ML24080A345

7 of the Wolf Creek Generating Station Updated Safety Analysis Report

ML24080A345
Person / Time
Site:	Wolf Creek
Issue date:	03/11/2024
From:	Mccoy J Wolf Creek
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
000348
Download: ML24080A345 (1)

Text

Wolf Creek Nuclear Operating Corporation T

Jaime H. McCoy Site Vice President

March 11, 2024 000348

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738

Subject:

Docket No. 50-482: Revision 37 of the Wolf Creek Generating Station Updated Safety Analysis Report

Commissioners and Staff:

f Pursuant to the updating requirements of 10 CFR 50. 71 (e), Wolf Creek Nuclear Operating Corporation (WCNOC) is submitting Updated Safety Analysis Report (USAR), Revision 37, on March 11, 2024. The 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 Commitment Changes," Revision 0, July 1999.

• 1 to this letter describes specifiq technical changes that have been processed since the issuance *of the USAR, Revision 36. In addition to these technical changes, editorial changes have been made and are included in Revision 37.

Attachment Ill to this letter provides a discussion of changes made to the Technical Requirements Manual (TRM) Revision 77.

I Attachment IV to this letter provides a discussion of changes made to the Quality Assurance Program (QAP) description that did* not

• reduce the commitments and are required to be submitted to the NRC in_accordancewith the requirements of 10 CFR 50.71(e), Maintenance of records, making of reports.

There are no newly identified structures, systems, or components (SSCs) that are subject to an aging management review or evaluation in the period from November 1, 2022, through October 31, 2023, as required by 10 CRF 54.37(b).

Enclosure I to this letter provides the CD-ROM su,bmittal of the Wolf Creek Generating Station (WCGS) USAR, Revision 37. This submittal satisfies the FSAR updating requirements of 1 O CFR50.71(e)(4). Enclosure I contains sensitive unclassified information and therefore warrants withholding under 10 CFR 2.390. '

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000348 Page 2 of 4

Enclosure II to this letter provides a CD-ROM containing the station-controlled drawings that are considered incorporated by reference into the USAR. Enclosure II contains sensitive unclassified information and therefore warrants withholding under 10 CFR 2.390.

Enclosure Ill to this letter provides a CD-ROM containing the Fire Hazards Analysis, incorporated by reference into the USAR. Enclosure Ill contains sensitive unclassified information and therefore warrants withholding under 10 CFR 2.390.

Enclosure IV to this letter provides a CD-ROM containing the Quality Program Manual and the EQSD-I, EQ Summary Document Section I Program Description, and EQSD-II, Equipment Qualification Summary Document Master List Section II, all of. which are incorporated by reference into the USAR. Enclosure IV contains sensitive unclassified information and therefore warrants withholding under 10 CFR 2.390.

Information from USAR Table 3.11 (8)-1, Plant Environmental Normal Conditions; USAR Table 3.11 (8)-2, Environmental Qualification Parameters for SNUPPS NUREG-0588 (LOCA, MSL8 and HEL8); USAR Table 3.11 (8)-3, Identification of Safety-Related Equipment and Components: Equipment Qualification; USAR Table 3.11 (8)-4, Containment Worst Case Radiation Levels (MRADs); USAR Table 3.11 (8)-5, Containment Spray Requirements; USAR Table 3.11 (8)-8, Exemptions from NUREG-0588 Qualification; USAR Table 3.11(8)-10, Equipment Added for NUREG-0737; and USAR Figures 3.11 (8)-1 through 3.11 (8)-49, were relocated from the USAR into EQSD-I and EQSD-11 and are incorporated by reference into the USAR. I This letter contains no new commitments. As previously stated, changes to existing regulatory commitments are included. 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) 364-4156, or Dustin Hamman at (620) 364-4204.

