wolf creek generating station updated safety analysis ... · subject: docket no. 50-482: revision...

W$LF CREEKNUCLEAR OPERATING CORPORATION

Cleveland ReasonerSite Vice President

March 11, 2015WO 15-0005

U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555

Subject: Docket No. 50-482: Revision 28 of the Wolf Creek Generating StationUpdated Safety Analysis Report

Gentlemen:

Pursuant to the updating requirements of 10 CFR 50.71(e), Wolf Creek Nuclear OperatingCorporation (WCNOC) is providing its Updated Safety Analysis Report (USAR), Revision 28.This submittal satisfies the Final Safety Analysis Report (FSAR) updating requirements of theaforementioned regulation. Per the requirement of 10 CFR 54.37(b), there are no newlyidentified systems, structures, and components that are subject to an aging managementreview 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 sinceissuance of the USAR, Revision 27. In addition to these technical changes, editorial changeshave been made and are included in Revision 28.

Attachment III to this letter provides a discussion of changes made in Revisions 55 through 58of 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 updatingrequirements of 10 CFR 50.71(e)(4). Chapter 2: Site Characteristics; Chapter 3: Design ofStructures Components, Equipment and Systems; Chapter 8: Electric Power; Chapter 9:Auxiliary Systems; and Chapter 12: Radiation Protection are considered sensitive unclassifiedinformation and therefore warrant withholding under 10 CFR 2.390.

7 053P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831

An Equal Opportunity Employer M/F/HCNVET

WO 15-0005 of 4

Enclosure II to this letter provides a CD-ROM containing the station-controlled drawings that areconsidered 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 controlleddrawings were relocated from the USAR in Revision 17. Enclosure II is considered sensitiveunclassified 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 andQuality Program Manual both of which are incorporated by reference into the USAR. TheUSAR Fire Hazards Analysis is considered sensitive unclassified information and thereforewarrants withholding under 10 CFR 2.390.

Enclosure IV to this letter provides a CD-ROM containing EQSD-I, EQ Summary DocumentSection I Program Description, and EQSD-lI, EQ Master List Section I1. Information from USARTable 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 forNUREG-0737; and USAR Figures 3.11(B)-i through 3.11(B)-49, has been relocated from theUSAR 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 withholdingunder 10 CFR 2.390.

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

This letter contains no commitments. WCNOC has historically submitted updates to the USARon March 11 of each year to coincide with the date of issuance of the WCGS operating licenseand to comply with the requirements of 10 CFR 50.71(e)(4). WCNOC considers that submittalsmade 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 ChangesAttachment II - USAR Changes Processed Since Revision 27Attachment III - Revisions 55 through 58 to the Technical Requirements Manual

WO 15-0005 of 4

Enclosure I -

Enclosure II -

Enclosure III -

Enclosure IV -

Enclosure V -

CD-ROM containing Updated Safety Analysis Report, Revision 28CD-ROM containing Updated Safety Analysis Report Controlled FigureDrawingsCD-ROM containing Updated Safety Analysis Report Fire Hazards Analysisand Quality Program ManualCD-ROM containing Updated Safety Analysis Report EQSD-I, EQ SummaryDocument Section I Program Description, and EQSD-II, EQ Master ListSection IITechnical Requirements Manual Replacement Pages and List of EffectivePages

cc: M. L. Dapas (NRC), w/a, w/eC. F. Lyon (NRC), w/a, w/eN. F. O'Keefe (NRC), w/a, w/eSenior Resident Inspector (NRC), w/a, w/e

WO 15-0005 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 VicePresident of Wolf Creek Nuclear Operating Corporation; that he has read the foregoingdocument and knows the contents thereof; that he has executed the same for and on behalf ofsaid Corporation with full power and authority to do so; and that the facts therein stated are trueand correct to the best of his knowledge, information and belief.

