Text

Updated Safety Analysis Report (Usar), Revision 28
	ML15084A513
Person / Time
Site:	Wolf Creek
Issue date:	03/11/2015
From:	Reasoner C; Wolf Creek
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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	WO 15-0005
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W$LF CREEK NUCLEAR OPERATING CORPORATION Cleveland Reasoner Site Vice President March 11, 2015 WO 15-0005 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Subject:

Docket No. 50-482:

Revision 28 of the Wolf Creek Generating Station 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 28.

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

Per the requirement of 10 CFR 54.37(b), there are no newly identified systems, structures, and components that are subject to an aging management review or evaluation of time-limited aging analyses.

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

This information is provided in accordance with the guidance of NuclearEnergy 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 27. In addition to these technical changes, editorial changes have been made and are included in Revision 28.

Attachment III to this letter provides a discussion of changes made in Revisions 55 through 58 of the Technical Requirements Manual (TRM).

Enclosure I to this letter provides the CD-ROM submittal of the Wolf Creek Generating Station (WCGS) USAR, Revision 28. This submittal satisfies the Final Safety Analysis Report updating requirements 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.

7 053 P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNVET

WO 15-0005 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. According to 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.

Enclosure III to this letter provides a CD-ROM containing the USAR Fire Hazards Analysis and Quality Program Manual both of which are incorporated by reference into the USAR.

The USAR Fire Hazards Analysis is considered sensitive unclassified information and therefore warrants withholding under 10 CFR 2.390.

Enclosure IV to this letter provides a CD-ROM containing EQSD-I, EQ Summary Document Section I Program Description, and EQSD-lI, EQ Master List Section I1. Information from USAR Table 3.11(B)-i, Plant Environmental Normal Conditions; USAR Table 3.11(B)-2, Environmental Qualification Parameters for SNUPPS NUREG-0588 (LOCA, MSLB and HELB);

USAR Table 3.11(B)-3, Identification of Safety-Related Equipment and Components:

Equipment Qualification; USAR Table 3.11(B)-4, Containment Worst Case Radiation Levels (MRADs); USAR Table 3.11(B)-5, Containment Spray Requirements; USAR Table 3.11-(B)-8, Exemptions from NUREG-0588 Qualification; USAR Table 3.11(B)-10, Equipment Added for NUREG-0737; and USAR Figures 3.11(B)-i through 3.11(B)-49, has been relocated from the USAR into EQSD-I and EQSD-l1 in Revision 28 and is incorporated by reference into the USAR.

Enclosure IV is considered sensitive unclassified information and therefore warrants withholding under 10 CFR 2.390.

Enclosure V to this letter provides those changes made to the WCGS Unit 1 TRM (Revision 55 through 58) and includes a List of Effective Pages.

The WCGS TRM is incorporated by reference into the USAR.

This letter contains no commitments. 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) 364-4171, or Mr.

Steven R. Koenig at (620) 364-4041.

Sincerely, Cleveland Reasoner COR/rlt Attachment I -

Commitment Changes Attachment II -

USAR Changes Processed Since Revision 27 Attachment III - Revisions 55 through 58 to the Technical Requirements Manual

WO 15-0005 Page 3 of 4 Enclosure I -

Enclosure II -

Enclosure III -

Enclosure IV -

Enclosure V -

CD-ROM containing Updated Safety Analysis Report, Revision 28 CD-ROM containing Updated Safety Analysis Report Controlled Figure Drawings CD-ROM containing Updated Safety Analysis Report Fire Hazards Analysis and Quality Program Manual CD-ROM containing Updated Safety Analysis Report EQSD-I, EQ Summary Document Section I Program Description, and EQSD-II, EQ Master List Section II Technical Requirements Manual Replacement Pages and List of Effective Pages cc:

M. L. Dapas (NRC), w/a, w/e C. F. Lyon (NRC), w/a, w/e N. F. O'Keefe (NRC), w/a, w/e Senior Resident Inspector (NRC), w/a, w/e

WO 15-0005 Page 4 of 4 STATE OF KANSAS

)

) SS COUNTY OF COFFEY )

Cleveland Reasoner, 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.

Byy__

Cleveland Reasoner Site Vice President SUBSCRIBED and sworn to before me this I I'L//day of 1ilb_.)wh

,2015.

i-RHONDA L. EMEYER

' My Appointment Expires Notary Public Expiration Date

lII,

,l I

/N

Attachment I to WO 15-0005 Page 1 of 7 Attachment I to WO 15-0005 Commitment Changes

Attachment I to WO 15-0005 Page 2 of 7 Regulatory Commitment Management System (RCMS) Changes Commitment No. RCMS 2013-481 from WM 13-0014, dated 06/26/2013 Commitment

Description:

Wolf Creek Nuclear Operating Corporation (WCNOC) will complete 40 percent (107 of 267) of the Maintenance craft performed Technical Specification surveillance procedures. These will be prioritized based on the importance and frequency of use so that the most commonly performed procedures are considered first.

Change to Commitment: This commitment has been satisfied. This commitment has been changed to closed and archived.

Justification: Greater than 40 percent of Maintenance craft performed Technical Specification surveillance procedures have been revised and released.

Commitment No. RCMS 2013-479 from WM 13-0014, dated 06/26/2013 Commitment

Description:

WCNOC will verify completion of 40 percent (580 tasks) of the new preventive maintenance scope of high critical (FID-1) classified assets as a result of Phase 1 of the ongoing Preventive Maintenance Optimization project.

FID-1 components are equipment whose failure would have a significant impact on level and continuity of risk, safety functions, production and compliance.

Change to Commitment: This commitment has been satisfied. This commitment has been changed to closed and archived.

Justification: Greater than 40 percent of Phase 1, FID-1 First Time Preventive Maintenances has been completed.

Commitment No. RCMS 2013-478 from WM 13-0014, dated 06/26/2013 Commitment

Description:

Essential Service Water (ESW) Piping Integrity

1) ESW Water Hammer: Wolf Creek Nuclear Operating Corporation (WCNOC) will install the modification to mitigate water hammer during the Mid-Cycle Outage.

2) ESW Below Ground: WCNOC will complete the below ground piping installation, tie-in and testing during the Mid-Cycle Outage.

3) ESW Above Ground: WCNOC will replace a minimum of 1200 linear feet during the Mid-Cycle Outage.

Change to Commitment: Items 2 and 3 were changed to closed and archived. Item 1 was transferred to RCMS 2012-457.

Justification:

Items 2 and 3 were completed by 5/1/2014. The commitment is being closed with the remaining action being transferred to RCMS 2012-457, the original Notice of Violation (NOV) EA-1 2-135 response, and modified in accordance with letter WM 14-0011.

Attachment I to WO 15-0005 Page 3 of 7 Commitment No. RCMS 2005-132 from WO 05-0003. dated 02121/2005 Commitment

Description:

WCNOC is working with the State of Kansas to obtain survey information regarding offsite mobile chemical sources. WCNOC will update both the offsite and onsite hazardous chemical assessments in accordance with Regulatory Guide 1.78, Rev 1, and the measured unfiltered inleakage results.

Change to Commitment:

This commitment is a duplicate of RCMS #2005-087.

The commitment has been closed and archived.

Justification: This commitment was written in response to Generic Letter 2003-01, Control Room Habitability. The intent of this commitment is covered by RCMS #2005-087.

Commitment No. RCMS 2006-241 from ET 06-0035, dated 10/05/2006 Commitment

Description:

If the revised analysis shows that the crack-growth acceptance criteria are exceeded during the subsequent operating cycle, WCNOC will, within 30 days, submit the revised analysis for Nuclear Regulatory Commission (NRC) review. If the revised analysis shows that the crack-growth acceptance criteria are not exceeded during either the current or the subsequent operating cycle, WCNOC will, within 30 days, submit a letter to the NRC confirming that its analysis has been revised.

Change to Commitment:

This commitment was closed due to the implementation of the Inservice Inspection program.

Justification:

10 CFR 50.55a(g)(6)(ii)(D)(1) states as follows:

"All licensees of pressurized water reactors shall augment their inservice inspection program with ASME Code Case N-729-1 subject to the conditions specified in paragraphs (g)(6)(ii)(D)(2) through (6) of this section.

Licensees of existing operating reactors as of September 10, 2008 shall implement their augmented inservice inspection program by December 31, 2008. Once a licensee implements this requirement, the First Revised NRC Order EA-03-009 no longer applies to that licensee and shall be deemed to be withdrawn."

Commitment No. RCMS 2006-239 from ET 06-0035, dated 10/05/2006 Commitment

Description:

If the NRC Staff finds that the crack growth formula in industry report MRP-55 is unacceptable, WCNOC will revise its analysis that justifies relaxation of the order within thirty days after NRC informs WCNOC of an NRC approved crack-growth rate formula.

Change to Commitment:

This commitment was closed due to the implementation of the Inservice Inspection program.

Justification:

In accordance with 10 CFR 50.55a(g)(6)(ii)(D)(1), once a licensee implements the Inservice Inspection Program, the First Revised NRC Order EA-03-009 no longer applies to that licensee and shall be deemed to be withdrawn.

Attachment I to WO 15-0005 Page 4 of 7 Commitment No. RCMS 2006-240 from ET 06-0035, dated 10/05/2006 Commitment

Description:

If WCNOC's revised analysis shows that the crack growth acceptance criteria are exceeded prior to the end of the current operating cycle, this relaxation request will be rescinded and WCNOC will, within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , submit to the NRC written justification for continued operation.

Change to Commitment:

This commitment was closed due to the implementation of the Inservice Inspection program.

Justification:

In accordance with 10 CFR 50.55a(g)(6)(ii)(D)(1), once a licensee implements the Inservice Inspection Program, the First Revised NRC Order EA-03-009 no longer applies to that licensee and shall be deemed to be withdrawn. A revised Operating License NPF-42 was released on 12/9/2008 that removed Order EA-03-009, Interim Inspection Requirements for Reactor Pressure Vessel Heads at pressurized water reactors (Reference Condition Action 5523).

Commitment No. RCMS 2005-131 from WO 05-0003. dated 02/21/2005 Commitment

Description:

WCNOC will submit a license amendment request to revise the Technical Specifications within one year after NRC resolution of TSTF-448, "Control Room Habitability."

This license amendment request will utilize the guidance of TSTF-448, as appropriate.

Change to Commitment: This commitment was satisfied in 2008, and is being closed and archived.

Justification: This commitment was written in response to Generic Letter 2003-01, "Control Room Habitability." TSTF-448 Notice of Availability was issued 01/17/07. Letter WO 08-0001, "Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process" was submitted, on 01/15/2008, as a request to revise the TS.

Incorporated by Amendment 179.

Commitment No. RCMS 2007-291 from WM 06-0033. dated 08/25/2006 Commitment

Description:

The license amendment will be implemented within 30 days of issuance. Final Technical Specification (TS) Bases changes will be implemented pursuant to TS 5.5.14 at the time the amendment is implemented.

Change to Commitment:

This commitment was satisfied, and changed to closed and archived.

Justification:

License amendment No. 171, was issued 11/07/2006. The amendment was implemented on 11/08/2006.

Attachment I to WO 15-0005 Page 5 of 7 Commitment No. RCMS 2013-476 from ET 13-0017, dated 05/16/2013 Commitment

Description:

If changes are required to address DW-12-013, WCNOC will implement required changes, including emergency (EMG) procedure changes and associated training if required.

Change to Commitment: The commitment was closed and archived.

Justification: This commitment was made in response to Generic Letter 2004-02 and Generic Safety Issue-191.

It was determined that WCNOC is not susceptible to core blockage of 15 g/FA (grams per fuel assembly), since further testing by the PWROG has confirmed that the chemical effects do not form with in the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of a Loss of Coolant Accident response.

It was concluded that changes to are not required to address DW-1 2-013.

Commitment No. RCMS 2010-378 from WO 09-0044, dated 11/23/2009 Commitment

Description:

The elements to establish, implement, and maintain the Cyber Security Program as described in Chapter 4 of the Cyber Security Plan will be implemented.

Schedule will be available onsite for inspection.

Change to Commitment: This commitment was changed to closed, archived.

Justification:

The source document, letter WO 09-0044, "Revision to Renewed Facility Operating License and Request for Approval of the Cyber Security Plan" and the commitments contained in WO 09-0044, were withdrawn by WCNOC. As such, the commitments made are no longer valid.