• I Sincerely, c!J~ J-1 3/YJfC/

Jaime H. McCoy

JHM/jkt

'000348 Page 3 of 4

J

Attachment I - Regulatory Commitment Management System (RCMS) Changes Attachment II - USAR Changes Processed Since Revision 36

Attachment Ill - Revision 77 to the Technical Requirements Manual

'Attachment IV - Quality Assurance Program Changes Since USAR Revision 36

\\

Enclosure I - CD-ROM Containing Updated Safety Analysis Report, Revision 37 Enclosure II - CD-ROM Containing Updated Safety Analysis Report Controlled Figure Drawings,

.Enclosure Ill - CD-ROM Containing Fire Hazards Analysis M-663-00d17A Enclosure IV - CD-ROM Containing Wolf Creek Quality Program Manual (QPM), Fire Analyses E-1F9900, E-1F9905, E-1F9910, E-1F9915, XX-E-013, Equipment Qualification Summary Document (EQSD)-I, and EQSD-11

• cc: S. S. Lee (NRC), w/a, wo/e J. D. Monninger (NRC), w/a, w/e G. E. Werner (NRC), 'wta, wle Senior Resident Inspector (NRC), w/a, w/e WC Licensing Correspondence, wo/a, wo/e - WO 24-000348 000348 Page 4 of 4

STATE OF KANSAS )

) ss COUNTY OF COFFEY )

Jaime H. McCoy, 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 saicl 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.

Jaime H.cCoy By ~5/m; Site Vice President

SUBSCRIBED and sworn to before me th~a~

NotaryPublic

Notarv Public

• JENNA Sta y Appointment Expiration Date I Z. / S / t.,b

)

Attachment I to 000348 Page-1 of 3

Attachment I to 000348

Regulatory Commitment Management System (RCMS) Changes Attachment I to 000348 Page 2 of 3

Commitment Changes

Commitment No. RCMS 2006-215 from letter No. ET 07-0020, dated May 25, 2007

During the review of the Wolf Creek Generating Station (WCGS), Unit 1, license renewal, application (LRA) by the NRC, Wolf Creek Nuclear Operating Corporation (V\\lCNOC) made:

commitments related to aging management programs (AMPs) to manage aging effects for 1 structures and components. This commitment regarding spillways comes from Commitment 18.

of NUREG-1915 Appendix A: WCGS Unit 1 License Renewal Commitments and is reiterated in:

USAR section A1.33 "RG 1.127, Inspection of Water-Control Structures Associated with Nuclear:

Power Plants".

• Commitment

Description:

Prior to the period of extended operation, procedures will; be enhanced: (1) so that the main dam service spillway and the auxiliary spillway will be:

inspected in accordance with the same specification, (2) to clarify the scope of, inspections for the spillways, (3) to add the 5 year inspection frequency for the main dam:

service spillway, and (4) to add cavitation to the list of concrete aging effects for surfaces i other than spillways. - i

I Change to Commitment: Closure of commitment.

Justification: The commitment is satisfied by the following:

(1) The auxiliary spillway was downgraded from safety-related to non-safety by Safety Classification Analysis (SCA) 94-0086-Rev. 2. This change brings the auxiliary spillway back to non-safety status as it was originally constructed. The surveillance instructions were transferred :

from the safety-related Specification C-404, to the non-safety-related Specification C-403. The.

main dam service and auxiliary spillways are now inspected in accordance with the same specification,

(2) The scope of the inspections for the auxiliary spillway and the service spillway were enhanced. The scope and technical requirements of these surveillances will conform to Kansas Administrative Regulation K.A.R. 5-40-90. The periodic surveillance of the main dam, auxiliary and service spillways also fall under the requirements of NRC Regulatory Guide 1.127 Rev. 01 for any condition that imposes operational constraints on the functioning of the spillways to pass the Probable Maximum Flood (PMP).

I (3) The surveillance frequency for the main dam spillways is once every three years as required !

by Kansas State regulation K.S.A. 82a-303b for high hazard dams. This is more conservative !

than the Regulatory Guide 1.127 Rev. 01 surveillance frequency of once every five years.

(4) Wolf Greek already examines and documents water control structures for cavitation while.

looking for concrete degradation. Additional notes were added to specification C-403 by Design :

Document Change Notice (DDCN) C-403-05-04 to specifically incll:lde cavitation to the list of

• concrete agin'g effects.

