL-03-W-W1-CN001, "Auxiliary Building HVAC," Revision 1, Change Notice 1 EG-M-032, Component Cooling Water Heat Exchanger Performance During Normal Operations, Shutdown, and Post-LOCA Recirculation, Revision 0 GL-M-002, Aux Building Electrical Penetration Room Heat Load and Cooler Evaluation, Revision 0 GL-04-W, "RHR Pump Rooms 1109 and 1111 Heat Loads." Revision 1 GG-MH-001, "Cooling Capacity of Spent Fuel Pool Pump Room Coolers at Low Flow Conditions," Revision 2 GF-01-W, "Cooling Load - Motor Driven Aux Feedwater Pump Rooms," Revision 0 GL-M-002, "Aux. Building Electrical Penetration room Heat Load and Cooler Evaluation,"

Revision 1 FL-01, Flooding of the Auxiliary Building, Revision 0 FL-02, Flooding of the Aux Building Rms 1107-1114, Revision 0 FL-06, Auxiliary Building Flooding Due to Pipe Break, Revision 0 FL-08, Control Building Flooding, Revision 0 FL-09, Flooding of Individual Fuel Building Rooms, Revision 0 FL-10, Flooding of Diesel Building Rooms, Revision 0 FL-11, Auxiliary Building Penetration Rooms Flooding, Revision 0 FL-12, Control Building Flooding, Revision 0 FL-13, Auxiliary Building Area 5 Flooding, Revision 0

-5-FL-14, Flooding of Control Building, Room 3501, Revision 0 FL-16, Flooding of Fuel Building Rooms, Revision 0 Drawings 10466-J-04EG24(Q), Instrument Isometric Drawing CCW HX to RHR HX Flow, Revision 3 10466-J-110-0875-W05, Component Cooling Water System CCW Outlet to Reactor Coolant Pumps, Revision 0 D-76-81, Refueling Water Storage Tank, Revision 7 D-76-83, Details - Refueling Water Storage Tank, Revision 5 M-12EG02, Piping & Instrumentation Diagram Component Cooling Water System, Revision 16 WIP-J-12EG13A-00-A, Component Cooling Water System Containment Isolation Valves, Revision 0 M-15EG06, Hanger Location Drawing, Component Cooling Water System Auxiliary Building, Common Header, Revision 7 M-15EG07, Hanger Location Drawing, Component Cooling Water System Auxiliary Building, Common Header, Revision 12 M15EG03, Hanger Location Drawing, Component Cooling Water System, Auxiliary Building, B Train, Revision 11 CF-SP-43500-1, Residual Heat Removal Pump Seal Assembly, Revision H 500-VN49768, Pump Assembly, Revision 8 M-11EG01, System Flow Diagram, Component Cooling Water, Revision 1 M-11EG02, System Flow Diagram, Component Cooling Water, Revision 2 M-12EG01, Piping & Instrumentation Diagram, Component Cooling Water System, Revision 13 M-12EG02, Piping & Instrumentation Diagram, Component Cooling Water System, Revision 16 M-12EG03, Piping & Instrumentation Diagram, Component Cooling Water System, Revision 7 E-11005, List of Loads Supplied by Emergency Diesel Generator, Revision 24 E-11023, Relay Setting Tabulation and Coordination Curves, System NB, Sheet 1, Revision 4 E-11023, Relay Setting Tabulation and Coordination Curves, System NB, Sheet 2 Revision 4 E-11023, Relay Setting Tabulation and Coordination Curves, System NB, Sheet 11, Revision 0

