WO 11-0010, Updated Safety Analysis Report, Revision 24

Updated Safety Analysis Report, Revision 24

ML11173A255
Person / Time
Site:	Wolf Creek
Issue date:	03/10/2011
From:	Hedges S Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
WO 11-0010
Download: ML11173A255 (14)

Text

W LF CREEK 'NUCLEAR OPERATING CORPORATION Stephen E. Hedges Site Vice President March 10, 2011 WO 11-0010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482: Revision 24 of the Wolf Creek Updated Safety Analysis Report Gentlemen:

Pursuant to the updating requirements of 10 CFR 50.71(e), Wolf Creek Nuclear Operating Corporation (WCNOC) is providing its Updated Safety Analysis Report (USAR), Revision 24.

This submittal satisfies the Final Safety Analysis Report (FSAR) updating requirements of the aforementioned regulation.

Attachment I to this letter provides information relative to changes in regulatory commitments.

This information is provided in accordance with the guidance of Nuclear Energy Institute (NEI) 99-04, "Guidelines for Managing NRC Commitments," Revision 0, July 1999.

Attachment II to this letter describes specific technical changes that have been processed since issuance of the USAR, Revision 23. In addition to these technical changes, editorial changes have been made and are included in Revision 24.

Attachment III to this letter provides a discussion of changes made in Revisions 40 through 43 of the Technical Requirements Manual (TRM).

Enclosure I to this letter provides the CD-ROM submittal of the Wolf Creek USAR, Revision 24.

This submittal satisfies the Final Safety Analysis Report updating requirement of 10 CFR 50.71(e)(4). Chapter 2: Site Characteristics, Chapter 3: Design of Structures, Components, Equipment and Systems, Chapter 8: Electric Power, Chapter 9: Auxiliary Systems, and Chapter 12: Radiation Protection, are considered sensitive unclassified information and therefore warrant withholding under 10 CFR 2.390.

Enclosure II to this letter provides a CD-ROM containing the station-controlled drawings that are considered incorporated by reference into the USAR. Per the guidance of NEI 98-03, Revision 1, "Guidelines for Updating FSARs," the USAR figures that are identical to controlled drawings were relocated from the USAR in Revision 17. Enclosure II is considered sensitive unclassified information and therefore warrants withholding under 10 CFR 2.390.

P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HC/VET

WO 11-0010 Page 2 of 3 Enclosure III to this letter provides a CD-ROM containing the USAR Quality Program Manual, TRM, and the Fire Hazards Analysis that are incorporated by reference into the USAR. The entire TRM, Revision 43, is provided since TRM, Revision 41, incorporated the concept of functionality and impacted the majority of the manual. The Updated Safety Analysis Report Fire Hazards Analysis is considered sensitive unclassified information and therefore warrants withholding under 10 CFR 2.390.

There are no commitments contained in this letter. WCNOC has historically submitted updates to the USAR on March 11 of each year to coincide with the date of issuance of the WCGS operating license and to comply with the requirements of 10 CFR 50.71(e)(4). WCNOC considers that submittals made prior to or on March 11 satisfy the requirements of 10 CFR 50.71 (e)(4).

If you have any questions concerning this matter, please contact me at (620) 364-4190, or Mr.

Gautam Sen, Manager Regulatory Affairs at (620) 364-4175.

Sincerely, Hedges SEH/rlt Attachment I - Commitment Changes Attachment II - USAR Changes Attachment III - Revisions to the Technical Requirements Manual Enclosure I - Updated Safety Analysis Report Enclosure II - Updated Safety Analysis Report Controlled Drawings Enclosure III - Updated Safety Analysis Report Quality Program Manual, Technical Requirements Manual, and Fire Hazards Analysis cc: E. E. Collins (NRC), w/a, w/e G. B. Miller (NRC, w/a, w/e B. K. Singal (NRC), w/a, w/e Senior Resident Inspector (NRC), w/a, wo/e

WO 11-0010 Page 3 of 3 STATE OF KANSAS )

SS COUNTY OF COFFEY )

Stephen E. Hedges, of lawful age, being first duly sworn upon oath says that he is Site Vice President of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

Stephen E. H dg es Site Vice Pres' ep SUBSCRIBED and sworn to before me this b'day of IMhULO) ,2011.