/

Attachment I to 000348

, Page 3 of 3

. Commitment No. RCMS 2006-217 from letter No. ET 07-0020, dated May 25, 2007

. In NUREG 1801, the NRC evaluated existing plant programs and documented the technical basis for determining where existing programs were adequate without modification and where

. existing programs needed to be augmented for the period of extended operation. This commitment comes from section XI.E6 that discusses the AMP for electrical cable connections

. not subject to 1 0 CFR 50.49 environmental qualification requirements.

Commitment

Description:

Prior to the period of extended operation: (1) the infrared thermography testing procedure will be enhanced to require an engineering evaluation when test acceptance criteria are not met. This engineering* evaluation will include identifying the extent of condition, the potential root cau.se for not meeting the test acceptance, and the likelihood of recurrence, and (2) A one-time inspection of a representative sample of low voltage low current or low load connections will be

~~~~- * '

, Change to Commitment: Prior to the period of extended operation: (1) the infrared thermography testing procedure will be enhanced to require using th~ corrective action program to perform an evaluation when test acceptance criteria are not met. This evaluation will

consider the extent of condition, the indications of aging effect, and changes to the one-time

.testing program or alternative insp~ction, and (2) A on~-time inspection of a representative

• sample of low voltage low current or low load connections will be performed.

.Justification: The NRC revised ' NUREG 1801 section XI.E6 based on operating experience.

. Therefore, Licensing Renewal commitment RCMS 2006-217 is changed to align with NRC

,approved NUREG-1801, Generic Aging Lessons Learned (GALL) Report, Revision 2. 1 to 000348 Page 1 of 5

Attachment II to 000348

USAR Changes Processed Since Revision 36 Attachment II to 000348 Page 2 of 5

USAR Change Request Description

22-011 PROCEDURES AP 07A-003, Al 07-006, Al 07A-017, Al 07A-019, AND Al 07A-020 WERE CONSOLIDATED INTO AP 07A-003 CLEAN AIR ACT COMPLIANCE PROCEDURE. THIS NEW CONSOLIDATED PROCEDURE (AP 07A-003) INVOLVES A CHANGE TO THE V\\IATER SOURCE TO THE WATER TREATMENT BUILDING NORTH, TO BE UTILIZED DURING OUTAGE OPERATIONS IN WHICH SERVICE WATER AND RAW WATER ARE UNAVAILABLE TO SUPPLY IONICS. THE SOURCE THAT WILL BE USED IS WATER FROM NEAR THE CIRC WATER OUTFALL, WHILE THE SERVICE WATER AND RAW WATER SYSTEMS ARE OUT OF SERVICE.

PAGE: 9.2-22 PAGE: 9.2-23

23-001 A NOTE TO FIGURE 3.6-1 WAS ADDED TO SHOW THAT TERMINAL END BREAK EP01-07 HAS BEEN DELETED. THE DELETED BREAK IS ALSO REMOVED FROM TABLE 3.6-4 SHEET 67.

TABLE: 3.6-4 (Sheet 67)