Byy__Cleveland ReasonerSite 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 15-0005Page 1 of 7

Attachment I to WO 15-0005

Commitment Changes


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) willcomplete 40 percent (107 of 267) of the Maintenance craft performed Technical Specificationsurveillance procedures. These will be prioritized based on the importance and frequency ofuse so that the most commonly performed procedures are considered first.

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

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


Commitment Description: WCNOC will verify completion of 40 percent (580 tasks) of thenew preventive maintenance scope of high critical (FID-1) classified assets as a result of Phase1 of the ongoing Preventive Maintenance Optimization project. FID-1 components areequipment whose failure would have a significant impact on level and continuity of risk, safetyfunctions, production and compliance.

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

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


Commitment Description: Essential Service Water (ESW) Piping Integrity1) ESW Water Hammer: Wolf Creek Nuclear Operating Corporation (WCNOC) will install themodification to mitigate water hammer during the Mid-Cycle Outage.2) ESW Below Ground: WCNOC will complete the below ground piping installation, tie-in andtesting 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 wastransferred to RCMS 2012-457.

Justification: Items 2 and 3 were completed by 5/1/2014. The commitment is being closedwith 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.


Commitment No. RCMS 2005-132 from WO 05-0003. dated 02121/2005

Commitment Description: WCNOC is working with the State of Kansas to obtain surveyinformation regarding offsite mobile chemical sources. WCNOC will update both the offsite andonsite hazardous chemical assessments in accordance with Regulatory Guide 1.78, Rev 1, andthe measured unfiltered inleakage results.

Change to Commitment: This commitment is a duplicate of RCMS #2005-087. Thecommitment has been closed and archived.

Justification: This commitment was written in response to Generic Letter 2003-01, ControlRoom 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 acceptancecriteria are exceeded during the subsequent operating cycle, WCNOC will, within 30 days,submit the revised analysis for Nuclear Regulatory Commission (NRC) review. If the revisedanalysis shows that the crack-growth acceptance criteria are not exceeded during either thecurrent or the subsequent operating cycle, WCNOC will, within 30 days, submit a letter to theNRC confirming that its analysis has been revised.

Change to Commitment: This commitment was closed due to the implementation of theInservice Inspection program.

Justification: 10 CFR 50.55a(g)(6)(ii)(D)(1) states as follows: "All licensees of pressurizedwater 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 theiraugmented inservice inspection program by December 31, 2008. Once a licensee implementsthis requirement, the First Revised NRC Order EA-03-009 no longer applies to that licenseeand shall be deemed to be withdrawn."


Commitment Description: If the NRC Staff finds that the crack growth formula in industryreport MRP-55 is unacceptable, WCNOC will revise its analysis that justifies relaxation of theorder within thirty days after NRC informs WCNOC of an NRC approved crack-growth rateformula.


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



Commitment Description: If WCNOC's revised analysis shows that the crack growthacceptance criteria are exceeded prior to the end of the current operating cycle, this relaxationrequest will be rescinded and WCNOC will, within 72 hours, submit to the NRC writtenjustification for continued operation.


Justification: In accordance with 10 CFR 50.55a(g)(6)(ii)(D)(1), once a licensee implementsthe Inservice Inspection Program, the First Revised NRC Order EA-03-009 no longer applies tothat licensee and shall be deemed to be withdrawn. A revised Operating License NPF-42 wasreleased on 12/9/2008 that removed Order EA-03-009, Interim Inspection Requirements forReactor Pressure Vessel Heads at pressurized water reactors (Reference Condition Action5523).

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

Commitment Description: WCNOC will submit a license amendment request to revise theTechnical Specifications within one year after NRC resolution of TSTF-448, "Control RoomHabitability." This license amendment request will utilize the guidance of TSTF-448, asappropriate.