' RHONDA L. TIEMEER Notary Public

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- OFICIAL- MY COMMISSION EXPIRES I e;- .SEAL:&

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Attachment I to WO 11-0010 Page 1 of 2 Commitment Changes Commitment No. 1990-039 from Letter NO 90-0104, dated April 9, 1990 Commitment

Description:

Integration of databases for fitness-for-duty and access screening is being performed.

Change to Commitment: The change to this commitment was removal of the commitment from the implementing procedure.

Justification: The commitment is met in the Security System Information System (SSIS).

Several improvements/changes have been made in the Access Screening and Fitness for Duty databases since the commitment was made in 1990. The latest change was the implementation of the SSIS in November 2007. With the implementation of SSIS access screening and fitness for duty information are combined into a single database. The SSIS system will not allow an individual to be granted unescorted access without all required elements, including fitness for duty, being satisfied. The implementation of SSIS is a more effective method than that previously used and replaces the need for integration of separate Access Screening and Fitness for Duty programs to prevent recurrence of the conditions for which the commitment was made.

Commitment No. 2009-366, Contained in Letter WO 09-0034, dated October 17, 2009 Commitment

Description:

Wolf Creek Nuclear Operating Corporation (WCNOC) and the owner companies will establish an upper tier WCNOC/Owners policy and agreement in accordance with Federal Energy Regulatory Commission (FERC) and applicable industry guidance to outline necessary program responsibilities and commitments between WCNOC and the Owners and establish lower tier implementation guidance documents covering, at a minimum, design, operation, and maintenance (including inspections and performance monitoring) for all equipment in the Wolf Creek Generating Station (WCGS) Switchyard up to and including the remote substation interfaces.

Change to Commitment: Completion date was revised to August 15, 2010. (NOTE: This commitment change was reported to the Nuclear Regulatory Commission (NRC) by letter ET 10-0015 on April 1, 2010)

Justification: The change in this commitment due date to August 15, 2010 will not have a significant impact on the intent of the commitment. The original commitment was made in Licensee Event Report (LER) 2009-002-00 to minimize a condition adverse to quality, a plant shutdown caused by the loss of offsite power. The agreement entered with Westar Energy will ensure that the appropriate activities are performed in the WCGS switchyard in accordance with FERC and applicable industry standards. This will minimize the likelihood of recurrence while the remaining actions are completed.

Commitment No. 2010-387, Contained in Letter WO 10-0012. dated March 11, 2010 Commitment

Description:

Identify and effect repairs of the source of the Refueling Water Storage Tank (RWST) leak to prevent further leakage.

Attachment I to WO 11-0010 Page 2 of 2 Change to Commitment: The commitment was revised to read, WCNOC will investigate the cause of the RWST leakage from the bottom of the tank using the test methods described in the original design specification. Repairs will be implemented as necessary to ensure American Society of Mechanical Engineers (ASME) Code requirements are satisfied." (NOTE: This commitment change was reported to the NRC by letter WO 10-0080 on December 1, 2010)

Justification: This change clarifies WCNOC's commitment regarding this violation to specify the test methods, and standards for acceptance of repairs.

Attachment II to WO 11-0010 Page 1 of 4 USAR CHANGES USAR Change Request Description 10-012 REVISE THE USAR TO REVISE THE HORSEPOWER FROM 3-3/4 TO 3.0/0.75 AND THE REVOLUTIONS PER MINUTE (RPM) FROM 1,7501438 TO 1,7401430 ON THE ESSENTIAL SERVICE WATER (ESW) TRAVELING WATER SCREEN, TABLE 9.2-5 (SHEET 2). THE SYSTEM DESCRIPTION AND INSTRUCTION MANUAL BOTH REFLECT THE CHANGED VALUE FOR THE HORSEPOWER AND RPM.