Letter WO 10-0048, "Revision to Renewed Facility Operating License and Request for Approval of the Cyber Security Plan" was submitted in the place of WO 09-0044, and the replacement commitment was RCMS 2013-488. RCMS 2013-488 was superceded by RCMS 2013-489 found in letter WO 11-0017, "Response to Request for Additional Information Regarding License Amendment Request for Approval of the Cyber Security Plan."

Cyber security requirements are codified as new 10 CFR 73.54.

Commitment No. RCMS 2010-377 from WO 09-0044, dated 11/23/2009 Commitment

Description:

For cyber security controls that have been identified for implementation by the process described in Section 3 of the Cyber Security Plan, an implementation plan will be prepared and available for on-site inspection.

Change to Commitment: This commitment was closed and archived.

Justification:

The source letter, WO 09-0044, was withdrawn by WCNOC.

As such, the commitments in this letter are no longer valid. Letter WO 10-0048 was submitted in place of WO 09-0044, and the replacement commitment was RCMS 2013-488. RCMS 2013-488 was superceded by RCMS 2013-489 found in letter WO 11-0017. Cyber security requirements are codified as new 10 CFR 73.54.

Attachment I to WO 15-0005 Page 6 of 7 Commitment No. RCMS 2010-376 from WO 09-0044, dated 11/23/2009 Commitment

Description:

The analysis of digital computer systems and networks in accordance with Section 3 of the Cyber Security Plan will be performed and results documented as required.

Change to Commitment: This commitment was closed and archived.

Justification:

The source document, letter WO 09-0044 and the commitments contained in WO 09-0044, were withdrawn by WCNOC.

As such, the commitments made are no longer valid. Letter WO 10-0048 was submitted in the place of WO 09-0044, and the replacement commitment was RCMS 2013-488.

RCMS 2013-488 was superceded by RCMS 2013-489 found in letter WO 11-0017. Cyber security requirements are codified as new 10 CFR 73.54.

Commitment No. RCMS 2013-488 from WO 10-0048, dated 07/19/2010 Commitment

Description:

Complete the implementation and enter the maintenance phase of the WCGS NRC approved Cyber Security Program.

All required modifications implemented.

All required procedures updated. All required training completed.

Change to Commitment: The status of this commitment has been changed to closed and archived.

Justification:

RCMS 2013-489 found in letter WO 11-0017 supercedes RCMS 2013-488 found in letter WO 10-0048.

Commitment No. RCMS 2013-469 from WO 12-0071, dated 12/13/2012 Commitment

Description:

WCNOC will add corrosion coupon test locations to the supply and return lines for both ESW trains at the above-ground to below-ground interface in the 1974' elevation of the Control Building.

Change to Commitment: This commitment was closed and archived.

Justification: This commitment is a duplicate of RCMS 2012-456. The source document for 2012-456 is letter WM 12-0023, "Reply to Notice of Violation EA-12-135." The commitment date was changed to 04/02/2014 based on letter WO 12-0071, "Revision to a Commitment Made in Reply to Notice of Violation EA-12-135." The commitment was able to be moved due to the Service water corrosion monitoring equipment monitoring both Service water and ESW.

Also, new ESW piping is currently being installed, which will include corrosion coupon locations.

This commitment was made in response to NOV EA-12-135.

Attachment I to WO 15-0005 Page 7 of 7 Commitment No. RCMS 2006-158 from ET 06-0002, dated 02/07/2006 Commitment

Description:

The purpose of this commitment was to track the 90 day implementation of a license amendment to the TS Bases. The commitment was written for a revision to the Technical Specification 3.3.1, "Reactor Trip System (RTS) Instrumentation."

Change to Commitment: Changed the status of the commitment to closed and archived.

Justification:

This RCMS was implemented in Revision 29 of the TS Bases, dated 10/17/2006. Updated Safety Analysis Report (USAR) change request 2011-020.

Commitment No. RCMS 2004-081 from WO 04-0027, dated 07/23/2004 Commitment

Description:

WCNOC has verified that a hydrogen monitoring system capable of diagnosing beyond design-basis accidents is installed at Wolf Creek Generating Station (WCGS) and is making a regulatory commitment to maintain that capability. The hydrogen monitors will be included in the Technical Requirements Manual (TRM).

This regulatory commitment will be implemented within 90 days of NRC approval of this amendment request.

Change to Commitment: This commitment was closed and archived.

Justification:

The TRM, TR 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," and associated TR Bases are revised consistent with the TS changes approved by Amendment No.

157. The NRC concluded that hydrogen monitoring equipment requirements no longer meet any of the four criteria in 10 CFR 50.36(c)(2)(ii) for retention in the TS's, and therefore may be relocated to other licensee-controlled documents. Document Revision Request (DRR) No. 05-0708. Implemented 04/20/2005.

Commitment No. RCMS 1996-114 from Enforcement Conference, dated 05/10/1996 Commitment

Description:

The use of an air bubbler and frazil ice detection system will be made a permanent part of the winterization procedure.

Change to Commitment: This commitment was closed and archived.

Justification: This commitment was written in response to NOV EA-96-124. Letter WM 96-0081, "Response to Enforcement Action EA-96-124" states the air bubbler would be part of an immediate short term corrective action.

The air bubblers were to be part of an additional compensatory enhancement to prevent ice blockage, until a permanent design solution could be implemented. A modification has been implemented to prevent frazil ice formation. The current configuration does not allow for the air bubbler to be moved into position to be used.

Attachment II WO 15-0005 Page 1 of 11 Attachment II to WO 15-0005 USAR Changes Processed Since Revision 27

Attachment II WO 15-0005 Page 2 of 11 USAR Change Request Description 14-002 REVISE THE USAR TO REFLECT CALCULATION DA-26, REV 1, FLOODING OF THE CONDENSER PIT DUE TO FAILURE OF CIRCULATING WATER SYSTEM EXPANSION JOINT. FLOODING OF THE CONDENSER PIT DUE TO FAILURE DESCRIBED IN THE USAR, BUT THE ANALYSIS WAS NOT FORMALLY CAPTURED ON A CALCULATION.

Page: 3B-15 Page: 3B-16 Page: 3B-17 14-003 REVISE THE USAR TO SHOW VALVE V-302 AS A GLOBE VALVE AND NOT A GATE VALVE ON SHEET 55 OF FIGURE 6.2.4-1. DRAWINGS M-12BM01 AND M-13BM03 SHOW V-302 AS A GLOBE VALVE.

Figure: 6.2.4-1 Sheet: 55 14-004 REVISE THE USAR TO CHANGE 1.b ON PAGE 5.4-19 FROM, "DEPRESS THE START BUTTON,"

TO "MOMENTARILY PLACE HANDSWITCH BGHS0026, RSC M/U CTRL, TO RUN." THE CHANGE IS BEING MADE TO MATCH THE USAR TO ACTUAL PLANT DESIGN OF MAIN CONTROL BOARD PANEL RL002 FOR HANDSWITCH BGHS0026.

Page: 15.4-19 14-005 REVISE THE USAR TO CHANGE THE CONTROLLING ISOTOPE FOR RADIATION MONITOR GE-RE-92 FROM KR-85 TO XE-133 IN TABLE 11.5-

3.

ALSO CHANGE THAT THE CLOSURE OF BLOWDOWN ISOLATION VALVE OCCURS ON A HI-HI ALARM AND NOT ON A HIGH ALARM.

Table: 11.5-3 14-006 REVISE THE USAR TO REFLECT THE USE OF SHIELDED CASKS VERSUS SHIELDED DRUMS IN THE FILTER HANDLING SYSTEM.

Page: 11.4-8

Attachment II WO 15-0005 Page 3 of 11 USAR Change Request Description 14-007 REVISE THE USAR TO INCORPORATE CHANGE PACKAGE 12512 THAT REPLACED THE THERMOCOUPLE CORE COOLING MONITOR.

THE UPGRADE INVOLVES REPLACEMENT OF THE EXISTING MICROPROCESSOR-BASED SYSTEM SUPPLIED BY WESTINGHOUSE WITH AN ADVANCED LOGIC SYSTEM SUPPLIED BY WESTINGHOUSE.

Page: 18.2-90 Page: 18.2-84 Page: 18.2-72 Figure: 18.2-12 Page: 18.2-88 Page: 18.2-83 Page: 18.2-87 Page: 18.2-74 Page: 18.2-85 Page: 18.2-73 14-008 REVISE THE USAR TO REFLECT JAMES EDWARDS, II, AS THE NEW MANAGER OPERATIONS AND THE RETIREMENT OF A

SHIFT MANAGER.

Page: 13.1-19 Page: 13.1-16 14-009 REVISE THE USAR TO REFLECT THAT THE RESULTS OF ANALYSIS DEMONSTRATES THAT THE REACTOR VESSEL INLET NOZZLES (INCLUDING THE SAFE-ENDS) AND THE RCS COLD LEG (INLET) PIPING MEET THE ASME CODE REQUIREMENTS FOR DESIGN, NORMAL, EMERGENCY, FAULTED AND UPSET CONDITIONS.

THE ANALYSIS WAS PERFORMED DUE TO REDUCED WALL THICKNESS.

Page: 3.6-40 Page: 3.9(N)-32 Page: 3.6-39 14-010 REVISE THE USAR TO REFLECT CORRECT FLOW VALUES FOR THE AUXILIARY FEEDWATER PUMP COOLERS, THE FUEL POOL COOLING PUMP ROOM COOLERS, THE CONTROL ROOM AIR CONDITIONING UNIT CONDENSERS, AND THE CLASS 1E SWITCHGEAR AIR CONDITIONING CONDENSERS.

Table: 9.2-3 14-011 Sheet: 2 Table: 9.2-3 Sheet: 1 REVISE THE USAR TO CLARIFY THAT THE PENETRATION THERMAL CAPABILITY (TC) CURVE BE INDEPENDENTLY COORDINATED WITH THE FUSE AND BREAKER TC CURVES.

Page: 8.1-12

Attachment II WO 15-0005 Page 4 of 11 USAR Change Request Description 14-012 REVISE THE USAR TO CORRECT THE PRIMARY AND BACKUP CONTAINMENT PENETRATION PROTECTION FOR LOAD CENTER FED CIRCUITS FOR CLASS 1E LOADS.

THE USAR WILL REFLECT THE PRIMARY AND BACKUP PROTECTION IS PROVIDED BY THE LOAD CENTER INDIVIDUAL LOAD BREAKERS AND EITHER A SERIES FUSE OR MOTOR CONTROL CENTER BREAKER INSTEAD OF INDIVIDUAL LOAD CIRCUIT BREAKERS AND ASSOCIATED LOAD CENTER MAIN FEED BREAKERS.

Page: 8.1-10 14-013 REVISE THE USAR TO REFLECT THE ADDITION OF VENT VALVE EJV-218 AS A CONTAINMENT ISOLATION VALVE.

Figure: 6.2.4-1 Sheet: 17 14-014 REVISE THE USAR TO REFLECT THE INSTALLATION OF NEW HIGH POINT VENT VALVES. CONTAINMENT PENETRATIONS 14 AND 15 ARE AFFECTED BY THE PIPING CHANGES.

Figure: 6.2.4-1 Sheet: 15 Figure: 6.2.4-1 Sheet: 14 14-015 REVISE THE USAR TO REFLECT LICENSE AMENDMENT 208 WHICH REVISES TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT 3.7.10.1 AND 3.7.13.1 TO REDUCE THE REQUIRED RUN TIME FOR PERIODIC OPERATION OF THE CONTROL ROOM PRESSURIZATION SYSTEM FILTER TRAINS AND THE EMERGENCY EXHAUST SYSTEM FILTER TRAINS, WITH HEATERS ON, FROM 10 HOURS TO 15 MINUTES, CONTINUOUS.

Page: 3A-20 Table: 9.4-2 Sheet: 13 14-016 REVISE THE USAR TO REFLECT THE REVISION OF CALCULATION 9461-C-003, WATER SURFACE ELEVATION CALCULATION, TO INCORPORATE CHANGES TO THE SITE DUE TO VEHICLE BARRIER AROUND TRANSFORMERS XNB01/02 AND THE ONSITE FLEX BUILDINGS.