-6-E-11NB01, Lower Medium Voltage System Class 1E 4.16 kV Single Line Meter and Relay Diagram, Revision 1 E-11NB02, Lower Medium Voltage System Class 1E 4.16 kV Single Line Meter and Relay Diagram, Revision 1 E-11NG01, Low Voltage System Class 1E 480V Single Line Meter and Relay Diagram, Revision 8 E-11NG02, Low Voltage System Class 1E 480V Single Line Meter and Relay Diagram, Revision 7 E-12NF-1(Q), Load Shedding and Emergency Load Sequence Logic, Revision 2 E-13EG01A, Schematic Diagram, Component Cooling Water Pump A, Revision 3 E-13EG01B, Schematic Diagram, Component Cooling Water Pump C, Revision 2 E-13EG01C, Schematic Diagram, Component Cooling Water Pump B, Revision 0 E-13EG01D, Schematic Diagram, Component Cooling Water Pump D, Revision 1 E-13EG02, Schematic Diagram, EGLV0001, EGLV0002, Demineralized Water Makeup to CCW Surge Tank , Revision 2 E-13EG03, Schematic Diagram, EGRV0009, EGRV0010, Component Cooling Water Surge Tank Vent, Revision 1 E-13EG05A, Schematic Diagram, Component Cooling Water Return from Nuclear Auxiliary Components, Revision 4 E-13EG05B, Schematic Diagram, EGHV0015, EGHV0016, Component Cooling Water Supply to Nuclear Auxiliary Components, Revision 4 E-13EG06, Schematic Diagram, EGHV0101, EGHV0102, Component Cooling Water Containment Isolation Valve, Revision 2 E-13EG07, Schematic Diagram, EGHV0101, EGHV0102, Component Cooling Water Supply to RHR Heat Exchanger, Revision 5 E-13EG08, Schematic Diagram, EGHV0069A, EGHV0069B, EGHV0070B, Component Cooling Water Supply/Return from Radwaste Building, Revision 2 E-13EG08A, Schematic Diagram, EGHV0070AComponent Cooling Water Return from Radwaste Building, Revision 2 E-13EG09A, Schematic Diagram, EGHV0061, Component Cooling Water Containment Isolation Valve, Revision 2

-7-E-13EG10, Schematic Diagram, EGHV0062, Containment Isolation Valve Return from Thermal Barrier Cooling Coil, Revision 4 E-13EG16, Schematic Diagram, EGTV0029, EGVT0030, CCW Heat Exchanger Outlet Temperature Control Valves, Revision 0 J-02EG01A(Q), Control Logic Diagram, Component Cooling Water System Pumps, Revision 5 J-12EG08A(Q), Control Logic Diagram, Component Cooling Water System CCW Supply/Return - Radwaste Building, Revision 1 J-12EG08B(Q), Control Logic Diagram, Component Cooling Water System CCW Supply/

Return - Radwaste Building, Revision 0 KD-7496, One Line Diagram, Revision 25 10466-A-1703, Radiation Zones - Normal Operation, Elevation 2026 - 0", Revision 3 10466-J-110-0199-W09, Instrument Loop Diagram, Component Cooling Water System Surge Tank Level, Revision W09 J-04EG47, Instrument Isometric Drawing Surge Tk B Flow Out, Revision 3 M-12EG01, Piping & Instrumentation Diagram Component Cooling Water System, Revision 13 M-12EG03, Piping & Instrumentation Diagram Componenet Cooling Water System, Revision 7 M-12LF01, Piping and Instrumentation Diagram Auxiliary Building Floor and Equipment Drain System, Revision 1 M-12LF03, Piping and Instrumentation Diagram Auxiliary Building Floor and Equipment Drain System, Revision 3 M-12LF03, Piping and Instrumentation Diagram Auxiliary Building Floor and Equipment Drain System, Revision 3 M-15EG01 (Q), Hanger Location Dwg. Component Cooling Water Sys. Aux Bldg. A Train, Revision 16 M-15EG03 (Q), Hanger Location Dwg. Component Cooling Water Sys. Aux Bldg. B Train, Revision 11 M-15EG04 (Q), Hanger Location Dwg. Component Cooling Water Sys. Aux Bldg. B Train, Revision 9 M-15EG06 (Q), Hanger Location Dwg. Component Cooling Water Sys. Aux Bldg. Common Header, Revision 7

-8-M-15EG07 (Q),Hanger Location Dwg. Component Cooling Water Sys. Aux Bldg. Common Header, Revision 12 M-15EG08 (Q), Hanger Location Dwg. Component Cooling Water Sys. Surge Tank Area, Revision 5 Configuration Change Packages (CCPs)

00289, CCW B Fuel Pool Clg HX Flow, Revision 0 04380, Evaluate CCW Temp Below 60EF, Revision 0 05906, CCW High Temperature Alarm Change, Revision 0 Plant Modification Requests (PMRs)

04857, Flow Transmitter EGFT0080 Over-ranged, Revision 0 04380, Evaluate CCW Temperature Below 60EF, Revision 2 03746, Alarm Setpoint Change CCW to RCP-Low, Revision 0 Setpoint Change Requests (SCRs)