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

Justification: This commitment was written in response to Generic Letter 2003-01, "ControlRoom Habitability." TSTF-448 Notice of Availability was issued 01/17/07. Letter WO 08-0001,"Application to Revise Technical Specifications Regarding Control Room Envelope Habitabilityin Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item ImprovementProcess" was submitted, on 01/15/2008, as a request to revise the TS. Incorporated byAmendment 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 ofissuance. Final Technical Specification (TS) Bases changes will be implemented pursuant toTS 5.5.14 at the time the amendment is implemented.

Change to Commitment: This commitment was satisfied, and changed to closed andarchived.

Justification: License amendment No. 171, was issued 11/07/2006. The amendment wasimplemented on 11/08/2006.



Commitment Description: If changes are required to address DW-12-013, WCNOC willimplement required changes, including emergency (EMG) procedure changes and associatedtraining if required.

Change to Commitment: The commitment was closed and archived.

Justification: This commitment was made in response to Generic Letter 2004-02 and GenericSafety Issue-191. It was determined that WCNOC is not susceptible to core blockage of 15g/FA (grams per fuel assembly), since further testing by the PWROG has confirmed that thechemical effects do not form with in the first 24 hours 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 CyberSecurity 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 FacilityOperating License and Request for Approval of the Cyber Security Plan" and the commitmentscontained in WO 09-0044, were withdrawn by WCNOC. As such, the commitments made areno longer valid. Letter WO 10-0048, "Revision to Renewed Facility Operating License andRequest 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 byRCMS 2013-489 found in letter WO 11-0017, "Response to Request for Additional InformationRegarding License Amendment Request for Approval of the Cyber Security Plan." Cybersecurity requirements are codified as new 10 CFR 73.54.


Commitment Description: For cyber security controls that have been identified forimplementation by the process described in Section 3 of the Cyber Security Plan, animplementation 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, thecommitments in this letter are no longer valid. Letter WO 10-0048 was submitted in place ofWO 09-0044, and the replacement commitment was RCMS 2013-488. RCMS 2013-488 wassuperceded by RCMS 2013-489 found in letter WO 11-0017. Cyber security requirements arecodified as new 10 CFR 73.54.



Commitment Description: The analysis of digital computer systems and networks inaccordance with Section 3 of the Cyber Security Plan will be performed and results documentedas required.


Justification: The source document, letter WO 09-0044 and the commitments contained inWO 09-0044, were withdrawn by WCNOC. As such, the commitments made are no longervalid. Letter WO 10-0048 was submitted in the place of WO 09-0044, and the replacementcommitment was RCMS 2013-488. RCMS 2013-488 was superceded by RCMS 2013-489found in letter WO 11-0017. Cyber security requirements are codified as new 10 CFR 73.54.


Commitment Description: Complete the implementation and enter the maintenance phase ofthe 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 andarchived.

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


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


Justification: This commitment is a duplicate of RCMS 2012-456. The source document for2012-456 is letter WM 12-0023, "Reply to Notice of Violation EA-12-135." The commitmentdate was changed to 04/02/2014 based on letter WO 12-0071, "Revision to a CommitmentMade in Reply to Notice of Violation EA-12-135." The commitment was able to be moved dueto 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.



Commitment Description: The purpose of this commitment was to track the 90 dayimplementation of a license amendment to the TS Bases. The commitment was written for arevision 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, dated10/17/2006. Updated Safety Analysis Report (USAR) change request 2011-020.


Commitment Description: WCNOC has verified that a hydrogen monitoring system capableof diagnosing beyond design-basis accidents is installed at Wolf Creek Generating Station(WCGS) and is making a regulatory commitment to maintain that capability. The hydrogenmonitors will be included in the Technical Requirements Manual (TRM). This regulatorycommitment will be implemented within 90 days of NRC approval of this amendment request.


Justification: The TRM, TR 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," andassociated TR Bases are revised consistent with the TS changes approved by Amendment No.157. The NRC concluded that hydrogen monitoring equipment requirements no longer meetany of the four criteria in 10 CFR 50.36(c)(2)(ii) for retention in the TS's, and therefore may berelocated 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.