Page: 2.4-13

Attachment II WO 15-0005 Page 5 of 11 USAR Change Request Description 14-017 REVISE THE USAR TO ENHANCE READER COMPREHENSION OF THE MINIMUM CONTAINMENT PRESSURE ANALYSIS FOR EMERGENCY CORE COOLING SYSTEM PERFORMANCE EVALUATION IN USAR SECTION 6.2.1.5. THE REVISION IS ADDING A DESCRIPTION OF THE BASIS OF THE CONTAINMENT PRESSURE MODEL AND TO PROVIDE THE INPUT PARAMETERS USED IN THE DETERMINATION OF THE FAN COOLER HEAT REMOVAL RATE USED IN LARGE BREAK LOSS OF COOLANT ACCIDENT ANALYSIS.

Page: 6.2-41 Table: 6.2.1-65 Page: 6.2-40 14-018 REVISE THE USAR TO REFLECT ORGANIZATIONAL CHANGES.

Page: 13.1-21 Page: 13.1-15 Table: 13.1-1 Figure: 13.1-2 Figure: 13.1-1 Page: 13.1-20 Page: 13.1-8 Page: 13.1-19 Page: 13.1-7 Page: 13.1-16 Sheet: 10 Table: 13.1-1 Figure: 13.1-2b Sheet: 8 14-019 REVISE THE USAR TO REFLECT DEMOLITION OF THE CHEMICAL ADDITION BUILDING NEAR THE ESSENTIAL SERVICE WATER (ESW)

PUMPHOUSE IN SUPPORT OF THE BELOW GROUND ESW PIPE REPLACEMENT PROJECT.

Page: 2.0-xxi Table: 1.6-3 14-020 v

Page: 1.2-6 Sheet: 3 REVISE THE USAR TO REFLECT USAR SECTION 3.11(B) BEING INCORPORATED BY REFERENCE AND REMOVED FROM THE USAR.

SECTION 3.11(B)

INFORMATION IS BEING DOCUMENTED IN EQUIPMENT QUALIFICATON

SUMMARY

DOCUMENT-I (EQSD),

SECTIONS I AND II, AND EQSD-II, ATTACHMENTS A - C. UPDATES TO EQSD DOCUMENTS ARE CONTROLLED THROUGH THE DESIGN CHANGE PROCESS.

Page: 3.11(B)-2 Page: 1.6-1

Attachment II WO 15-0005 Page 6 of 11 USAR Change Request Table: 3.11(B)-3 S

Table: 3.11(B)-3 S

Table: 3.11(B)-1 S

Table: 3.11(B)-3 S

Table: 3.11(B)-5 S

Table: 3.11(B)-10 S

Table: 1.6-4 S

Table: 3.11(B)-1 S

Table: 3.11(B)-2 S

Table: 3.11(B)-3 S

Table: 3.11(B)-8 S

Table: 3.11(B)-3 S

Description

heet: 22

heet: 11

heet: 13 heet: 15 heet: 17 heet: 19 heet: 21

heet: 23

heet: 25 heet: 27

heet: 29 heet: 31

heet: 33 heet: 6

heet: 1

heet: 1

heet: 1

heet: 2

heet: 3

heet: 5

heet: 2

heet: 4

heet: 6

heet: 3

heet: 5 heet: 7

heet: 75 heet: 64

heet: 66

heet: 68 heet: 70

heet: 72

heet: 74

heet: 76

heet: 78 heet: 80

heet: 82

heet: NOTES

heet: 3 heet: 49

heet: 37

heet: 39

heet: 41

heet: 43

heet: 45

heet: 62 Table:

Table:

3.11(B)-1 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11(B)-3 3.11 (B)-3 3.11(B)-3 3.11(B)-3 3.11 (B)-2 3.11 (B)-4 3.11(B)-8 1.6-4 3.11(B)-1 3.11(B)-3 3.11(B)-3 3.11(B)-2 3.11 (B)-2 3.11(B)-3 3.11 (B)-3 3.11 (B)-3 3.11(B)-1 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11(B)-3 3.11 (B)-3 3.11 (B)-3 3.11(B)-3 3.11 (B)-3 3.11 (B)-3 3.11(B)-8 3.11 (B)-3 3.11 (B)-8 3.11 (B)-3 3.11(B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 3.11 (B)-3 Sheet:

Sheet:

1 12 14 16 18 9

8 24 26 28 30 32 20 1

4 1

1 2

10 36 3

5 2

4 6

4 63 65 67 69 71 34 60 77 79 81 83 2

73 4

38 40 42 44 46 48

Attachment II WO 15-0005 Page 7 of 11 USAR Change Request Description Table: 3.11(B)-3 Table: 3.11(B)-3 Table: 3.11(B)-3 Table: 3.11(B)-3 Table: 3.11 (B)-3 Table: 3.11(B)-3 Table: 3.11(B)-3 Table: 3.11(B)-2 Table: 3.11(B)-4 Table: 3.11(B)-8 Figure: 3.11 (B)-12 Figure: 3.11 (B)-23 Figure: 3.11 (B)-21 Figure: 3.11 (B)-1 9 Figure: 3.11 (B)-1 7 Figure: 3.11(B)-15 Figure: 3.11 (B)-I 3 Figure: 3.11 (B)-I 1 Figure: 3.11 (B)-9 Figure: 3.11(B)-7 Figure: 3.11(B)-5 Figure: 3.11 (B)-3 Figure: 3.11 (B)-14 Figure: 3.11 (B)-48 Figure: 3.11 (B)-47 Figure: 3.11 (B)-46 Figure: 3.11 (B)-44 Figure: 3.11 (B)-42 Figure: 3.11 (B)-25 Figure: 3.11 (B)-26 Figure: 3.11 (B)-36 Figure: 3.11 (B)-34 Figure: 3.11(B)-32 Figure: 3.11 (B)-30 Figure: 3.11 (B)-28 Figure: 3.11 (B)-40 Sheet: 61 Sheet: 51 Sheet: 53 Sheet: 55 Sheet: 57 Sheet: 59 Sheet: 47 Table:

Table:

3.11(B)-3 3.11(B)-3 3.11(B)-3 3.11(B)-3 3.11(B)-3 3.11(B)-3 3.11(B)-1 3.11 (B)-3 3.11(B)-5 3.11(B)-10 Sheet: 50 Sheet: 52 Sheet: 54 Sheet: 56 Sheet: 58 Sheet: 35 Figure: 3.11 (B)-24 Figure: 3.11 (B)-22 Figure: 3.11 (B)-20 Figure: 3.11 (B)-1 8 Figure: 3.11(B)-1 6 Figure: 3.11 (B)-I Figure: 3.11 (B)-27 Figure: 3.11(B)-1 0 Figure: 3.11 (B)-8 Figure: 3.11(B)-6 Figure: 3.11 (B)-4 Figure: 3.11 (B)-2 Figure: 3.11 (B)-38 Figure: 3.11 (B)-49 Figure: 3.11(B)

Figure: 3.11 (B)-45 Figure: 3.11 (B)-43 Figure: 3.11 (B)-41 Figure: 3.11 (B)-39 Figure: 3.11 (B)-37 Figure: 3.11 (B)-35 Figure: 3.11 (B)-33 Figure: 3.11 (B)-31 Figure: 3.11 (B)-29 Figure: 3.11 (B)-7A Figure: 3.11 (B)-9A 14-021 REVISE THE USAR TO REFLECT THE ADDITION OF A NEW CATHODIC PROTECTION BUIDLING NEAR THE FIRING RANGE TO PROTECT THE NEW ESSENTIAL SERVICE WATER PIPELINE ON THE LIST OF PRINCIPLE STRUCTURES.

Page: 1.2-6 Page: 1.2-7

Attachment II WO 15-0005 Page 8 of 11 USAR Change Request Description 14-022 REVISE THE USAR TO REFLECT THE INSTALLATION OF AN ALTERNATE JOCKEY PUMP TO PROVIDE PRESSURE MAINTENANCE FOR THE FIRE PROTECTION WATER SYSTEM.

Page: 9.5-7 Page:

9.5-5 Table: 9.5A-1 Table: 9.5A-1 Sheet: 45 Sheet: 44 14-023 Page:

Page:

Table:

REVISE THE USAR TO REFLECT THE REPLACEMENT AND REDESIGN OF BELOW GROUND ESSENTIAL SERVICE WATER PIPING.

3.0-xxxv 2.0-xxxiii 3.0-xxxiv 2.0-xxvii 2.5-255 2.4-74 2.5-70 2.5-202 3.7(S)-3 3C-2 2.5-201 3.8-70 9.4-85 3.5-13 2.5-62 2.5-222 9.4-88 2.5-246 2.4-16 2.5-37 2.5-67A 3.5-3 9.2-5 2.5-32 2.5-54A 3.4-1 3.7(S)-2 2.5-36 Page:

Page:

2.0-xxx 2.0-xxxii 2.0-xxxvi 2.0-xxvi 2.5-224 2.5-59 2.4-75 2.5-259 2.5-117 3.8-64 3.5-11 3.8-63 3C-10 3.8-67 9.2-5 2.5-225 2.5-236 9.2-7 Page:

Page:

2.0-xxxix 2.0-xxxi 2.0-xxxvii 3.0-xxxviii 2.0-xxiv 2.5-61 2.5-200 2.5-220 2.5-258 3.8-65 3.8-60 3.8-75 9.2-32 2.5-235 2.5-352 3.5-12 2.5-239 9.2-11 Page:

Page:

2.0-xxxviii 2.0-xxxv 2.0-xxxiv 3.0-xxiv 2.5-232 2.5-69 241-2 3.8-69 2.5-199 3.8-76 9.2-9 2.5-233 3C-9 241-1 2.5-221 2.5-234 2.5-245 3.4-1 Sheet: 2 Sheet:

Sheet:

2 1

3 Table: 2.5-36 Table: 2.5-37 Table: 3.3-1 Table: 2.5-36 Table: 3.7(S)-i Table: 2.5-54A Table: 3.2-1 Table: 3.4-2 Table: 3C-1 Table:2.5-37 Sheet: 3 Sheet: 3 Sheet: 2 Sheet: 2 Sheet: 21 Sheet: 2 Sheet: 1 Figure: 2.5-36qqqq Figure: 2.5-36jjjj Figure: 2.5-361111 Figure: 2.5-36nnnn 1-2 1-3 1-3 1-3 Figure:2.5-36iiii Figure:2.5-36kkkk Figure:2.5-36mmmm Figure:2.5-30 Sheet:

Sheet:

1-3 1-3 1-4

Attachment II WO 15-0005 Page 9 of 11 USAR Change Request Description Figure: 2.5-36pppp Figure: 2.5-36rrrr Figure: 2.5-36tttt Figure: 2.5-36mmm Figure: 2.5-36vvvv Figure: 2.5-36yyy Figure: 2.5-36nnn Figure: 2.5-36ppp Figure: 2.5-36rrr Figure: 2.5-36hhhh Figure: 2.5-36gggg Figure: 2.5-36aaaa Figure: 2.5-36cccc Figure: 2.5-36eeee Figure: 2.5-36www Figure: 2.5-36wwww Figure: 3.8-135 Figure: 3.8-136 Figure: 3.8-138 Figure: 3.5-1 Figure: 3.8-142 Figure: 3.8-144 Figure: 3C-4 Figure: 2.5-105 Figure: 2.5-105w Figure: 2.5-51 Figure: 2.5-62d Figure: 2.5-36vvv Figure: 3.8-132 Figure: 2.5-36zzzz Figure: 2.5-105y Figure: 2.5-36sss Figure: 2.5-107a Figure: 2.5-105r Sheet: 1-2 Sheet: 1-3 Sheet: 1-2 Sheet: 1-2 Sheet: 1-3 Sheet: 1-2 Sheet: 1-3 Sheet: 1-3 Sheet: 1-3 Sheet: 1-3 Sheet: 1-3 Sheet:

Sheet:

1-3 1-3 1-3 Figure: 2.5-36ffff Figure: 2.5-36ssss Figure: 2.5-36uuuu Figure: 2.5-36yyyy Figure: 2.5-36oooo Figure: 2.4-55 Figure: 2.5-36ooo Figure: 2.5-36qqq Figure: 2.5-36ttt Figure: 2.5-36xxx Figure: 2.5-36zzz Figure: 2.5-36bbbb Figure: 2.5-36dddd Figure: 2.5-47 Figure: 2.5-107b Figure: 3.8-134 Figure: 3.8-135a Figure: 3.8-137 Figure: 2.5-108 Figure: 2.5-36uuu Figure: 3.8-143 Figure: 3.8-145 Figure: 2.5-98 Figure: 3.8-139 Figure: 2.5-36xxxx Figure: 2.5-62c Figure: 2.5-62e Figure: 2.5-105j Figure: 2.5-105v Figure: 2.5-105x Figure: 2.5-105z Figure: 2.5-118 Figure: 2.5-114 Figure: 1.2-43 Sheet:

Sheet:

1-3 1-2 1-2 1-2 1-2 1-3 1-3 1-3 1-3 1

Sheet: 1-2 Sheet: 1-3 Sheet: 1-3 Sheet: 1-3 Sheet: 1-2 Sheet: 1-2 Sheet: 1-3 Sheet: 1-5 Sheet: 1-2 Sheet: 1-2 Sheet:

1

Attachment II WO 15-0005 Page 10 of 11 USAR Change Request Description 14-024 REVISE THE USAR TO REFLECT A CHANGE IN THE MAIN GENERATOR NAMEPLATE AS A RESULT OF THE GENERATOR REWIND.