FIGURE: 3.6-1 (Sheet 40)23-002 \\ ' EDITORIAL CHANGES WERE MADE TO SECTION 5.3.1.6 AND 5.1.6.3 OF USAR.

THE SECTIONS HAD MULTIPLE PARAGRAPHS THAT WERE EXTRANEOUS INFORMATION OR THAT NEEDED TO BE REVISED AND RELOCATED. NO CHANGE WAS MADE TO THE TECHNICAL CONTENT.

PAGE: 5.3-7 PAGE: 5.3-8 PAGE: 5.3-12 PAGE: 5.3-13 PAGE: 5.3-14

23-003 MOVED TO USAR REV 38

23-004 THE SHIFT TECHNICAL ADVISOR ROLE IS NOW A SRO/STA DUAL ROLE, DUE TO LAR 232. THIS POSITION IS NO LONGER BEING FULFILLED BY THE SHIFT ENGINEER.

PAGE: 18.1-5 TABLE: 13.1-1 (Sheet12)

FIGURE: 13.1-2b

23-005 CONTROL CIRCUITS OF AFFECTED MOVS WERE RECONFIGURED IN RESPONSE TO INFORMATION NOTICE 92-18. DRAWINGS WERE REVISED TO REFLECT THESE CHANGES IN THE PLANT. USAR TABLE 1.7-1 WAS UPDATED TO REFLECT THE DRAWING UPDATES. THE TABLE WA$ ALSO REVIEWED AND UPDATED FOR ACCURACY.

TABLE: 1.7-1 (Sheet 3) TABLE: 1.7-1 (Sheet 4) TABLE: 1.7-1 (Sheet 5)

TABLE: 1.7-1 (Sheet 6) TABLE: 1. 7 -1 (Sheet 7) TABLE: 1.7-1 (Sheet 8)

" Attachment II to 000348 Page 3 of 5

TABLE: 1.7-1 (Sheet 9) TABLE: 1.7-1 (Sheet 10) TABLE: 1.7-1 (Sheet 11)

TABLE: 1.7-1 (Sheet 12) TABLE: 1.7-1 (Sheet 13) TABLE: 1.7-1 (Sheet 14)

TABLE: 1.7-1 (Sheet 15) TABLE: 1.7-1 (Sheet 16) TABLE: 1.7-1 (Sheet 17)

TABLE: 1.7-1 (Sheet 19) TABLE: 1.7-1 (Sheet 20) TABLE: 1:7-1 (Sheet 21)23-006 THE TURBINE INSPECTION FREQUENCY STATED IN USAR SECTION 10.2.3.6 WAS REPLACED WITH A GENERAL STATEMENT THAT THE TURBINES WILL BE

. INSPECTED PER NEIL LOSS CONTROL MANUAL GUIDANCE.

PAGE: 10.2-11

23-007 "ZIRCALOY-4" IS NO LONGER THE STANDARD CLADDING THAT IS USED AT WOLF CREEK. "ZIRCONIUM ALLOY" WAS SUBSTITUTED FOR THIS INSTANCE OF "ZIRCALOY-4" TO GENERICALLY COVER POTENTIAL ZIRCONIUM ALLOY CLADDINGS FOR HYDROGEN GENERATION. IN USAR SECTION 6, THE TERM "ZIRCALOY" IS ALSO USED TO REFER TO GENERIC ZIRCONIUM ALLOY CLADDINGS.

PAGE: 6.2-80

I 23-008 THE USAR WAS UPDATED TO ALIGN WITH NRC APPROVED NUREG-1801,:

GENERIC AGING LESSONS LEARNED (GALL) REPORT, REVISION 2, PART 1 XI.ES. :

' PAGE: 1 BA-22

23-009 COMPONENTS 8 AND 9, LISTED IN TABLE 9.2-13, ARE AIR-OPERATED VALVES!

(AOVS). THE USAR TABLE HAD THEM LISTED AS MOTOR-OPERATED ISOLATION VALVES (MOVS). THIS CHANGE UPDATED THE USAR TO REFLECT THE COMPONENTS AS DESIGNED IN THE PLANT CURRENTLY.

TABLE: 9.2-13 !

.I

I 23-010 THIS CHANGE UPDATES THE USAR TO ALIGN WITH GUIDANCE PROVIDED IN; GL 87-11 RELATED TO REFERENCE MEB 3-1 REV. 0 AND MEB 3-1 REV. 2. !

PAGE: 3.6-10 PAGE: 3.6-13 ' '

TABLE: 3.6-2a (Sheet 2) i i

1 23-011 USAR APPENDIX 3A WAS UPDATED BECAUSE CR 10022036 IDENTIFIED THAT' I THE DISCUSSION ON REG. GUIDE 1.65 DID NOT GET UPDATED ORIGINALLYi WHEN WCNOC BEGAN ISi INTERVAL 4.

• PAGE: 3A-26

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23-012 REFERENCE TO REGULATORY GUIDE 8.7 WAS UPDATED TO REVISION 4.