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 animmediate short term corrective action. The air bubblers were to be part of an additionalcompensatory enhancement to prevent ice blockage, until a permanent design solution couldbe implemented. A modification has been implemented to prevent frazil ice formation. Thecurrent configuration does not allow for the air bubbler to be moved into position to be used.

Attachment II WO 15-0005Page 1 of 11

Attachment II to WO 15-0005

USAR Changes Processed Since Revision 27


USAR Change Request Description

14-002 REVISE THE USAR TO REFLECT CALCULATION DA-26, REV 1,FLOODING OF THE CONDENSER PIT DUE TO FAILURE OFCIRCULATING WATER SYSTEM EXPANSION JOINT. FLOODING OF THECONDENSER PIT DUE TO FAILURE DESCRIBED IN THE USAR, BUT THEANALYSIS 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 ANDNOT 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, "DEPRESSTHE START BUTTON," TO "MOMENTARILY PLACE HANDSWITCHBGHS0026, RSC M/U CTRL, TO RUN." THE CHANGE IS BEING MADE TOMATCH THE USAR TO ACTUAL PLANT DESIGN OF MAIN CONTROLBOARD PANEL RL002 FOR HANDSWITCH BGHS0026.

Page: 15.4-19

14-005 REVISE THE USAR TO CHANGE THE CONTROLLING ISOTOPE FORRADIATION MONITOR GE-RE-92 FROM KR-85 TO XE-133 IN TABLE 11.5-3. ALSO CHANGE THAT THE CLOSURE OF BLOWDOWN ISOLATIONVALVE 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 CASKSVERSUS SHIELDED DRUMS IN THE FILTER HANDLING SYSTEM.

Page: 11.4-8



14-007 REVISE THE USAR TO INCORPORATE CHANGE PACKAGE 12512 THATREPLACED THE THERMOCOUPLE CORE COOLING MONITOR. THEUPGRADE INVOLVES REPLACEMENT OF THE EXISTINGMICROPROCESSOR-BASED SYSTEM SUPPLIED BY WESTINGHOUSEWITH AN ADVANCED LOGIC SYSTEM SUPPLIED BY WESTINGHOUSE.

Page: 18.2-90Page: 18.2-84Page: 18.2-72Figure: 18.2-12

Page: 18.2-88Page: 18.2-83

Page: 18.2-87Page: 18.2-74

Page: 18.2-85Page: 18.2-73

14-008 REVISE THE USAR TO REFLECT JAMES EDWARDS, II, AS THE NEWMANAGER OPERATIONS AND THE RETIREMENT OF A SHIFTMANAGER.

Page: 13.1-19 Page: 13.1-16

14-009 REVISE THE USAR TO REFLECT THAT THE RESULTS OF ANALYSISDEMONSTRATES THAT THE REACTOR VESSEL INLET NOZZLES(INCLUDING THE SAFE-ENDS) AND THE RCS COLD LEG (INLET) PIPINGMEET THE ASME CODE REQUIREMENTS FOR DESIGN, NORMAL,EMERGENCY, FAULTED AND UPSET CONDITIONS. THE ANALYSISWAS 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 THEAUXILIARY FEEDWATER PUMP COOLERS, THE FUEL POOL COOLINGPUMP ROOM COOLERS, THE CONTROL ROOM AIR CONDITIONINGUNIT CONDENSERS, AND THE CLASS 1E SWITCHGEAR AIRCONDITIONING CONDENSERS.

Table: 9.2-3

14-011

Sheet: 2 Table: 9.2-3 Sheet: 1

REVISE THE USAR TO CLARIFY THAT THE PENETRATION THERMALCAPABILITY (TC) CURVE BE INDEPENDENTLY COORDINATED WITHTHE FUSE AND BREAKER TC CURVES.