EG 93 075, Range Change for CCW B to Fuel Pool Building HX Flow Transmitter EG 94 016, Change Setpoint per PMR 3746 R/0 EG 96 035, Setpoint Change to 105EF per CCP 05906 EG 96 055, Proposed Calibration Tolerance for CCW HX to RHR HX Flow EG 97 002, Range Change and Flow Transmitter Change Out per PMR 04857 R/1 EG 98 023, Revise Temperature Control Range for CCW HX Bypass Valve EG 00 017, Range Change for CCW B to Fuel Pool Building HX Flow Transmitter EG 00 056, Setpoint and Associated Banding Revised per CCP 09680 EG 01 031, Scale Changes for CCW HT Exch Outlet Temp Recorder Design Changes CCP No. 07164, CCW Pump Motor Protective Relay Instantaneous Setpoint, Revision 0.

CCP No. 10065, EG Physical Separation Exemption, Revision 0.

CCP No. 10188, CCW Alarm 074A Delay, Revision 0.

-9-PMR No. 03411, Limitorque: Class RH vs. Class B Motors, Revision 0.

PMR No. 03580, Addition of Time Delay Circuitry, Revision 0.

10 CFR 50.59 Evaluations 59 2001-0023, Compensatory Measures for Inoperable Electric Penetration Room Cooler (SGL 15A/B), July 15, 2002 59 2001-0024, Steam Generator Tube Rupture Transient and Radiological Response Based on Revised Operator Action Times, October 13, 2001 59 2002-0001, Updating a Final Safety Analysis Report Described Evaluation Methodology Regarding Post-Loss of Coolant Accident Subcriticality, October 02, 2002 59 2003-0001, Replace the Existing Regulating Transformers XPN07/08 A, B, &C with a Commercial Grade Three Phase Transformer, January 07, 2003 10 CFR 50.59 Screenings CAL-AL-16-W, Determine the Available Net Positive Suction Head for the Auxiliary Feedwater Pumps, with Dissolved Nitrogen in the Condensate Storage Tank, September 18, 2002 CAL-GL MH 002, Tubes/Circuits Plugging Criteria for Safety Injection Pump Room Coolers SGL09A & SGL09B, December 17, 2002 CAL-EF-M-043, Emergency Service Water Make-up Flow Rate to Auxiliary Feedwater - Test Acceptance Criteria, April 01, 2002 PROC-SYS AL-120, Feeding Steam Generators with a Motor Driven or Turbine Driven Auxiliary Feedwater Pump, March 19, 2002 PROC-SYS BB-202, Pressurizer Relief Tank Operation, March 19, 2002 PROC-SYS EF-203, Fill and Vent of Emergency Service Water Trains, March 19, 2002 PROC-SYS EC-320, Fuel Pool Cooling and Cleaning System Shutdown, June 25, 2002 PROC-SYS EJ-110, Residual Heat Removal System Fill and Vent Including Initial Reactor Coolant System Fill. December 11, 2002 PROC-SYS JE-201, Transferring NB01 Power Sources, February 13, 2003 PROC-SYS KJ-124, Post Maintenance Run of Emergency Diesel Generator B, December 05, 2002 PROC-SYS NB-201, Emergency Fuel Oil Storage Tank Filling, April 05, 2002 PROC-SYS NK-131, Energizing NK Buses, December 05, 2002

-10-CSM 660, Flux Mapping System Software Revision, February 19, 2002 10 CFR 50.59 Applicability Determinations Proc-AI 10-001, Fire Brigade Equipment Inventory, Maintenance and Cleaning, July 19, 2002 Proc-AI 10-005, Fire Evacuation, February 04, 2003 Proc-AP 10-100, Fire Protection Program, February 10, 2003 Proc-AP 10-102, Control of Combustibles, March 27, 2003 Proc-AP 10-103, Fire Protection Impairment Control, May 07, 2003 Performance Improvement Requests 1995-0997 2000-0141 2001-2021 2001-2766 2002-0734 2003-1114 1995-1162 2000-0300 2001-2117 2001-2783 2002-1330 2003-1603 1997-0958 2000-0330 2001-2333 2001-2783 2002-1574 2003-1658 1997-3138 2000-1553 2001-2637 2001-2797 2003-0667 2003-1659 1997-3738 2000-2412 2001-2646 2001-2804 2003-0740 2003-1802 1997-3978 2000-2433 2001-2655 2001-2950 2003-0764 2003-1828 1997-4062 2000-3094 2001-2728 2001-3043 2003-1008 2003-1829 1998-1176 2001-0855 2001-2745 2001-3079 2003-1012 Maintenance Work Orders 93-101488-002 99-206228-000 99-209975-004 99-209976-004 02-233783-000 93-101488-003 99-206228-001 99-209975-005 00-215389-000 02-233784-000 93-101488-012 99-206289-000 99-209976-000 00-216913-000 02-234351-000 98-129418-001 99-206289-001 99-209976-001 01-227275-000 02-234351-002 98-129418-002 99-209975-000 Work Package 101488 Task 2, Revision 0 Engineering Dispositions WO 00263-92, Revision 1 WR 00464-93, Revision 1 WR 01743-93, Revision 1 Work Requests (WRs)