TABLE: 12.1-1 Attachment II to 000348 Page 4 of 5

23-013 SECTION 3.9(8) OF THE USAR REFERENCED ME101 COMPUTER CODE FOR PIPE STRESS ANALYSIS OF WOLF CREEK ASME PIPING. ME101 IS NO LONGER SUPPORTED BY BECHTEL AND WOLF CREEK HAS CHANGED THE PIPE STRESS ANALYSIS SOFTWARE TO PIPESTRESS, WHICH IS THE SOFTWARE WESTINGHOUSE USES FOR CLASS 1 PIPING ANALYSIS. GOING FORWARD, ALL NEW PIPE STRESS ANALYSES WILL BE PERFORMED IN PIPESTRESS AND SOME OF THE ME101 ANALYSES WILL BE CONVERTED TO PIPESTRESS, AS NECESSARY. OTHER EXISTING PIPE STRESS ANALYSES WILL BE LEFT AS ME101 UNLESS AND UNTIL REVISION OF THE ANALYSIS IS NECESSARY, AT WHICH TIME IT WOULD BE CONVERTED TO PIPESTRESS.

PAGE: 3.9(b)-2 TABLE: 3.9(8)-1

23-014 THIS CHANGE UPDATES THE USAR TO REFLECT CALCULATION CHANGE NOTICE 0720517.01-C-001-001-CN002. THIS CCN REEVALUATED THE LIFTED WEIGHT OF THE REACTOR VESSEL HEAD (RVH) SIMPLFIED HEAD ASSEMBLY (SHA), AND DETERMINED THE MAXIMUM ALLOWABLE WEIGHT WHICH CAN BE LIFTED AS A FUNCTION OF THE DROP HEIGHT OF THE SHA. BY KNOWING THE MAXIMUM ALLOWABLE WEIGHT, FUTURE QUESTIONS ABOUT MARGIN BETWEEN THE EVALUATED WEIGHT AND THE WEIGHT OF THE RVH SHA AS MEASURED BY THE LOAD CELL CAN BE MINIMIZED.

PAGE: 9.0-i PAGE: 9.. 0-x PAGE: 9.1-51 PAGE: 9.1-52 PAGE: 9.1-53 PAGE: 9.1-54 PAGE: 9.1-55 PAGE: 9.1-56 PAGE: 9.1-57 PAGE: 9.1-58 PAGE: 9.1-59 PAGE: 9.1-60 PAGE: 9.1-61 PAGE: 9.1-62 PAGE: 9.1-63 PAGE: 9.1-64 PAGE: 9.1-65 TABLE: 9.1-10 TABLE: 9.1-12

23-015 CHANGE PACKAGE 020728 SUPPORTS THE UPDATE OF FOUR DOCUMENTS:

M-10GS, SCA-91-0006, WCRE-34, AND THE USAR. THESE UPDATES INVOLVE THE CONTAINMENT HYDROGEN ANALVZERS: SGS02A AND SGS02B. PER GUIDANCE PROVIDED BY THE NRC THROUGH 10 CFR 50.44 AND APPROVED VIA LICENSE AMENDMENT REQUEST 157, THE HYDROGEN ANALYZERS ARE NO LONGER REQUIRED FOR A DESIGN BASIS LOCA, ONLY A BEYOND DESIGN BASIS LOCA. CHANGES TO ALL FOUR DOCUMENTS ARE TO BRING THEM INTO ALIGNMENT WITH THE CURRENT LICENSE AS AMENDED.

PAGE: 6.2-74 PAGE: 6.2-78 PAGE: 6.2-86 PAGE: 6.2-89 TABLE: 6.2.5-1 FIGURE: 6.2.4-1 FIGURE: 6.2.4-1

• FIGURE: 6.2.4-1 (Page 42 of 74) (Page 69 of74) (Page 70 of74)

FIGURE: 6.2.5-1 (Page 71 of 74) 1 to 000348 Page 5 of 5

23-016 APPENDIX 3A, REGULATORY GUIDE 1.133 REVISION 1 DATED 5/81, UPDATED TO REFLECT REMOVAL OF THE LOOSE PARTS MONITORING SYSTEM (LPMS)

FROM TRM AS WELL AS CHANGES TO MAINTENANCE STRATEGY.

PAGE: 13A-57

23-017 THE APPENDIX J PROGRAM NO LONGER FOLLOWS REG GUIDE 1.163 AND CURRENTLY FOLLOWS A NEW GUIDELINE UNDER NEI 94-01 REV 3-A, CONDITIONS AND LIMITATIONS SPECIFIED IN REV 2-A, AND REQUIRES AN UPDATE TO THE USAR. THE CHANGE WAS MADE UNDER THE IMPLEMENTATION OF LICENSE AMENDMENT 226 (CR 00146622).

I PAGE: 18A-17 PAGE: 18A-18