Table: 9.2-5 Sheet: 2 10-013 REVISE THE USAR TO ADD "CONTROLLED SWITCHING OF THE WOLF CREEK SUBSTATION BREAKERS" ON PAGES 8.2-6 AND 8.2-10. THIS CHANGE IS FOR CONSISTENCY. THIS CHANGE WILL CLARIFY THAT IF ONE OF THE THREE 345-KV LINES FAULT, THE BREAKERS IN THE SWITCHYARD WOULD TRIP, DEENERGIZING THE LINE. ANY ONE OF THE TWO REMAINING INCOMING 345-KV TRANSMISSION LINES CAN CARRY THE TOTAL ESF LOAD BY "CONTROLLED SWITCHING OF THE WOLF CREEK SUBSTATION BREAKERS."

Page: 8.2-10 Page: 8.2-6 10-014 REVISE THE USAR, PAGE 13.1-18, TO ADD W. C. BRANDT AS A SHIFT MANAGER.

Page: 13.1-18 10-015 REVISE THE USAR TO UPDATE TABLE 9.5A-1, SHEET 22. THE FIRE PROTECTION AUDIT FREQUENCY IS BEING CHANGED FROM "ANNUALLY" TO "AUDITS.. .ARE PERFORMED AS REQUIRED BY THE QUALITY PROGRAM MANUAL". THIS CHANGE IS MADE TO INCORPORATE NRC ADMIN LETTER 95-06.

Table: 9.5A-1 Sheet: 22 10-016 REVISE THE USAR TO INCORPORATE THE STATION'S USE OF NEI 97-06, STEAM GENERATOR PROGRAM GUIDELINES, IN LIEU OF REGULATORY GUIDE 1.83, WHICH WAS WITHDRAWN BY THE NRC ON NOVEMBER 3,2009.

Page: 12.4-6 Page: 5.4-20 Page: 5.4-19 Page: 5.4-16 Page: 3A-35

Attachment II to WO 11-0010 Page 2 of 4 USAR Change Request Description 10-017 REVISE THE USAR TO INCORPORATE CHANGE PACKAGE 13256. CHANGE PACKAGE 13256 HAS APPROVED THE REDUCTION IN FLOW RATE TO THE NORMAL CHARGING PUMP ROOM COOLER.

Page: 9.4-41 Table: 9.4-8 Sheet: 5 10-018 REVISE THE USAR TO INCORPORATE ADMINISTRATIVE AND EDITORIAL CORRECTIONS Page: 3A-11 Page: 3A-7 Page: 3A-6 Page: 17.0-0 Page: 2.2-8 Page: 2.2-7 Page: 2.2-6 Page: 8.2-10 Table: 10,3-1 Sheet: 1 Table: 7A-3 Sheet: 11.2 Table: 3.10(B)-i Sheet: 1 10-019 REVISE THE USAR TO CHANGE THE CLOSURE TIME OF THE MAIN STEAM ISOLATION VALVE (MSIV) AND MAIN FEEDWATER ISOLATION VALVE (MFIV)

HYDRAULIC ACTUATED VALVES TO A SYSTEM PRESSURE DEPENDENT TIME VS THE CURRENT TIME OF 3 SECONDS. THIS CHANGE CAPTURES THE MECHANICAL MODIFICATIONS OF THE VALVE REPLACEMENT.

Page: 10.3-9 Page: 10.3-5 Page: 10.3-4 Page: 10.0-vii Page: 7.3-57 Page: 3B-13 Page: 3.6-14 Page: 10.4-26 Page: 10.4-32 Table: 10.3-2 Sheet: 1 Table: 10.4-6 Sheet: 1 Table: 9.3-11 Sheet: 1 Table: 9.3-2 Sheet: 6 Table: 9.3-2 Sheet: 2 Table: 9.3-2 Sheet: 1 Table: 7.1-3 Sheet: 2 Table: 7.1-1 Sheet: 1 Table: 3.9(B)-16 Sheet: 3 Table: 3.9(B)-16 Sheet: 1 Table: 3.2-1 Sheet: 12

Attachment II to WO 11-0010 Page 3 of 4 USAR Change Request Description 10-020 REVISE THE USAR TO INCORPORATE THE USE OF FIRE-RESISTIVE ELECTRICAL CABLE MANUFACTURED BY MEGGIT SAFETY SYSTEMS. THE CABLE HAS BEEN DEMONSTRATED TO PROVIDE AN EQUIVALENT LEVEL OF PROTECTION, AS WOULD THE 3-HOUR AND 1-HOUR RATED CABLE.