Page: 10.2-5 Figure: 10.1-3 Figure: 10.1-2 14-025 REVISE THE USAR TO REFLECT EDITORIAL CORRECTION.

INCLUDES GRAMMATICAL ERRORS AND THE INCLUSION THIS OF PREVIOUSLY APPROVED CHANGES THAT INCORPORATED.

WERE NOT CORRECTLY Page:

Page:

Table:

14-026 2.0-xix 3.0-xi 3.0-vii 2.0-xxii 2.0-iv 1.0-v 9.0-vii 15.0-v 11.0-vi 9.0-xv 3.0-xxiv 6.0-xxi 6.0-i 3.5-13 Page:

Page:

3.0-xxii 3.0-xix 3.0-iii 3.0-xxxiv 2.0-iii 1.0-iv 2.0-xxxiv 13.0-iv 11.0-ii 9.0-viii 8.0-iii 6.0-xix 18.0-v 10.4-11 Page:

Page:

3.0-xvii 3.0-ix 3.0-ii 2.0-xvii 2.0-ii 1.0-i 9.0-xi 13.0-iii 10.0-vii 3.0-xxiii 8.0-i 6.0-xviii 3.0-xxxv Page:

Page:

3.0-xvi 3.0-xviii 10.0-iii 2.0-v 1.0-vii 2.0-xxiv 18.0-iii 13.0-i 10.0-i 9.0-iv 7.0-ix 6.0-ix 2.5-224 11.5-3 11.5-1 7.4-1 Table:

11.5-2 Table:

11.5-1 Sheet: 1 Table: 3.6-3 Sheet: 24 Sheet:

2 Sheet:

2 REVISE THE USAR TO REFLECT C.

D.

HAWES AS THE SUPERINTENDENT OPERATIONS SUPPORT (TRAINING).

Page: 13.1-19 Page: 13.1-17 14-027 REVISE THE USAR TO CHANGE THE VACUUM FLOW RATE ON GERE092 FROM 2.6 TO 3.0 SCFM.

Table: 11.5-3

Attachment II WO 15-0005 Page 11 of 11 USAR Change Request Description 14-028 REVISE THE USAR TO REFLECT THE REPLACEMENT OF THE FIRE ALARM SYSTEM COLOR GRAPHICS TOUCH SCREEN ANNUNCIATOR SYSTEM WITH A NEW STATE-OF-THE-ART SYSTEM.

Page: 9.5-16 14-029 THE USAR IS BEING REVISED TO REFLECT THE COMPLETION OF THE NEW EMERGENCY OFFSITE FACILITY AND ALTERNATE TECHNICAL SUPPORT CENTER FACILITY.

THE NEW FACILITY IS REQUIRED DUE TO AMENDED EMERGENCY PLANNING REGULATIONS.

Page: 18.3-16 Page: 18.3-6 Page: 18.3-1 Page: 18.0-1 Page: 18.0-iii Page: 18.4-1 Table: 1.3-4 Sheet: 21 Figure: 2.1-6 14-030 REVISE THE USAR TO REFLECT THE INSTALLATION OF A NEW VOICE OVER INTERNET PROTOCOL (VOIP) PHONE TECHNOLOGY THAT REPLACED THE PRIVATE BRANCH EXCHANGE (PBX) TELEPHONE SYSTEM.

Page: 9.5-40 15-001 REVISE THE USAR TO REFLECT REVISION TO CALCULATION EN-03-W-002 WHICH RECALCULATED THE CONTAINMENT POST-LOCA SUMP pH VERSUS TIME.

Figure: 6.5-5 15-002 REVISE THE USAR TO REFLECT THE ADDITION OF FOUR 345 kV TRANSMISSION LINES.

ONE FROM THE RENO SUBSTATION TO SUMMIT SUBSTATION, ONE FROM ROSE HILL SUBSTATION TO THE SOONER SUBSTATION, AND TWO FROM WICHITA TO THISTLE.

Page: 8.2-3 Figure: 8.2-5 Figure: 8.2-1

Attachment III to WO 15-0005 Page 1 of 3 Attachment III to WO 15-0005 Revisions 55 through 58 to the Technical Requirements Manual

Attachment III to WO 15-0005 Page 2 of 3 REVISIONS TO THE TECHNICAL REQUIREMENTS MANUAL (TRM) 1 Technical Requirement (TR) 3.3.17, "Reactivity Control and Power Distribution Alarms,"

(page 3.3-28) was revised to correct the header associated with TR 3.3.17. The header for TR 3.3.17 was identified as Explosive Gas Monitoring Instrumentation, TR 3.3.16. The header was revised to Reactivity Control and Power Distribution Alarms, TR 3.3.17.

2.

TR Bases 3.1.9, "Boration Injection System - Operating," and TR Bases 3.1.10, "Boration Injections System - Shutdown," pages B 3.1.9-6 and B 3.1.10-4 were revised to delete the sentence, "All of the boron solution volume of the BATs is considered to be usable." A review of WCRE-03, "Wolf Creek Tank Document," identified that the total volume of one Boric Acid Tank (BAT) as 27,755 gallons. Updated Safety Analysis Report (USAR) Table 9.3-9 and document 10466-M-10BG, "System Description Chemical and Volume Control System," specify the usable capacity of a BAT as 24,000 gallons.

Based on this information, the statements in the TRM do not reflect the information in the USAR and system description documents. This change revises the TRM to be consistent with the system description documents and the USAR.

3.

Technical Surveillance Requirement (TSR) 3.7.20.2 (Snubber Functional Tests) and associated TR Bases were revised to change the TSR Frequency to be consistent with Subsection ISTD of the 2009 edition of the ASME Operation and Maintenance (ASME OM-2009) Code.

The changes to TSR 3.7.20.2 are consistent with ISTD-5240, "Test Frequency," which states: Tests of snubbers from the facility shall be performed every fuel cycle. Snubber testing may begin no earlier than 60 days before a scheduled refueling outage." Specifically the Note to TSR 3.7.20.2 was revised from "This surveillance shall not be performed in MODES 1 and 2." to "This surveillance shall begin no earlier than 60 days before a scheduled refueling outage."

The TSR Frequency is revised from "18 months" to "Once each refueling".

4.

Technical Requirement Manual (TRM) page 3.3-30 is revised to correct the header associated with TR 3.3.17. The header for TR 3.3.17 is currently identified as Primary to Secondary LEAKAGE Detection Instrumentation, TR 3.3.18.

The header should be Reactivity Control and Power Distribution Alarms, TR 3.3.17.

5.

TR 3.7.7, "Component Cooling Water (CCW) System Instrumentation," and associated TR Bases were revised to remove from TR 3.7.7 the requirement for the Radwaste Building loop high flow instrumentation to be FUNCTIONAL. Design Change Package (DCP) 13540, Rev. 0, provides a modification to restrict flow to the non-safety related CCW piping from the safety related portion of CCW in the event of a break in the non-safety related CCW piping. As the modification negates the need for the automatic CCW to Radwaste high flow trips, the requirements in TR 3.7.7 to maintain the loop high flow instrumentation FUNCTIONAL are not necessary.

6.

Note (c) to Table TR 5.2.1-1, "Minimum Shift Crew Composition," is revised from "Individual may be a SRO." to "Individual may be a RO." This revision is to correct an error that was made in Revision 51 of the TRM. Revision 51 to the TRM revised TR 5.2.1, "Unit Staff," and Table TR 5.2.1-1, to identify the minimum staffing required by Technical

Attachment III to WO 15-0005 Page 3 of 3 Specification 5.2.2 and the minimum staffing necessary to meet plant operational requirements and radiological emergency response staffing requirements.

7.

The Bases for TSR 3.7.7.2 Frequency were revised for consistency with Technical Specification Surveillance Requirement (SR) 3.7.7.2. The revision allows individual valves to be tested during power operation under appropriate administrative controls.

TSR 3.7.7.2 requires a CHANNEL CALIBRATION that includes verifying valves EGHV0069A/B and EGHV0070A/B close from surge tank level instrumentation. Prior to conversion to the Improved TS (Amendment No. 123 - 1999), TS Surveillance Requirement 4.7.3c. stated:

"At least once per 18 months during shutdown, by performing a CHANNEL CALIBRATION of the surge tank level and flow instrumentation which provide automatic isolation of the non-nuclear safety-related portion of the system." The TSR Bases requirement to only perform the TSR during shutdown conditions is overly conservative and the performance of the TSR at power will not impact plant operation. Revising the TSR 3.7.7.2 Bases to be consistent with TS SR 3.7.7.2 provides for consistency of testing requirements.

Enclosure I to WO 15-0005 Page 1 of 2 Enclosure I to WO 15-0005 CD-ROM containing Updated Safety Analysis Report, Revision 28

Enclosure I to WO 15-0005 Page 2 of 2 Subject Enclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated Safety Analysis Report (WCGS USAR), Revision 28. In accordance with 10 CFR 2.390, WCGS USAR Chapters 2, 3, 8, 9, and 12 contain sensitive unclassified information and therefore warrant withholding.

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

The CD-ROM labeled "Wolf Creek Generating Station Updated Safety Analysis Report, Rev.28" contains the following files:

001_USAR.pdf 002_USARC01.pdf 003_USARC02.0.pdf 004_USARC02 Figures.pdf 005 USARC03.pdf 006 USARC04.pdf 007 USARC05.pdf 008 USARC06.pdf 009 USARC07.pdf 010 USARC08.pdf 011 USARC09.pdf 012 USARC10.pdf 013 USARC11.pdf 014 USARC12.pdf 015 USARC13.pdf 016 USARC14.pdf 017 USARC15.pdf 018 USARC16.pdf 019 USARC17.pdf 020 USARC18.pdf 021_USARNRCQ.pdf 022_USAR Rev. 28-loep.pdf 238 KB, sensitive unclassified information 774 KB, publicly available 34.7 MB, sensitive unclassified information 35.4 MB, sensitive unclassified information 15.4 MB, sensitive unclassified information 2.24 MB, publicly available 2.36 MB, publicly available 10.5 MB, publicly available 1.82 MB, publicly available 2.14 MB, sensitive unclassified information 7.0 MB, sensitive unclassified information 1.4 MB, publicly available 941 KB, publicly available 776 KB, sensitive unclassified information 857 KB, publicly available 338 KB, publicly available 4.96 MB, publicly available 56 KB, publicly available 64 KB, publicly available 1.15 MB, publicly available 348 KB, publicly available 405 KB, publicly available

Enclosure II to WO 15-0005 Page 1 of 2 Enclosure II to WO 15-0005 CD-ROM containing Updated Safety Analysis Report Controlled Figure Drawings

Enclosure II to WO 15-0005 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.

In accordance with 10 CFR 2.390, this enclosure is considered sensitive unclassified information and therefore warrants withholding.