06544-93 01015-91 02-029376 02-029377

-11-Surveillance Test Results for the Following Component Cooling Water Valves EGHV0015 EGHV0054 EGHV0060 EGHV0016 EGHV0058 EGHV0061 EGHV0053 EGHV0059 EGHV0062 Pump Test Data Component Cooling Water Pump Vibration Data, 4th Quarter 1999 - 1st Quarter 2003 Component Cooling Water Pump Train A Surveillance Test, June 11, 2003 Self-Assessments SEL 03-007, Heat Exchanger Program SEL 01-047, Self-Assessment of the Implementation of the Revised 10 CFR 50.59 Rule Requirements, November 13, 2001 SEL 03-017, Effectiveness of Implementation of the 10 CFR 50.59 Process, Draft Licensing Evaluations RER 97-114 Reportability Evaluation Request (RER)

RER 92-008 USAR Change Requests97-206 Miscellaneous Documents Westinghouse Letter SAP-98-114, February 25, 1998, "Revised RHR Cool Down Analysis -

Results and Calculation Note Transmittal" E-012.2-015-04, Data Sheet, Component Cooling Water Pump Motor, Revision 1.

E-012.2-018-04, Time-Current Heating Curve, Component Cooling Water Pump Motor, Revision 1.

M-018-01502, Goodrich Corporation Engineering Report, Wolf Creek NPP 6201 kW Diesel Generator Set, May 29, 2002.

M-018-0390-02, Colt Industries Special Report, Explanation of Frequency Dip Recovery Problems Encountered During the Sequential Load Testing, December 20, 1983.

-12-WCNOC Cable Code Report (SETROUTE), for component cooling water pumps motor feeder cables, run June 2, 2003.

SNUPPS Letter # SLNRC 81-109, to Harold Denton, NRC NRR, Subject: Power Systems Branch Review, September 22, 1981.

NUREG 0881, Safety Evaluation Report Related to Operation of Wolf Creek Generating Station Unit 1, April 1982 [Chapter 8].

NUREG 0881, Safety Evaluation Report Related to Operation of Wolf Creek Generating Station Unit 1, Supplement 1, August 1982 [Chapter 8].

NUREG 0881, Safety Evaluation Report Related to Operation of Wolf Creek Generating Station Unit 1, Supplement 2, June1983 [Chapter 8].

NUREG 0881, Safety Evaluation Report Related to Operation of Wolf Creek Generating Station Unit 1, Supplement 3, August 1983 [Chapter 8].

NUREG 0881, Safety Evaluation Report Related to Operation of Wolf Creek Generating Station Unit 1, Supplement 4, December 1983 [Chapter 8].

NUREG 0881, Safety Evaluation Report Related to Operation of Wolf Creek Generating Station Unit 1, Supplement 5, May 1985 [Chapter 8].

NUREG 0881, Safety Evaluation Report Related to Operation of Wolf Creek Generating Station Unit 1, Supplement 6, June 1985 [Chapter 8].

NUREG 0830, Safety Evaluation Report related to the operation of Callaway Plant, Unit No. 1, dated October 1981 SAP-92-211, Residual Heat Removal Pump IPE Event, Westinghouse letter dated August 11, 1992 M-10EG(Q), System Description: Component Cooling Water System, Revision 3 Interoffice Correspondence NP 92-0183, RER 92-008, R/0 - Concerns Regarding CCW Temperature Less Than 60EF - Preliminary Evaluation, January 30, 1992 Exchanger Specification Sheet WCNOC M-071-0015-03, Fuel Pool Cooling Heat Exchangers, May 12, 1977