Page: 8.1-18 Page: 8.3-36 Page: 8.3-30 Page: 8.3-29 Page: 8.3-27 Page: 8.1-21 Page: 8.1-17 Page: 7.1-11 Page: 3.71B-16 Page: 3A-56 Table: 9.5E-1 Sheet: 6 Table: 9.5A-1 Sheet: 32 Table: 9.5A-1 Sheet: 30 Table: 7.4-6 Sheet: 40 Table: 3.11(B)-7 Sheet: 1 Table: 3.11(B)-3 Sheet: 68 Table: 3.2-1 Sheet: 23 11-001 REVISE THE USAR TO INCORPORATE RELOCATION OF THE MAIN FEEDWATER CHECK VALVES FROM INSIDE CONTAINMENT TO OUTSIDE CONTAINMENT DURING REFUELING OUTAGE NO. 17.

Page: 15.2-23 Page: 15.2-22 Page: 15.2-20 Page: 15.2-18 Page: 15.2-13 Page: 15.2-12 Table: 15.2-1 Sheet: 5 Table: 15.2-1 Sheet: 4 Table: 15.2-1 Sheet: 3 Figure: 15.2-22 Figure: 15.2-21 Figure: 15.2-20 Figure: 15.2-19 Figure: 15.2-18 Figure: 15.2-17 Figure: 15.2-16 Figure: 15.2-15 Figure: 15.2-14 Figure: 15.2-13 Figure: 15.2-12 Figure: 15.2-11 Figure: 15.2-10 Figure: 15.2-9 11-002 REVISE THE USAR TO ADD THE NEW POSITION OF SUPERINTENDENT OPERATIONS SUPPORT (TRAINING) AND THE BIOGRAPHIES FOR TWO NEW SHIFT MANAGERS, D. R. BOWERS AND M. A. BLOW.

Page: 13.1-18 Page: 13.1-17 Figure: 13.1-2b

Attachment II to WO 11-0010 Page 4 of 4 USAR Change Request Description 11-003 REVISE THE USAR TO REPLACE SCAFFOLD NUMBER 08-SO154 IN TABLE 1.7-4 WITH SCAFFOLD NUMBER 10-SO154.

Table: 1.7-4 Sheet: 1 11-004 REVISE THE USAR TO INCLUDE SCAFFOLDING THAT WILL REMAIN IN THE PLANT FOR OVER 12 MONTHS FOR COMPONENT COOLING WATER VOID MONITORING.

Table: 1.7- 4 Sheet: 2 11-005 REVISE THE USAR TO IDENTIFY SCAFFOLDING THAT WILL REMAIN IN THE PLANT FOR OVER 12 MONTHS FOR COMPONENT COOLING WATER VOID MONITORING THAT REQUIRED A DESIGN CHANGE.

Table: 1.7- 4 Sheet: 2 11-006 REVISE THE USAR TO INCORPORATE ORGANIZATIONAL CHANGES Page: 13.1 -16 Page: 13.1-6 Page: 13.1-7 Page: 13.1-8 Page: 13.1 -9 Page: 13.1-10 Page: 13.1-11 Page: 13.1-12 Page: 13.1 -13 Page: 13.1-5 Page: 13.1-15 Page: 18.1-16 Page: 13.1 -20 Page: 13.4-1 Page: 13.5-1 Page: 13.5-2 Page: 13.5 i-6 Page: 13.5-7 Page: 13.5-8 Page: 13.5-9 Page: 13.55-11 Page: 13.1-14 Table: 13.1-1 Sheet: 3 Table: 13.1-1 Sheet: 1 Figure: 13.1-2 Figure: 13.1-1

Attachment III to WO 11-0010 Page 1 of 2 REVISIONS TO THE TECHNICAL REQUIREMENTS MANUAL 1 Technical Requirement (TR) 3.7.20, "Snubbers," and associated TR Bases were revised to identify the transient event inspection as a technical surveillance requirement.