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

The CD-ROM labeled "WCGS Updated Safety Analysis Report, Rev.28 Controlled Figure Drawings Only" contains the following files:

001_Chapter 1.pdf 002_Chapter 2.pdf 003_Chapter 5.pdf 004_Chapter 6.pdf 005 Chapter 7.pdf 006_Chapter 8.pdf 007_Chapter 9.pdf 008_Chapter 10.pdf 009_Chapter 11.pdf 010_Chapter 12.pdf 011_Chapter 18.pdf 012_Index Removed Figure List.pdf 9.15 MB, sensitive unclassified information 2.34 MB, sensitive unclassified information 1.16 MB, sensitive unclassified information 2.38 MB, sensitive unclassified information 932 KB, sensitive unclassified information 1.28 MB, sensitive unclassified information 22.6 MB, sensitive unclassified information 6.77 MB, sensitive unclassified information 4.10 MB, sensitive unclassified information 1.16 MB, sensitive unclassified information 227 KB, sensitive unclassified information 89 KB, sensitive unclassified information

Enclosure III to WO 15-0005 Page 1 of 2 Enclosure III to WO 15-0005 CD-ROM containing Updated Safety Analysis Report Fire Hazards Analysis and Quality Program Manual

Enclosure III to WO 15-0005 Page 2 of 2 Subject Enclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated Safety Analysis Report Fire Hazards Analysis and Wolf Creek Quality Program Manual (WCQPM),

both of which are considered incorporated by reference into the WCGS USAR. In accordance with 10 CFR 2.390, the WCGS USAR Fire Hazards Analysis is considered sensitive unclassified information and therefore warrants withholding.

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

The CD-ROM labeled "WCGS USAR Fire Hazards Analysis & Quality Program Manual" contains the following files:

001_WCQPM Rev 9.pdf 002_E-1 F9900 Rev 9.pdf 003_E-1 F9905 Rev 6.pdf 004_E-1 F9910 Rev 12.pdf 005_XX-E-013 Rev 3.pdf 006_XX-E-013 Rev 3_CN003.pdf 007_XX-E-013 Rev 3_CN004.pdf 008_XX-E-013 Rev 3_CN005.pdf 009_XX-E-013 Rev 3_CN007.pdf 010_M-663-00017A W05 1 to B1-98.pd 011_M-663-00017A W05 Bl-99 to B2-40.pdf 012_M-663-00017A W05 B2-41 to B6-2.pdf 013_M-663-00017A W05 B6-3 to B7-79.pdf 014_M-663-00017A W05 B7-80 to B8-147.pdf 015_M-663-00017A W05 B8-148 to B13-25.pdf 016_M-663-00017A W05 B13-26 to G1A-63.pdf 017_M-663-00017A W05 G1A-64 to G1A-123.pdf 018_M-663-00017A W05 G1A-124 to G2A-3.pdf 019_M-663-00017A W05 G2B-1 to G2B79.pdf 020_M-663-00017A W05 Att G3 to G3D-26.pdf 021_M-663-00017A W05 G3D-27 to G4D-19.pdf 022_M-663-00017A W05 Att G5 to Att H.pdf 5.13 MB, publicly available 5.30 MB, 8.33 MB, 17.0 MB, 1.58 MB, 340 KB, 594 KB, 288 KB, 358 KB, 23.7 MB, 31.7 MB, 49.5 MB, 28.3 MB, 45.3 MB, 33.9 MB, 2.7 MB, 17.0 MB, 15.7 MB, 18.8 MB, 22.0 MB, 20.6 MB, 20.0 MB, sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified sensitive unclassified information information information information information information information information information information information information information information information information information information information information information

Enclosure IV to WO 15-0005 Page 1 of 2 Enclosure IV to WO 15-0005 CD-ROM Containing EQSD-I, EQ Summary Document Section I Program Description, and EQSD-II, EQ Master List Section II

Enclosure IV to WO 15-0005 Page 2 of 2 Subject Enclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated Safety Analysis Report EQSD-I, EQ Summary Document Section I Program Description, and EQSD-II, EQ Master List Section II, both of which are considered incorporated by reference into the WCGS USAR. In accordance with 10 CFR 2.390, the WCGS EQSD-I, EQ Summary Document Section I Program Description, and EQSD-II, EQ Master List Section II, is considered sensitive unclassified information and therefore warrants withholding.

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

The CD-ROM labeled "EQSD-I, EQ Summary Document Section I Program Description, and EQSD-II, EQ Master List Section Ir" contains the following files:

001_EQSD-l Rev 7.pdf 002_EQSD-II Rev 27.pdf 003_EQSD-ll-027-CN01.pdf 11.3 MB, sensitive unclassified information 1.26 KB, sensitive unclassified information 187 KB, sensitive unclassified information

Enclosure V to WO 15-0005 Page 1 of 1 Enclosure V to WO 15-0005 Technical Requirements Manual Replacement Pages and List of Effective Pages (23 Pages)

Reactivity Control and Power Distribution Alarms TR 3.3.17 3.3 INSTRUMENTATION 3.3.17 Reactivity Control and Power Distribution Alarms TR 3.3.17 The following annunciator alarms shall be FUNCTIONAL:

a.

AXIAL FLUX DIFFERENCE (AFD);

b.

Rod Insertion Limit;

c.

Rod Position Deviation; and

d.

QUADRANT POWER TILT RATIO (QPTR).

APPLICABILITY:

According to Table TR 3.3.17-1.

ACTIONS Separate Condition entry is allowed for each alarm.

CONDITION REQUIRED ACTION COMPLETION TIME A.

AFD Alarm is A.1 Perform Technical Once per hour nonfunctional.

Specification Surveillance Requirement (SR) 3.2.3.1.

B.

Rod Insertion Limit Alarm B.1 Perform Technical Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months nonfunctional.

Specification SR 3.1.6.2.

C.

Rod Position Deviation C.1 Perform Technical Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Alarm nonfunctional.

Specification SR 3.1.4.1.

(continued)

Wolf Creek - Unit 1 TRM3R 3.3-28 Revision 55

Reactivity Control and Power Distribution Alarms TR 3.3.17 Table TR 3.3.17-1 (page 1 of 1)

Reactivity Control and Power Distribution Alarms APPLICABLE MODES OR OTHER ANNUCIATOR SPECIFIED FUNCTION WINDOW CONDITIONS A.

AXIAL FLUX DIFFERENCE 00-079D 1 (b)

Alarm B.

Rod Insertion Limit Alarm 00-081C or 00-081D 1, 2(a)

C.

Rod Position Deviation Alarm 00-079C 1, 2 D.

QUADRANT POWER TILT (00-078B and 00-078C) 1(c)

RATIO Alarm or 00-079C (a)

(b)

(c)

With kff _> 1.0.

With THERMAL POWER > 50% RTP.

Wolf Creek - Unit 1 TRM 3.3-30 Revision 56

CCW System Instrumentation TR 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System Instrumentation TR 3.7.7 The required CCW surge tank level instrumentation shall be FUNCTIONAL for each CCW train.

APPLICABILITY:

MODES 1, 2, 3, and 4 when non-essential loads are supplied by associated CCW train.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Restore required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channel(s) nonfunctional.

channel(s) to FUNCTIONAL status.

B.

Required Action and B.1 Initiate Condition Report.

Immediately associated Completion Time not met.

Wolf Creek - Unit 1 - TRM 3.7-1 Revision 57

Snubbers TR 3.7.20 TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY TSR 3.7.20.2 NOTE -.-.--............-----------

This surveillance shall begin no earlier than 60 days before a scheduled refueling outage.

Perform a functional test on a representative sample Once each of each type of snubber in accordance with Table TR refueling 3.7.20-4.

TSR 3.7.20.3 Verify that the service life of mechanical snubbers is In accordance with not exceeded.

Snubber Service Life Program TSR 3.7.20.4 Perform an inspection of all required snubbers Within 6 months attached to sections of systems that have following the event experienced an unexpected potentially damaging transient in accordance with Table TR 3.7.20-1.

Wolf Creek - Unit I - TRM 3.7-11 Revision 56

Organization TR 5.2 Table TR 5.2.1-1 (page 1 of 1)

Minimum Shift Crew Composition NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION Technical Specification Requirements Plant Operational Requirements POSITION MODE 1, 2, 3, or 4 MODE 5 or 6 At All Times SM 1

1 (b) 1 CRS 1

None 1

RO 2

1 2

NSO 2

1 5 (c)(d)

STA 1 (a)

None 1 (e)

CHM None None 2

HP 1

1 3

ENS Communicator None None 1

Offsite Communicator None None 1

SM CRS RO NSO STA CHM HP Shift Manager with a Senior Operator license on Unit 1 Control Room Supervisor with a Senior Operator license on Unit 1 Individual with an Operator license on Unit 1 Nuclear Station Operator Shift Technical Advisor (Shift Engineer)

Chemistry Personnel Health Physics Personnel (a)

This position shall be manned in MODES 1, 2, 3, and 4 unless the Shift Manager or the individual with a Senior Operator license meets the qualifications as required by Technical Specification 5.2.2f.

(b)

One individual with a Senior Operator license, either Shift Manager or Control Room Supervisor.

(c)

Individual may be a RO.

(d)

One individual is designated to perform OFN KC-016/OFN KC-017, Aft. E.

(e)

This position shall be manned in MODES 1, 2, 3, and 4. In MODES 5 and 6, this position is not required to be filled by an individual qualified as a STA.

Wolf Creek - Unit 1 - TRM 5.0-2 Revision 57

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TAB - Title Page TRM Title Page TAB - Table of Contents i

43 DRR 10-3738 12/28/10 ii 35 DRR 08-0727 8/28/08 iii 54 DRR 13-2529 10/25/13 TAB - 1.0 USE AND APPLICATION 1.0-1 41 DRR 10-1702 10/1/10 1.0-2 41 DRR 10-1702 10/1/10 TAB - 3.0 APPLICABILTY 3.0-1 41 DRR 10-1702 10/1/10 3.0-2 41 DRR 10-1702 10/1/10 3.0-3 41 DRR 10-1702 10/1/10 3.0-4 20 DRR 04-1410 10/7/04 TAB - 3.1 REACTIVITY CONTROL SYSTEMS 3.1-1 41 DRR 10-1702 10/1/10 3.1-2 3

DRR 99-1581 12/18/99 3.1-3 34 DRR 08-0256 3/11/08 3.1-4 34 DRR 08-256 3/11/08 3.1-5 41 DRR 10-1702 10/1/10 3.1-6 37 DRR 09-0287 3/20/09 3.1-7 41 DRR 10-1702 10/1/10 3.1-8 41 DRR 10-1702 10/1/10 3.1-9 11 DRR 02-0412 4/5/02 3.1.10 48 DRR 12-0266 2/2/12 TAB - 3.3 INSTRUMENTATION 3.3-1 3.3-2 3.3-3 3.3-4 3.3-5 3.3-6 3.3-7 3.3-8 3.3-9 3.3-10 3.3-11 3.3-12 3.3-13 3.3-14 3.3-15 3.3-16 3.3-17 3.3-18 3.3-19 3.3-20 3.3-21 3.3-22 41 41 23 41 41 23 23 43 41 41 39 39 39 49 39 39 41 39 51 51 51 51 DRR 10-1702 DRR 10-1702 DRR 05-0708 DRR 10-1702 DRR 10-1702 DRR 05-0708 DRR 05-0708 DRR 10-3738 DRR 10-1702 DRR 10-1702 DRR 09-1775 DRR 09-1775 DRR 09-1775 DRR 12-0673 DRR 09-1775 DRR 09-1775 DRR 10-1702 DRR 09-1775 DRR 13-0371 DRR 13-0371 DRR 13-0371 DRR 13-0371 10/1/10 10/1/10 4/20/05 10/1/10 10/1/10 4/20/05 4/20/05 12/28/10 10/1/10 10/1/10 10/28/09 10/28/09 10/28/09 4/10/12 10/28/09 10/28/09 10/1/10 10/28/09 2/26/13 2/26/13 2/26/13 2/26/13 Wolf Creek - Unit 1 i

Revision 57

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TAB - 3.3 INSTRUMENTATION (continued) 3.3-23 51 DRR 13-0371 2/26/13 3.3-24 51 DRR 13-0371 2/26/13 3.3-25 51 DRR 13-0371 2/26/13 3.3-26 51 DRR 13-0371 2/26/13 3.3-27 51 DRR 13-0371 2/26/13 3.3-28 55 DRR 14-0344 2/27/14 3.3-29 51 DRR 13-0371 2/26/13 3.3-30 56 DRR 14-1570 7/1/14 3.3-31 51 DRR 13-0371 2/26/13 3.3-32 51 DRR 13-0371 2/26/13 3.3-33 51 DRR 13-0371 2/26/13 3.3-34 51 DRR 13-0371 2/26/13 3.3-35 51 DRR 13-0371 2/26/13 3.3-36 51 DRR 13-0371 2/26/13 3.3-37 51 DRR 13-0371 2/26/13 TAB - 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4-1 37 DRR 09-0287 3/20/09 3.4-2 3