23-018 TO ALIGN WITH THE FUTURE STATE STAFFING ORGANIZATION, THE QUALITY DEPARTMENT IS COMBINING THE FIRST LINE LEADERSHIP OVERSIGHT ROLE OF THE SUPERVISOR PROCUREMENT AND QUALITY ASSURANCE INTO ONE POSITION. AS A RESULT OF INTEGRATING THE ROLES AND RESPONSIBILITIES A NEW LEADERSHIP TITLE, MANAGER NUCLEAR QUALITY ASSURANCE AND PROCUREMENT POSITION WAS CREATED. USAR SECTION.

13.1.2.2.9 QUALITY SECTION AND TABLE 13.1-1 (SHEET 8) WAS REVISED TO REFLECT FUTURE STATE STAFFING TITLE CHANGES. IN ADDITION, SECTION 13.1.2.2.9 REFERENCE TO PERFORMANCE-BASED QA AUDITS WAS REPLACED WITH COMPLIANCE-BASED QA AUDITS TO REFLECT THE FUNCTION OF THE QUALITY ASSURANCE GROUP.

PAGE: 13.1-11 TABLE: 13.1-1 (Sheet 8)23-019 A USAR WORDING ERROR WAS FOUND ON PAGE 18A-16. USARCR 2015-029 CHANGED USAR CHAPTER' 18, APPENDIX A, SECTION A1.26 CORRECTLY IN REVISION 29. HOWEVER, DURING THE NEXT USAR REV. 30 UPDATE AN ADMINISTRATIVE ERROR OCCURRED AS THE WORDS "INSPECTION FREQUENCY BEING AT LEAST ONCE EVERY TWO YEARS FOR ELECTRICAL MANHOLES WITHOUT SUMP PUMPS AND WITH THE INSPECTION" WERE INADVERTENTLY REMOVED. IT APPEARS THAT AN UPDATE TO A PREVIOUS SECTION PUSHED THE WORDS FROM USAR PAGE 18A-15 TO THE NEXT PAGE, BUT INSTEAD OF ADDING THE WORDS TO USAR PAGE 18A-16, THE WORDS DISAPPEARED. THIS USAR CHANGE REQUEST WILL FIX THIS ADMINISTRATIVE ERROR.

PAGE: 18A-16 PAGE: 18A-17 PAGE: 18A-18 Attachment Ill to 000348 Page 1 of 2

Attachment Ill to 000348

Revision 77 to the Technical Requirements Manual Attachment Ill to 000348 Page 2 of 2

REVISION 77 TO THE TECHNICAL REQUIREMENTS MANUAL

TRM REVISION 77

1. TR Bases B 3.5.1 is revised to reflect the current system configuration and alarm setpoints following upgrade of the

• 7300 system - Design Change Package (DCP) 13324.

Attachment IV to 000348 Page 1 of 2

Attachment IV to 000348

Quality Assurance Program Changes Since USAR Revision 36 Attachment IV to 000348 Page 2 of 2

QUALITY ASSURANCE PROGRAM CHANGES SINCE USAR REVISION 36

10 CFR 50.54, Condition of licenses, item (3) requires that changes to the Quality Assurance:

Program description that do not reduce the commitments to be submitted to the NRC in accordance with the requirements of 10 CFR 50.71(e), Maintenance of records, making of.

reports. The following is a summary of changes to the Quality Assurance Program that did not1 reduce cemmitments. '

j Revision to the Wolf Creek Quality Program Manual (WCQPM), (Revision 14, dated:

11/27/2023)

The following program changes based on 1 0CFR50.54(a)(3) are not a reduction of:

commitments in the Wolf Creek Quality Program.

This is an Operating Quality Program Evaluation based on 1 0CFR50.54(a)(3) that the following1 changes are not a reduction in the Wolf Creek Quality Pr_ogram. :

These changes will incorporate condition reports 10025260, 10026599 and 10026602 during this revision. This revision will also incorporate Procedure Change Request 74457, 74834,.