Additionally, the TR Bases is being revised to identify a definition of unexpected potentially damaging transient and how this transient is determined.

2. Technical Surveillance Requirement (TSR) 3.3.14.3 were revised to change the 40 month Frequency for disassembly of one valve from each category listed in TSR 3.3.14.1 to 120 month Frequency for all valves listed in TSR 3.3.14.1. It has been determined that changing the interval to 120 months will not increase the potential for a main turbine overspeed and associated missile generation event. Calculation of missile probability does not consider the valve inspection interval to be a factor in determining the probability of missile generation. The change is more restrictive than the current requirements, which ensure that a small sample of valves was inspected relatively frequently but which did not ensure that every valve eventually received an inspection.

3. The Technical Requirements Manual (TRM) and TRM Bases were revised to differentiate between OPERABILITY and functionality to be consistent with the guidance in Regulatory Issue Summary (RIS) 2005-20, Rev. 1, "Revision to NRC Inspection Manual Part 9900 Technical Guidance, "Operability Determinations & Functionality Assessments for Resolution of Degraded or Nonconforming Conditions Adverse to Quality or Safety." The guidance in RIS 2005-20 indicates that the operability determination process is applicable to Technical Specification (TS) systems, subsystems, and components (SSCs) and that functionality applies to non-TS SSCs. Section 3.5 specifies that functionality is an attribute of SSCs that is not controlled by TSs. This includes additional changes to TR 3.4.17, Structural Integrity, and associated Bases that clarifies that when a degraded/nonconforming condition is identified on a TS-required ASME Code Class 1, 2, or 3 component, an immediate operability determination is performed to determine if structural integrity is maintained.

4. TRM pages 3.3-30 and 3.3-31 were revised to change the TR heading. TRM TR 3.3.18 is titled "Primary to Secondary LEAKAGE Detection Instrumentation." Pages 3.3-30 and 3.3-31 (first two pages of TR 3.3.18) have a heading of "Reactivity Control and Power Distribution Alarms TR 3.3.17." A format error occurred in a prior revision to the TRM that resulted in the TR 3.3.17 heading to appear on the first two pages of TR 3.3.18.

5. Page B 3.3.3-5 was revised to incorporate missing wording as a result of a prior revision.

The sentence in TSR 3.3.3.1 states: "It is based on the assumpti approximately the same value." and is being revised to "It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value."

6. Page B 3.3.16-5 was revised to add a double line at the bottom of the page indicating the end of TR B 3.3.16.

Attachment III to WO 11-0010 Page 2 of 2

7. Page B 3.4.3-3 was revised to be consistent with the TR 3.4.3 Required Actions. The TR 3.4.3 Required Actions are to restore pressurizer pressure/temperature to within limits.

The current wording in the TR 3.4.3 Bases indicate that a CR be initiated to address why the pressurizer pressure/temperature limit was not restored to OPERABLE status. The wording should specify that a CR be initiated to address why the pressurizer pressure/temperature limit was not restored to within limits or determine if the pressurizer is acceptable for continued operation.

8. Page B 3.4.16-2 was revised to add "hours" after 36 for the specified Completion Time for Required Actions B.1 and B.2. The change is an administrative change to correct a typographical error.