DRR 99-1581 12/18/99 3.4-3 41 DRR 10-1702 10/11/10 3.4-4 41 DRR 10-1702 10/11/10 3.4-5 3

DRR 99-1581 12/18/99 3.4-6 33 DRR 07-1554 9/28/07 3.4-7 33 DRR 07-1554 9/28/07 3.4-8 41 DRR 10-1702 10/1/10 3.4-9 41 DRR 10-1702 10/1/10 3.4-10 35 DRR 08-0729 8/28/08 TAB - 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5-1 41 DRR 10-1702 10/1/10 TAB - 3.6 CONTAINMENT SYSTEMS 3.6-1 17 DRR 04-0452 5/26/04 3.6-2 37 DRR 09-0287 3/20/09 3.6-3 17 DRR 04-0452 5/26/04 TAB - 3.7 PLANT SYSTEMS 3.7-1 3.7-2 3.7-3 3.7-4 3.7-5 3.7-6 3.7-7 3.7-8 3.7-9 3.7-10 3.7-11 3.7-12 57 28 52 41 41 41 26 37 50 50 56 50 DRR 14-1878 DRR 06-1349 DRR 13-0658 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 06-0050 DRR 09-0287 DRR 12-1537 DRR 12-1537 DRR 14-1570 DRR 12-1537 9/30/14 7/24/06 3/28/13 10/1/10 10/1/10 10/1/10 2/28/06 3/20/09 8/30/12 8/30/12 7/1/14 8/30/12 Wolf Creek - Unit 1 ii Revision 57

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TAB - 3.7 PLANT SYSTEMS (continued) 3.7-13 50 DRR 12-1537 8/30/12 3.7-14 50 DRR 12-1537 8/30/12 3.7-15 50 DRR 12-1537 8/30/12 3.7-16 50 DRR 12-1537 8/30/12 3.7-17 50 DRR 12-1537 8/30/12 3.7-18 50 DRR 12-1537 8/30/12 3.7-19 50 DRR 12-1537 8/30/12 3.7-20 50 DRR 12-1537 8/30/12 3.7-21 50 DRR 12-1537 8/30/12 3.7-22 50 DRR 12-1537 8/30/12 3.7-23 50 DRR 12-1537 8/30/12 3.7-24 50 DRR 12-1537 8/30/12 3.7-25 50 DRR 12-1537 8/30/12 3.7-26 50 DRR 12-1537 8/30/12 3.7-27 50 DRR 12-1537 8/30/12 3.7-28 50 DRR 12-1537 8/30/12 3.7-29 50 DRR 12-1537 8/30/12 3.7-30 50 DRR 12-1537 8/30/12 3.7-31 50 DRR 12-1537 8/30/12 3.7-32 50 DRR 12-1537 8/30/12 3.7-33 50 DRR 12-1537 8/30/12 3.7-34 50 DRR 12-1537 8/30/12 3.7-35 50 DRR 12-1537 8/30/12 3.7-36 50 DRR 12-1537 8/30/12 3.7-37 54 DRR 13-2529 10/25/13 3.7-38 54 DRR 13-2529 10/25/13 TAB - 3.8 ELECTRICAL POWER SYSTEMS 3.8-1 47 DRR 11-2404 11/16/11 3.8-2 47 DRR 11-2404 11/16/11 3.8-3 47 DRR 11-2404 11/16/11 3.8-4 47 DRR 11-2404 11/16/11 3.8-5 47 DRR 11-2404 11/16/11 TAB-3.9 REFUELING OPERATIONS 3.9-1 3

DRR 99-1581 12/18/99 3.9-2 41 DRR 10-1702 10/1/10 3.9-3 41 DRR 10-1702 10/1/10 TAB - 3.10 EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING 3.10-1 3

DRR 99-1581 3.10-2 37 DRR 09-0287 3.10-3 37 DRR 09-0287 3.10-4 3

DRR 99-1581 3.10-5 37 DRR 09-0287 3.10-6 3

DRR 99-1581 12/18/99 3/20/09 3/20/09 12/18/99 3/20/09 12/18/99 Wolf Creek - Unit 1 iii Revision 57

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TAB - 5.0 ADMINISTRATIVE CONTROLS 5.0-1 51 DRR 13-0371 2/26/13 5.0-2 57 DRR 14-1878 9/30/14 5.0-3 24 DRR 05-1376 6/28/05 5.0-4 41 DRR 10-1702 10/1/10 5.0-5 17 DRR 04-0452 9/28/05 5.0-6 25 DRR 05-1996 2/16/05 5.0-7 16 DRR 03-1498 11/4/03 Note 1 The page number is listed on the center of the bottom of each page.

Note 2 The revision number is listed in the lower right hand corner of each page. The Revision number will be page specific.

Note 3 The change document will be the document requesting the change. Therefore, the change document should be a DRR number in accordance with AP 26A-002.

Note 4 The date effective or implemented is the date the Technical Requirement pages are to be issued by Document Control.

Wolf Creek - Unit 1 iv Revision 57

Boration Injection System - Operating TR B 3.1.9 BASES TECHNICAL SURVEILLANCE REQUIREMENTS TSR 3.1.9.2 (continued) unusable volume. The combined BAT boron solution volume may be contained in one or both of the BATs. If one BAT meets the minimum boron solution volume requirement, that BAT is the only boron solution source required for the associated boration injection subsystem to be considered FUNCTIONAL. If both BATs are necessary to meet the minimum boron solution volume requirement, both BATs are required to be FUNCTIONAL for the associated boration injection subsystem to be considered FUNCTIONAL.

The 7 day Frequency to verify boron solution volume is appropriate since the RWST and BAT volumes are normally stable and has been shown to be acceptable through operating experience. In addition, the Frequency is consistent with the Technical Specification surveillance Frequency for verifying the RWST boron solution volume.

TSR 3.1.9.3 This TSR requires a verification of the boron solution concentration of the RWST and the required BAT(s) every 7 days. This TSR verifies the boron concentration by sampling, calculation, or administrative means. The minimum boron solution concentration requirements of the RWST and the required BAT(s), along with the boron solution volume requirements, ensure cold shutdown boron weight is available for injection (i.e., SDM equivalent to 1.3% Ak/k at 2000F). The maximum boron solution concentration requirement of the required BAT(s) ensure that the concentration of boric acid in each required BAT is not allowed to precipitate.

The Frequency to verify boron concentration is appropriate since the RWST and BAT boron solution concentration is normally stable and has been shown to be acceptable through operating experience. In addition, the Frequency is consistent with the Technical Specification surveillance Frequency for verifying the RWST boron solution concentration.

TSR 3.1.9.4 Verifying the correct-alignment for each boration injection subsystem manual, power operated, and automatic valve provides assurance that the proper flow paths exist for boration injection subsystem operation. This TSR does not apply to valves that are locked, sealed, or otherwise Wolf Creek - Unit 1 - TRM B 3.1.9-6 Revision 55

Boration Injection System - Shutdown TR B 3.1.10 BASES TECHNICAL SURVEILLANCE REQUIREMENTS TSR 3.1.10.2 This surveillance requires verification every 7 days that the RWST boron solution volume is at least 394,000 gallons or the combined boron solution volume of the BATs is at least 17,658 gallons in MODE 4. The maximum expected boron injection capability requirement value of 17,658 gallons is calculated based on blending the concentrated boric acid solution with reactor makeup water, assuming offsite power, to form the final boron concentration required for the RCS. In MODE 5 or 6, the minimum required boron solution volume of the RWST is 55,416 gallons or the required BAT volume is 2,968 gallons. The minimum boron solution volume, along with the boron solution concentration requirements, ensure cold shutdown boron weight is available for injection (i.e., SDM equivalent to 1.3% Ak/k at 2000F). The boron solution volume limit of the RWST ensures 83,754 gallons are available to inject the required cold shutdown boron weight in MODE 4 and 14,071 gallons are available to inject the required cold shutdown boron weight in MODES 5 and 6. The boron solution volume limits of the RWST include any unusable volume. The combined BAT boron solution volume may be contained in one or both of the BATs. If one BAT meets the minimum boron solution volume requirement, that BAT is the only boron solution source required for the associated boration injection subsystem to be considered FUNCTIONAL.

If both BATs are necessary to meet the minimum boron solution volume requirement, both BATs are required to be FUNCTIONAL for the associated boration injection subsystem to be considered FUNCTIONAL.

The 7 day Frequency to verify boron solution volume is appropriate since the RWST and BAT volumes are normally stable and has been shown to be acceptable through operating experience. In addition, the Frequency is consistent with the Technical Specification surveillance Frequency for verifying the RWST boron solution volume.

TSR 3.1.10.7 Each required RHR suction relief valve shall be demonstrated FUNCTIONAL by verifying its RHR suction isolation valves are open. This Surveillance is only required to be performed if the RHR suction relief valve is being used to meet this TR.

The RHR suction isolation valves are verified to be opened every 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The Frequency is considered adequate in view of other administrative controls such as valve status indications available to the operator in the control room that verify the RHR suction isolation valves are open.

Wolf Creek - Unit 1 - TRM B 3.1.10-4 Revision 55

CCW System Instrumentation TR B 3.7.7 B 3.7 PLANT SYSTEMS TR B 3.7.7 Component Cooling Water (CCW) System Instrumentation BASES BACKGROUND The Component Cooling Water (CCW) System is a closed loop system that provides cooling water to selected Engineered Safety Features (ESF) components. The CCW System also contains another cooling water supply loop, which is common to, but isolable from, both trains. This loop provides a means of heat rejection for other non-essential equipment from various reactor support systems (Ref. 1).

The non-essential CCW System loads which are shed include the Post Accident Sampling System (PASS) Cooling System, Nuclear Sample Cooling System, and the Radwaste Building loads, which supply cooling water to the various evaporators, recombiners, and waste gas compressors. Isolation of the PASS Cooling System is accomplished through the closing of the series isolation supply valves EG HV-72 and EG HV-73 and the closing of the series isolation return valves EG HV-74 and EG HV-75. Isolation of the Nuclear Sample Cooling System and the Radwaste Building loads is accomplished through the closing of the series isolation supply valve EG HV-69A and EG HV-70A and the closing of the series isolation return valves EG HV-69B and EG HV-70B. The primary isolation signal, which isolates the non-essential CCW System loads, is a Safety Injection Signal (SIS).

This TR covers instrumentation associated with level switches EGLSLL0001 and EGLSLL0002 and their instrumentation. This instrumentation provides backup automatic isolation of the non-essential CCW System loads.

CCW System and CCW System actuation instrumentation OPERABILITY requirements regarding the intended support function of safety related systems are specified in Technical Specifications LCO 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation," and LCO 3.7.7, "Component Cooling Water (CCW) System," and associated Bases (Refs. 2 and 3).

APPLICABLE The design basis of the CCW System is for one CCW train to remove SAFETY ANALYSES the heat from components important to mitigating the consequences of a loss-of-coolant-accident (LOCA) or a main steam line break (MSLB) and transfer the heat to the Essential Service Water System.

Wolf Creek - Unit 1 - TRM B 3.7.7-1 Revision 57

CCW System Instrumentation TR B 3.7.7 BASES APPLICABLE The accomplishment of these functions are provided through the SAFETY ANALYSES reduction in non-essential heat load being cooled by the CCW System.

(continued)

Isolation of these loads is accomplished by an SIS. However, no DBA or transient assumes the CCW System Instrumentation associated with this TR to be OPERABLE (Ref. 4).

In the event of a hazard that could compromise the integrity of the non-safety, non-seismic piping to the radwaste service loads, such as a seismically induced pipe break or crack or a non-mechanistic malfunction in the moderate energy piping, no SIS would be generated for the automatic isolation of the non-safety related radwaste service loads (via closure of valves EGHV0069A/B and EGHV0070A/B). For such an event, the low-low level signal from the CCW surge tank level channels (initiated by transmitters EGLT0001 and EGLT0002) will isolate the radwaste service loads.