76663, 0000000852, 000000891 and 0000000912.

Administrative title change correction for a typographical error for the CEO and CNO. The.

Quality department is combining the first line leadership oversight role of the Supervisor Procurement and Quality Assurance into one position. As a result of integrating the roles and responsibilities a new leadership title, Manager Nuclear Quality Assurance & Procurement position was created. This new organizational title change wifl require a change to the Wolf Creek Updated Safety Analysis Report.

The term Responsible Manager, in the procedure writing process, is being replaced throughou, the procedure. Changes were made to better align with AP 15C-001, Procedure Writers Guide,*

Step 5.1 and 5.1.1. Organizational titles have changed throughout the company and the term Manager may not be applicable anymore for some organizations.

J Enclosure I to 000348 Page 1 of 2

Enclosure I to 000348

CD-ROM Containing Updated Safety Analysis Report, Revision 37 Enclosure I to 000348 Page 2 of 2

Subject Enclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated Safety Analysis Report, Revision 37.

Contact Name Jenna Slocum Mailing Address

• Wolf Creek Nuclear Operating Corporation P.O. Box411 Burlington, KS 66839 E-Mail Address jenna.e.slocum@evergy.com Phone Number 620-364-8831 ext. 4898

Document Components:

The CD-ROM labeled "WCGS USAR, Rev.37" contains the following files:

001_USAR.pdf 269 KB 002_USARC01.pdf 1.28 MB 003_ USARC02.0. pdf 70.0 MB 004_USARC02 Figures.pdf 56.1 MB 005_USARC03.pdf 69.8 MB 006_ USARC04.pdf 12.3 MB 007 _USARCOS.pdf 5.57 MB 008_USARC06.pdf 23.8 MB 009_USARC07.pdf 4.53 MB 010_USARC08.pdf 3.22 MB 011_USARC09.pdf 11.8 MB 012_USARC1 0.pdf 7.02 MB 013_USARC11.pdf 2.23 MB 014_USARC12.pdf 4.36 MB 015_USARC13.pdf 1.29 MB 016_USARC14.'pdf 399 KB 017 _USARC15.pdf 63.4 MB 018_USARC16.pdf 58.0 KB 019_USARC17.pdf 90.0 KB 020_USARC18.pdf 2.17 MB 021_USARNRCQ.pdf 452 KB 022_USAR Rev. 36-loep.pdf 443 KB Enclosure II to 000348 Page 1 of 2

Enclosure 11 to 000348

CD-ROM Containing Updated Safety Analysis Report Controlled Figure Drawings Enclosure II to 000348 Page 2 of 2

Subject Enclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated Safety Analysis Report (WCGS USAR} controlled figure drawings that are considered incorporated by reference into the WCGS USAR.

Contact Name \\ Jenna Slocum.

Mailing Address Wolf Creek Nuclear Operating Corporation P.O. Box 411 '

Burlington, KS 66839 E-Mail Address jenna.e.slocum@evergy.com Phone Number 620-364-8831 ext. 4898

Document Components:

The CD-ROM labeled "Updated Safety Analysis Report Controlled Figure Drawings Rev. 37" contains the following files:

001_Chapter 1.pdf 83.9 MB 002_Chapter 2.pdf 27.9 MB 003_Chapter 5.pdf 19.3 MB 004_Chapter 6.pdf 23.6 MB 005_Chapter 7.pdf 12.3 MB 006_Chapter 8.pdf 27.7 MB 007_Chapter 9.pdf 143 MB 009_Chapter 10.pdf 76.8 MB 009_Chapter 11.pdf 23.1 MB 010_Chapter 12.pdf 9.28 MB 011_Chapter 18.pdf 4.75 MB Enclosure Ill to 000348 Page 1 of 2

Enclosure Ill to 000348

CD-ROM Containing Fire Hazards Analysis M-663-00017 A

I Enclosure IWto 000348 Page 2 of 2

Subject Enclosed is the CD-ROM submittal of the Fire Hazards Analysis which is considered incorporated by reference into the WCGS USAR.

Contact Name Jenna Slocum Mailing Address Wolf Creek Nuclear Operating Corporation P.O. Box411 Burlington, KS 66839 E-Mail Address jenna.e.slocum@evergy.com Phone Number 620-364-8831 ext. 4898

Document Components: ',, /,

The CD-ROM labeled "Fi~e Hazards Analysis M-663-00017 A" contains the following files: I

014_M-663-00017A W08 1 to 86.pdf 94.8 MB

. 01s_M-663-00017A woa 87 to 813.pdf 93.6 MB 016_M-663-00017A W06 C to G3C.pdf 99.9 MB 017_M-663-00017A W06 G3D to H.pdf 74.7 MB Enclosure IV to 000348 Page 1 of 2

Enclosure IV to 000348

CD-ROM Containing the Wolf Creek Quality Program Manual (QPM), Fire Analyses E-1 F9900,.E-1 F9905, E-1F9910, E-1 F9915, XX-E-013, Equipment Qualification Summary Document (EQSD)-I, and EQSD-II Enclosure IV to 000348 Page 2 of 2

Subject.

• Enclosed is the CD-ROM submittal of the Wolf Creek Quality Program Manual (QPM), Fire Analyses E-1F9900, E-1F9905, E-1F9910, E-1F9915, XX-E-013, Equipment Qualification Summary Document (EQSD)-I, and EQSD-11 are considered incorporated by reference into the!

WCGS USAR. '

Contact Name. Jenna Slocum Mailing Addres's" Wolf Creek Nuclear Operating Corporation P.O. Box411 Burlington, KS 66839 i-E-Mail Address jenna.e.slocum@evergy.com i Phone Number 620-364-8831 ext. 4898 Document Components: ! '

The CD-ROM labeled "Quality Program Manual (QPM), Fire Analyses E-1 F9900, E-1 F9905, E-*

1F9910, E-1F9915, XX-E-013, Equipment Qualification Summary Document (EQSD)-I, and EQSD-11" contains the following files:

001_WCQPM Rev 14.pdf 667 KB 002_E-1F9900 Rev 10.pdf 15.4 MB 003_E-1F9905 Rev 12.pdf 5.02 MB 004_E:1F9905 Rev 13.pdf 5.13 MB 005_E-1 F9905 Rev 14.pdf 5.12 MB 006_E-1 F9910 Rev 18.pdf 36.9 MB 007_E-1F9910 Rev 19.pdf 14.7 MB 008_E-1 F9915 Rev H;,,pdf 1.31 MB 009_XX-E-013 Rev 4.pdf 14.2 MB 010_XX-E-013 Rev 4_CN002.pdf 3.20 MB 011J.XX-E-013 Rey 4_CN003.pdf 3.53 MB 012_XX-E-013 Rev 4_CN004.pdf 1.16 MB 013_XX-E-013 Rev 4_CNQ06.pdf 1.10 MB 014_X)(-E-013 Rev 4_CN007.pdf 589 KB 015_X)(-E-013 Rev 4_CN0P8.pdf 883 KB 016_XX-E-013 Rev 4_CN009.pdf 725 KB 017 _XX-E-013 Rev 4_CN010.pdf 1.04 MB 018_XX-E-013 Rev 4_CN011.pdf 1.09 MB 019_XX-E-013 Rev 4_CN012.pdf 920 KB 020_EQSD-I Rev 19.pdf 10.4 MB 021_EQSD-II Rev 34.pdf 5.09 MB