9. TR 3.7.23, "Class 1 E Electrical Equipment Air-Conditioning (A/C)," and associated Bases are being revised. A Note is added to the Condition A Required Actions to require entering the applicable Conditions and Required Actions of LCO 3.8.4, "DC Sources -

Operating," LCO 3.8.7, "Inverters - Operating," and LCO 3.8.9, "Distribution Systems -

Operating," for a failure of one Class 1E Electrical Equipment A/C train with an affected room temperature greater than or equal to 104 0 F. Additionally, the Completion Time for Required Action A.1 is revised from 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Guidance is provided in the TR 3.7.23 Bases that prior to removing one Class 1E Electrical Equipment A/C train from service for testing or maintenance, the compensatory measures specified in Required Action A.1 should be accomplished. The Bases also provides guidance that LCO 3.0.3 should be entered, as there is no LCO 3.8.7 Condition for two inoperable inverters.

10. Amendment No. 188 approved changes to the Technical Specification (TS) to permit use of the Westinghouse computer code, the Best Estimate Analyzer for Core Operations -

Nuclear (BEACON) power distribution monitoring system (PDMS), as described in WCAP-12472-P-A, "BEACON Core Monitoring and Operations Support System," to perform power distribution surveillances. WCNOC letter ET 09-0019 submitted changes to the TRM for the PDMS in lieu of TS requirements. The changes to the TRM include changes to TR 3.3.10 and the addition of new TR 3.3.19, "Power Distribution Monitoring System (PDMS)."

11. TRM pages 3.7-22, 3.7-23, and 3.7-24 were revised to change the TR heading. TRM TR 3.7.22 is titled "Area Temperature Monitoring." Pages 3.7.22 thru 3.7.24 have a heading of "Sealed Source Contamination TR 3.7.21". A format error occurred in a prior revision to the TRM that resulted in the TR 3.7.21 heading to appear on the pages of TR 3.7.22.

Enclosure I to WO 11-0010 Page 1 of 1 Subject Enclosed is the CD-ROM submittal of the Wolf Creek Updated Safety Analysis Report (USAR),

Revision 24. In accordance with 10 CFR 2.390, USAR Chapters 2, 3, 8, 9, and 12 contain sensitive unclassified information and therefore warrant withholding.

Contact Name Lucille Rockers Mailing Address Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 E-Mail Address lurocke*,wcnoc.com Phone Number 620-364-8831 ext. 4898 Document Components:

The CD-ROM labeled "Wolf Creek Updated Safety Analysis Report Rev.24" contains the following files:

001_USAR.pdf 2.56 MB, sensitive unclassified information 002_USARC01 .pdf 681 KB, publicly available 003_USARC02.0.pdf 38.3 MB, sensitive unclassified information 004_USARC02 Figures.pdf 28.8 MB, sensitive unclassified information 005_USARC03.pdf 24.0 MB, sensitive unclassified information 006_USARC04.pdf 2.59 MB, publicly available 007_USARC05.pdf 1.69 MB, publicly available 008_USARC06.pdf 16.6 MB, publicly available 009_USARC07.pdf 1.97 MB, publicly available 010_USARC08.pdf 1.06 MB, sensitive unclassified information 011_USARC09.pdf 15.1 MB, sensitive unclassified information 012_USARC10.pdf 869 KB, publicly available 013_USARC11.pdf 1.08 MB, publicly available 014_USARC12.pdf 902 KB, sensitive unclassified information 015_USARC13.pdf 353 KB, publicly available 016_USARC14.pdf 368 KB, publicly available 017_USARC15.pdf 8.59 MB, publicly available 018_USARC16.pdf 58 KB, publicly available 019_USARC17.pdf 67 KB, publicly available 020_USARC18.pdf 1.20 MB, publicly available 021_USARNRCQ.pdf 308 KB, publicly available 022_USAR Rev. 24-loep.pdf 446 KB, publicly available

Enclosure II to WO 11-0010 Page 1 of 1 Subject Enclosed is the CD-ROM submittal of the station-controlled drawings that are considered incorporated by reference into the Wolf Creek Updated Safety Analysis Report (USAR). In accordance with 10 CFR 2.390, this enclosure is considered sensitive unclassified information and therefore warrants withholding.

Contact Name Lucille Rockers Mailing Address Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 E-Mail Address lurocke*,wcnoc. com Phone Number 620-364-8831 ext. 4898 Document Components:.