TR This TR requires that the instrumentation associated with the automatic isolation of the CCW System from non-safety related heat loads are FUNCTIONAL. For the CCW System instrumentation to be considered FUNCTIONAL, the surge tank low level instrumentation must be capable of automatically isolating the Radwaste System, the PASS coolers, and the Nuclear Sample Cooling System loads upon receipt of a surge tank low level signal.

APPLICABILITY The CCW System instrumentation associated with this TR is required to be FUNCTIONAL in MODES 1, 2, 3, and 4 when non-essential loads are being supplied by the associated CCW train since the CCW System is required to perform its safety function in MODES 1, 2, 3, and 4. The CCW instrumentation associated with this TR is not required to be FUNCTIONAL in MODES 1, 2, 3, and 4 when the non-essential loads are isolated from the associated CCW train since the required function is performed.

ACTIONS A.1 This Required Action provides direction to restore the inoperable CCW System instrumentation to FUNCTIONAL status. The Completion Time is considered a reasonable time to repair the equipment and is consistent with the allowable outage time for an inoperable CCW train per Technical Specification 3.7.7.

Wolf Creek - Unit 1 - TRM B 3.7.7-2 Revision 57

CCW System Instrumentation TR B 3.7.7 BASES ACTIONS B..1 (continued)

If the Required Action cannot be performed within the associated Completion Time, Required Action B.1 requires initiation of a Condition Report (CR) immediately. As part of the initiation of the CR, action shall be implemented in a timely manner to place the unit in a safe condition as determined by plant management. The CR should provide an accurate description of the problem, the Required Action and associated Completion Time not complied with. The intent of this Required Action is to utilize the corrective action program to assure prompt attention and adequate management oversight to minimize the additional time the channel is nonfunctional.

TECHNICAL TSR 3.7.7.1 SURVEILLANCE REQUIRMENTS A CHANNEL OPERATIONAL TEST (COT) of the surge tank level instrumentation circuits that provide automatic isolation of the non-safety-related portions of the system assures that the channel components are capable of performing their design functions upon the initiation of a simulated or actual actuation signal. The Frequency of 184 days is reasonable, based on plant-specific operating experience, instrument reliability, and satisfactory performance trend.

TSR 3.7.7.2 A CHANNEL CALIBRATION of surge tank level instrumentation circuits, which provide automatic isolation of the non-safety-related portion of the system, assures that the channels will respond, within the required range and accuracy necessary for the continued FUNCTIONALITY of the circuit.

The CHANNEL CALIBRATION must include all devices up to and including the associated automatic valves to provide complete testing of the required function. The 18 month Frequency is based upon the need to perform this TSR under conditions that apply during a unit outage and the potential for an unplanned transient if the TSR were performed with the reactor at power. However, individual valves may be tested during power operation under appropriate administrative controls, and if an actual actuation occurs during operation credit may be taken for automatic operation of valves. Operating experience has shown that these components usually pass the TSR when performed at the 18 month Frequency. Therefore, the Frequency is acceptable from a reliability standpoint.

Wolf Creek - Unit I - TRM B 3.7.7-3 Revision 58

Snubbers TR B 3.7.20 BASES TECHNICAL Surveillance Testing is performed in accordance with the applicable SURVEILLANCE requirements of ASME Section XI, "Rules for Inservice Inspection of REQUIREMENTS Nuclear Power Plant Components" (Ref. 1) and Subsection ISTD, "Preservice and Inservice Examination and Testing of Dynamic Restraints (Snubbers) in Light-Water Reactor Nuclear Power Plants" (Ref. 11).

NRC letter dated June 2, 2006 (Ref. 10), approved the proposed alternative to use TRM, Section 3.7.20, for snubber visual inspection and functional testing in lieu of the applicable ASME Code requirements specified in Section Xl, Article IWF-5000 for the third 10-year inservice inspection interval. The NRC safety evaluation specifies that changes to the TRM snubber visual inspection and functional testing requirements shall be submitted to the NRC for authorization pursuant to 10 CFR 50.55a(a)(3) or as an exemption pursuant to 10 CFR 50.12.

Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the Commission if a justifiable basis for exemption is presented and, if applicable, snubber life destructive testing was performed to qualify the snubber for the applicable design conditions at either the completion of their fabrication or at a subsequent date. Snubbers so exempted shall be listed in the list of individual snubbers indicating the extent of the exemptions.

In order to establish the inspection frequency for each type of snubber on a safety related system, it was assumed that the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber could cause the system to be unprotected and to result in failure during an assumed initiating event. Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.

TSR 3.7.20.1 TSR 3.7.20.1 comprises a visual inspection of the snubbers listed in Table TR 3.7.20-5. A pre-fuel load visual inspection and functional test has been performed on each snubber using the acceptance criteria listed in Table TR 3.7.20-2. The baseline takes into account that the snubbers have experienced thermal cycling and normal operating service as a result of previous hot functional testing. The initial inservice inspection has been performed on the snubbers prior to completion of the first Wolf Creek - Unit 1 - TRM B 3.7.20-8 Revision 56

Snubbers TR B 3.7.20 BASES TECHNICAL TSR 3.7.20.1 (continued)

SURVEILLANCE REQUIREMENTS refueling outage. The frequency of subsequent surveillances depends on the number of snubbers found nonfunctional from each previous inspection as provided in Table TR 3.7.20-3 and the Inservice Inspection Program as described in TR 5.5.6.

The acceptance criteria and corrective actions are listed in Table TR 3.7.20-2.

The visual inspections are designed to detect obvious indications of nonfunctionality of the snubbers. Removal of insulation or direct contact with the snubbers is not required initially. However, suspected causes of nonfunctionality are to be investigated and all snubbers of the same type and all snubbers subjected to the same failure mode are to be inspected more frequently.

The visual inspection frequency is based upon maintaining a constant level of snubber protection during an earthquake or severe transient and the number of unacceptable snubbers found during the previous inspection. As a result, the required inspection intervals vary inversely with the number of nonfunctional snubbers found during an inspection. If a snubber fails the visual acceptance criteria, the snubber is declared unacceptable and cannot be declared FUNCTIONAL via functional testing. However, if the cause of rejection is understood and remedied for that type of snubber and for any other type of snubbers that may be generically susceptible and FUNCTIONALITY verified by testing, that snubber may be reclassified acceptable for the purpose of establishing the next surveillance interval.

Snubbers may be categorized according to accessibility as noted in the Notes to Table TR 3.7.20-3. The accessibility of each snubber is determined based on radiation level as well as other factors such as temperature, atmosphere, location, etc. The recommendations of Regulatory Guide 8.8, "Information Relevant to Maintaining Occupational Radiation Exposure as Low a Practicable," (Ref. 7) and Regulatory Guide 8.10, "Operation Philosophy for Maintaining Occupational Radiation Exposure as Low as Practicable," (Ref. 8) are considered in planning and implementing the visual inspection program.

Since the visual inspections are augmented by a functional testing program, the visual inspection need not be a hands on inspection, but shall require visual scrutiny sufficient to assure that fasteners or mountings for connecting the snubbers to supports or foundations have no visible bolts, pins or fasteners missing, or other visible signs of physical damage such as cracking or loosening.

Wolf Creek - Unit 1 - TRM B 3.7.20-9 Revision 56 1

Snubbers TR B 3.7.20 BASES TECHNICAL TSR 3.7.20.2 SURVEILLANCE REQUIREMENTS This TSR is modified by a Note which restricts the performance of this (continued)

TSR to 60 days prior to and during a scheduled refueling outage.

TSR 3.7.20.2 comprises the functional testing of snubbers listed in Table TR 3.7.20-5. The testing for these snubbers have been separated into two sample plans as described in Table TR 3.7.20-4. Sample Plan 1.a (10%) is typically used for the snubbers with small population. Sample plan 1.b. (Figure TR 3.7.20-1) is typically used for snubbers with large population. Figure TR 3.7.20-1 was developed using "Wald's Sequential Probability Ratio Plan" as described in "Quality Control and Industrial Statistics" by Acheson J. Duncan.

The sample plan shall be selected prior to the test period and cannot be changed during the test period.

Snubber functional testing is performed to the requirements of Table TR 3.7.20-4 and performed prior to the completion of each refueling outage. The once each refueling Frequency, in conjunction with the Note, is based on the need to perform this surveillance under the conditions that apply just prior to or during a unit refueling outage.

TSR 3.7.20.3 This TSR addresses the monitoring of the service life of the snubbers in accordance with the Snubber Service Life Program described in TR 5.5.5.

The requirement to monitor the snubber service life is included to ensure that the snubbers periodically undergo a performance evaluation in view of their age and operating conditions.

TSR 3.7.20.4 If the plant has experienced an unexpected, potentially damaging snubber transient, an inspection per Table TR 3.7.20-1 is performed on all snubbers attached to sections of systems that have experienced the transient. The potential impact of the transient is assessed by reviewing operating data and by visually inspecting the associated system. In addition to the visual inspection, the freedom-of-motion of the mechanical snubber(s) is verified per Table TR 3.7.20-1.

Wolf Creek - Unit 1 - TRM B 3.7.20-10 Revision 56

Snubbers TR B 3.7.20 BASES References

7.

Regulatory Guide 8.8, "Information Relevant to Maintaining (continued)

Occupational Radiation Exposure as Low as Practicable."

8.

Regulatory Guide 8.10, "Operating Philosophy for Maintaining Occupational Radiation Exposure as Low as Practicable."

9.

WCAP-11618, "MERITS Program-Phase II, Task 5, Criteria Application," including Addendum 1 dated April, 1989, Section 3.7.9.

10.

NRC letter (D. Terao to R. Muench) dated June 2, 2006, "Wolf Creek Generating Station - Relief Request 13R-03 for the Third 10-Year Interval Inservice Inspection and Examination of Snubbers (TAC NO. MC8571)."

11.

ASME OM-2009, Subsection ISTD, ISTD-5240, "Test Frequency."

Wolf Creek - Unit 1 - TRM B 3.7.20-12 Revision 56

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REVISION NO. (2)

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DATE EFFECTIVE/

IMPLEMENTED (4)

TAB - Table of Contents 43 DRR 10-3738 12/28/10 ii 25 DRR 05-1996 9/28/05 iii 54 DRR 13-2529 10/25/13 TAB - B 3.0 APPLICABILTY B 3.0-1 41 DRR 10-1702 10/1/10 B 3.0-2 41 DRR 10-1702 10/1/10 B 3.0-3 41 DRR 10-1702 10/1/10 B 3.0-4 41 DRR 10-1702 10/1/10 B 3.0-5 41 DRR 10-1702 10/1/10 B 3.0-6 41 DRR 10-1702 10/1/10 B 3.0-7 41 DRR 10-1702 10/1/10 B 3.0-8 41 DRR 10-1702 10/1/10 B 3.0-9 41 DRR 10-1702 10/1/10 B 3.0-10 41 DRR 10-1702 10/1/10 B 3.0-11 41 DRR 10-1702 10/1/10 B 3.0-12 41 DRR 10-1702 10/1/10 B 3.0-13 41 DRR 10-1702 10/1/10 B 3.0-14 20 DRR 04-1410 10/7/04 TAB - B 3.1 REACTIVITY CONTROL SYSTEMS B 3.1.7-1 41 DRR 10-1702 10/1/10 B 3.1.7-2 41 DRR 10-1702 10/1/10 B 3.1.7-3 3

DRR 99-1581 12/18/99 B 3.1.8-1 41 DRR 10-1702 10/1/10 B 3.1.8-2 41 DRR 10-1702 10/1/10 B 3.1.9-1 15 DRR 03-0861 7/10/03 B 3.1.9-2 41 DRR 10-1702 10/1/10 B 3.1.9-3 41 DRR 10-1702 10/1/10 B 3.1.9-4 41 DRR 10-1702 10/1/10 B 3.1.9-5 41 DRR 10-1702 10/1/10 B 3.1.9-6 55 DRR 14-0344 2/27/14 B 3.1.9-7 28 DRR 06-1349 7/24/06 B 3.1.9-8 3

DRR 99-1581 12/18/99 B 3.1.10-1 41 DRR 10-1702 10/1/10 B 3.1.10-2 49 DRR 12-0674 4/10/12 B 3.1.10-3 48 DRR 12-0266 2/2/12 B 3.1.10-4 55 DRR 14-0344 2/27/14 B 3.1.10-5 48 DRR 12-0266 2/2/12 TAB - B 3.3 INSTRUMENTATION B 3.3.3-1 4

B 3.3.3-2 4

B 3.3.3-3 4

B 3.3.3-4 4

B 3.3.3-5 4

B 3.3.3-6 2

B 3.3.9-1 4

B 3.3.9-2 4

B 3.3.9-3 4

1.

1.

1.1

.8

.1 11

l DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 06-1349 DRR 10-1702 DRR 10-1702 DRR 10-1702 10/1/10 10/1/10 10/1/10 10/1/10 10/1/10 7/24/06 10/1/10 10/1/10 10/1/10 Wolf Creek - Unit 1 Revision 58

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENT MANUAL BASES PAGE (1)

REVISION NO. (2)

CHANGE DOCUMENT (3)

DATE EFFECTIVE/

IMPLEMENTED (4)

TAB - B 3.3 INSTRUMENTATION (continued)

B 3.3.9-4 8

B 3.3.10-1 3

B 3.3.10-2 41 B 3.3.10-3 41 B 3.3.11-1 41 B 3.3.11-2 41 B 3.3.11-3 41 B 3.3.11-4 41 B 3.3.11-5 39 B 3.3.12-1 41 B 3.3.12-2 37 B 3.3.12-3 19 B 3.3.13-1 41 B 3.3.13-2 41 B 3.3.13-3 41 B 3.3.13-4 3

B 3.3.14-1 51 B 3.3.14-2 51 B 3.3.14-3 53 B 3.3.14-4 53 B 3.3.14-5 51 B 3.3.14-6 53 B 3.3.14-7 51 B 3.3.14-8 51 B 3.3.14-9 51 B 3.3.14-10 51 B 3.3.14-11 51 B 3.3.15-1 45 B 3.3.15-2 45 B 3.3.15-3 46 B 3.3.15-4 45 B 3.3.15-5 45 B 3.3.16-1 41 B 3.3.16-2 41 B 3.3.16-3 41 B 3.3.16-4 41 B 3.3.16-5 41 B 3.3.17-1 19 B 3.3.17-2 41 B 3.3.17-3 41 B 3.3.17-4 41 B 3.3.17-5 3

B 3.3.18-1 14 B 3.3.18-2 41 B 3.3.18-3 49 B 3.3.18-4 49 B 3.3.18-5 49 B 3.3.18-6 49 B 3.3.18-7 49 B 3.3.19-1 43 B 3.3.19-2 43 DRR 01-0475 DRR 99-1581 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 09-1775 DRR 10-1702 DRR 09-0287 DRR 04-1019 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 99-1581 DRR 13-0371 DRR 13-0371 DRR 13-1518 DRR 13-1518 DRR 13-0371 DRR 13-1518 DRR 13-0371 DRR 13-0371 DRR 13-0371 DRR 13-0371 DRR 13-0371 DRR 11-0662 DRR 11-0662 DRR 11-0725 DRR 11-0662 DRR 11-0662 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 04-1019 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 99-1581 DRR 02-1459 DRR 10-1702 DRR 12-0673 DRR 12-0673 DRR 12-0673 DRR 12-0673 DRR 12-0673 DRR 10-3738 DRR 10-3738 5/1/01 12/18/99 10/1/10 10/1/10 10/1/10 10/1/10 10/1/10 10/1/10 10/28/09 10/1/10 3/20/09 9/1/04 10/1/10 10/1/10 10/1/10 12/18/99 2/26/13 2/26/13 6/26/13 6/26/13 2/26/13 6/26/13 2/26/13 2/26/13 2/26/13 2/26/13 2/26/13 3/21/11 3/21/11 4/11/11 3/21/11 3/21/11 10/1/10 10/1/10 10/1/10 10/1/10 10/1/10 9/1/04 10/1/10 10/1/10 10/1/10 12/18/99 2/12/03 10/1/10 4/10/12 4/10/12 4/10/12 4/10/12 4/10/12 12/28/10 12/28/10 Wolf Creek - Unit 1 ii Revision 58

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENT MANUAL BASES PAGE (1)

REVISION NO. (1)

CHANGE DOCUMENT (3)

DATE EFFECTIVE/

IMPLEMENTED (4)

TAB - B 3.3 INSTRUMENTATION (continued)

B 3.3.19-3 43 DRR 10-3738 12/28/10 B 3.3.19-4 43 DRR 10-3738 12/28/10 TAB - B 3.4 REACTOR COOLANT SYSTEM (RCS)

B 3.4.3-1 10 DRR 02-0122 2/28/02 B 3.4.3-2 10 DRR 02-0122 2/28/02 B 3.4.3-3 41 DRR 10-1702 10/1/10 B 3.4.3-4 31 DRR 007-0657 5/1/07 TAB - B 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)

B 3.4.10-1 41 DRR 10-1702 10/1/10 B 3.4.10-2 41 DRR 10-1702 10/1/10 B 3.4.16-1 3

DRR 99-1581 12/18/99 B 3.4.16-2 41 DRR 10-1702 10/1/10 B 3.4.16-3 33 DRR 07-1554 9/28/07 B 3.4.17-1 41 DRR 10-1702 10/1/10 B 3.4.17-2 35 DRR 08-0729 8/28/08 B 3.4.17-3 41 DRR 10-1702 10/1/10 B 3.4.17-4 35 DRR 08-0729 8/28/08 B 3.4.17-5 41 DRR 10-1702 10/1/10 B 3.4.17-6 41 DRR 10-1702 10/1/10 B 3.4.17-7 41 DRR 10-1702 10/1/10 B 3.4.17-8 41 DRR 10-1702 10/1/10 B 3.4.17-9 41 DRR 10-1702 10/1/10 B 3.4.18-1 3

DRR 99-1581 12/18/99 B 3.4.18-2 41 DRR 10-1702 10/1/10 B 3.4.18-3 41 DRR 10-1702 10/1/10 TAB - B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

B 3.5.1-1 3

DRR 99-1581 12/18/99 B 3.5.1-2 41 DRR 10-1702 10/1/10 B 3.5.1-3 3

DRR 99-1581 12/18/99 TAB - B 3.6 CONTAINMENT SYSTEMS B 3.6.1-1 38 DRR 09-1010 7/16/09 B 3.6.1-2 41 DRR 10-1702 10/1/10 B 3.6.1-3 41 DRR 10-1702 10/1/10 B 3.6.1-4 41 DRR 10-1702 10/1/10 B 3.6.1-5 37 DRR 09-0287 3/20/09 B 3.6.1-6 17 DRR 04-0452 5/26/04 B 3.6.1-7 36 DRR 08-1845 12/9/08 TAB - B 3.7 PLANT SYSTEMS B 3.7.7-1 B 3.7.7-2 B 3.7.7-3 B 3.7.7-4 B 3.7.8-1 57 57 58 8

41 DRR 14-1878 DRR 14-1878 DRR 14-2330 DRR 01-0475 DRR 10-1702 9/30/14 9/30/14 11/6/14 5/1/01 10/1/10 Wolf Creek - Unit 1 iii Revision 58

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENT MANUAL BASES PAGE (1)

REVISION NO. (2)

CHANGE DOCUMENT (3)

DATE EFFECTIVE/

IMPLEMENTED (4)

TAB - B 3.7 PLANT SYSTEMS (continued)

B 3.7.8-2 52 B 3.7.8-3 52 B 3.7.13-1 41 B 3.7.13-2 41 B 3.7.13-3 41 B 3.7.17-1 26 B 3.7.17-2 41 B 3.7.17-3 26 B 3.7.19-1 5

B 3.7.19-2 37 B 3.7.19-3 5

B 3.7.20-1 3

B 3.7.20-2 50 B 3.7.20-3 50 B 3.7.20-4 50 B 3.7.20-5 50 B 3.7.20-6 50 B 3.7.20-7 50 B 3.7.20-8 56 B 3.7.20-9 56 B 3.7.20-10 56 B 3.7.20-11 50 B 3.7.20-12 56 B 3.7.21-1 3

B 3.7.21-2 37 B 3.7.21-3 3

B 3.7.21-4 3

B 3.7.22-1 3

B 3.7.22-2 41 B 3.7.22-3 49 B 3.7.24-1 41 B 3.7.24-2 41 B 3.7.24-3 44 B 3.7.24-4 41 B 3.7.24.5 37 B 3.7.24-6 21 DRR 13-0658 DRR 13-0658 DRR 10-1702 DRR 10-1702 DRR 10-1702 DRR 06-0050 DRR 10-1702 DRR 06-0050 DRR 00-0958 DRR 09-0287 DRR 00-0958 DRR 99-1581 DRR 12-1537 DRR 12-1537 DRR 12-1537 DRR 12-1537 DRR 12-1537 DRR 12-1537 DRR 14-1570 DRR 14-1570 DRR 14-1570 DRR 12-1537 DRR 14-1570 DRR 99-1581 DRR 09-0287 DRR 99-1581 DRR 99-1581 DRR 99-1581 DRR 10-1702 DRR 12-064 DRR 10-1702 DRR 10-1702 DRR 11-0496 DRR 10-1702 DRR 09-0287 DRR 04-1535 3/28/13 3/28/13 10/1/10 10/1/10 10/1/10 2/28/06 10/1/10 2/28/06 8/17/00 3/20/09 12/18/99 12/18/99 8/30/12 8/30/12 8/30/12 8/30/12 8/30/12 8/30/12 7/1/14 7/1/14 7/1/14 8/30/12 7/1/14 12/18/99 3/20/09 12/18/99 12/18/99 12/18/99 10/1/10 4/10/12 10/1/10 10/1/10 3/9/11 10/1/10 3/20/09 12/1/04 TAB - B 3.8 ELECTRICAL POWER SYSTEMS B 3.8.1-1 47 B 3.8.1-2 47 B 3.8.1-3 47 B 3.8.11-1 3

B 3.8.11-2 41 B 3.8.11-3 41 B 3.8.11-4 54 B 3.8.11-5 41 B 3.8.11-6 41 DRR 11-2404 DRR 11-2404 DRR 11-2404 DRR 99-1581 DRR 10-1702 DRR 10-1702 DRR 13-2529 DRR 10-1702 DRR 10-1702 11/16/11 11/16/11 11/16/11 12/18/99 10/1/10 10/1/10 10/25/13 10/1/10 10/1/10 Wolf Creek - UnIt 1 iv Revision 58

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENT MANUAL BASES PAGE (1)

REVISION NO. (2)

CHANGE DOCUMENT (3)

DATE EFFECTIVE/

IMPLEMENTED (4)

TAB - B 3.9 REFUELING OPERATIONS B 3.9.7-1 3

DRR 99-1581 12/18/99 B 3.9.7-2 3

DRR 99-1581 12/18/99 B 3.9.9-1 41 DRR 10-1702 10/1/10 B 3.9.9-2 41 DRR 10-1702 10/1/10 B 3.9.9-3 17 DRR 04-0452 5/26/04 TAB - B 3.10 EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING B 3.10.1-1 3

DRR 99-1581 12/18/99 B 3.10.1-2 37 DRR 09-0287 3/20/09 B 3.10.1-3 3

DRR 99-1581 12/18/99 B 3.10.2-1 3

DRR 99-1581 12/18/99 B 3.10.2-2 37 DRR 09-0287 3/20/09 B 3.10.2-3 41 DRR 10-1702 10/1/10 B 3.10.3-1 3

DRR 99-1581 12/18/99 B 3.10.3-2 37 DRR 09-0287 3/20/09 B 3.10.3-3 37 DRR 09-0287 3/20/09 B 3.10.3-4 3

DRR 99-1581 12/18/99 Note 1 The page number is listed on the center of the bottom of each page.

Note 2 The revision number is listed in the lower right hand corner of each page.

number will be page specific.

The Revision Note 3 The change document will be the document requesting the change. Therefore, the change document should be a DRR number in accordance with AP 26A-002.

Note 4 The date effective or implemented is the date the Technical Requirement Bases pages are issued by Document Control.

Wolf Creek - Unit 1 V

Revision58

v t e Letter Sequence Request
TAC:MF5855, (Approved, Closed)
Initiation Request, Request Acceptance... Administration Questions Answers Results Approval Other:
MONTHYEAR2015-03-04 [Table View]

ML15084A513

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