The CD-ROM labeled "Updated Safety Analysis Report (USAR) Rev.24 Controlled Figure Drawings Only" contains the following files:

001_Chapter 1.pdf 19.7 MB, sensitive unclassified information 002_Chapter 2.pdf 3.90 MB, sensitive unclassified information 003_Chapter 5.pdf 3.51 MB, sensitive unclassified information 004_Chapter 6.pdf 4.10 MB, sensitive unclassified information 005_Chapter 7.pdf 1.93 MB, sensitive unclassified information 006_Chapter 8.pdf 5.86 MB, sensitive unclassified information 007_Chapter 9.pdf 47.1 MB, sensitive unclassified information 008_Chapter 10.pdf 21.6 MB, sensitive unclassified information 009 Chapter 11 .pdf 3.41 MB, sensitive unclassified information 010 Chapter 12.pdf 2.30 MB, sensitive unclassified information 011_Chapter 18.pdf 227 KB, sensitive unclassified information 012_Index Removed Figure List.pdf 91 KB, sensitive unclassified information

Enclosure III to WO 11-0010 Page 1 of 1 Subject Enclosed is the CD-ROM submittal of the station Quality Program Manual, Technical Requirements Manual, and Fire Hazards Analysis that are considered incorporated by reference into the Wolf Creek Updated Safety Analysis Report (USAR). In accordance with 10 CFR 2.390, the Updated Safety Analysis Report Fire Hazards Analysis is considered sensitive unclassified information and therefore warrants withholding.

Contact Name Lucille Rockers Mailing Address Wolf Creek Nuclear Operating Corporation P.O. Box 411 Burlington, KS 66839 E-Mail Address lurocke(Dwcnoc.com Phone Number 620-364-8831 ext. 4898 Document Components:

The CD-ROM labeled "Fire Hazards Analysis, Quality Program Manual & Technical Requirements Manual" contains the following files:

001_WFCKQPMR8.pdf 195 KB, publicly available 002_WFCKTRMR43.pdf 910 KB, publicly available 003_E-1 F9900.pdf 491 KB, sensitive unclassified information 004_E- 1F9905. pdf 1.02 MB, sensitive unclassified information 005_E-1F9910.pdf 30.1 MB, sensitive unclassified information 006_XX-E-013-Rev.2.pdf 1.44 MB, sensitive unclassified information 007_XX-E-013-Rev.2-CN001 .pdf 503 KB, sensitive unclassified information 008_XX-E-01 3-Rev.2-CN002.pdf 159 KB, sensitive unclassified information 009_XX-E-01 3-Rev.2-CN003.pdf 232 KB, sensitive unclassified information 010_XX-E-01 3-Rev.2-CN004.pdf 772 KB, sensitive unclassified information 011_XX-E-01 3-Rev.2-CN005.pdf 123 KB, sensitive unclassified information 012_M-663-00017A W03 CS to B1-98.pdf 30.2 MB, sensitive unclassified information 013_M-663-00017A W03 B1-99 to B2-40.pdf 30.8 MB, sensitive unclassified information 014_M-663-00017A W03 B2-41 to B6-2.pdf 49.2 MB, sensitive unclassified information 015_M-663-00017A W03 B6-3 to B8-3.pdf 35.4 MB, sensitive unclassified information 016_M-663-00017A W03 B8-4 to B8-147.pdf 40.7 MB, sensitive unclassified information 017_M-663-00017A W03 B8-148 to B13-25. pdf 36.4 MB, sensitive unclassified information 018_M-663-00017A W03 B 13-26 to G 1A-63. pdf 40.2 MB, sensitive unclassified information 019_M-663-00017A W03 G1A-64 to G2B-61 .pdf 45.5 MB, sensitive unclassified information 020_M-663-00017A W03 G2B-62 to G3D-50.pdf 29.3 MB, sensitive unclassified information 021_M-663-00017A W03 ATT G4 to AU- H.pdf 28.5 MB, sensitive unclassified information 022_WIP-M-663-00017A.pdf 50 KB, sensitive unclassified information