Page: 8.1-12



14-012 REVISE THE USAR TO CORRECT THE PRIMARY AND BACKUPCONTAINMENT PENETRATION PROTECTION FOR LOAD CENTER FEDCIRCUITS FOR CLASS 1E LOADS. THE USAR WILL REFLECT THEPRIMARY AND BACKUP PROTECTION IS PROVIDED BY THE LOADCENTER INDIVIDUAL LOAD BREAKERS AND EITHER A SERIES FUSEOR MOTOR CONTROL CENTER BREAKER INSTEAD OF INDIVIDUALLOAD CIRCUIT BREAKERS AND ASSOCIATED LOAD CENTER MAINFEED 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 HIGHPOINT VENT VALVES. CONTAINMENT PENETRATIONS 14 AND 15 AREAFFECTED 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 WHICHREVISES TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENT3.7.10.1 AND 3.7.13.1 TO REDUCE THE REQUIRED RUN TIME FORPERIODIC OPERATION OF THE CONTROL ROOM PRESSURIZATIONSYSTEM FILTER TRAINS AND THE EMERGENCY EXHAUST SYSTEMFILTER TRAINS, WITH HEATERS ON, FROM 10 HOURS TO 15MINUTES, CONTINUOUS.

Page: 3A-20

Table: 9.4-2 Sheet: 13

14-016 REVISE THE USAR TO REFLECT THE REVISION OF CALCULATION9461-C-003, WATER SURFACE ELEVATION CALCULATION, TOINCORPORATE CHANGES TO THE SITE DUE TO VEHICLE BARRIERAROUND TRANSFORMERS XNB01/02 AND THE ONSITE FLEXBUILDINGS.

Page: 2.4-13



14-017 REVISE THE USAR TO ENHANCE READER COMPREHENSION OF THEMINIMUM CONTAINMENT PRESSURE ANALYSIS FOR EMERGENCYCORE COOLING SYSTEM PERFORMANCE EVALUATION IN USARSECTION 6.2.1.5. THE REVISION IS ADDING A DESCRIPTION OF THEBASIS OF THE CONTAINMENT PRESSURE MODEL AND TO PROVIDETHE INPUT PARAMETERS USED IN THE DETERMINATION OF THE FANCOOLER HEAT REMOVAL RATE USED IN LARGE BREAK LOSS OFCOOLANT 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: 13.1-21Page: 13.1-15

Table: 13.1-1

Figure: 13.1-2Figure: 13.1-1

Page: 13.1-20Page: 13.1-8

Page: 13.1-19Page: 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 CHEMICALADDITION BUILDING NEAR THE ESSENTIAL SERVICE WATER (ESW)PUMPHOUSE IN SUPPORT OF THE BELOW GROUND ESW PIPEREPLACEMENT 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) BEINGINCORPORATED BY REFERENCE AND REMOVED FROM THE USAR.SECTION 3.11(B) INFORMATION IS BEING DOCUMENTED INEQUIPMENT QUALIFICATON SUMMARY DOCUMENT-I (EQSD),SECTIONS I AND II, AND EQSD-II, ATTACHMENTS A - C. UPDATES TOEQSD DOCUMENTS ARE CONTROLLED THROUGH THE DESIGNCHANGE PROCESS.

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


USAR Change Request

Table: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-1 STable: 3.11(B)-3 STable: 3.11(B)-5 STable: 3.11(B)-10 STable: 1.6-4 STable: 3.11(B)-1 STable: 3.11(B)-1 STable: 3.11(B)-2 STable: 3.11(B)-2 STable: 3.11(B)-2 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-8 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 STable: 3.11(B)-3 S

Description

;heet: 22;heet: 11;heet: 13heet: 15heet: 17heet: 19heet: 21;heet: 23;heet: 25heet: 27;heet: 29heet: 31;heet: 33heet: 6;heet: 1;heet: 1;heet: 1;heet: 2;heet: 3;heet: 5•heet: 2;heet: 4;heet: 6;heet: 3•heet: 5heet: 7;heet: 75heet: 64;heet: 66;heet: 68heet: 70;heet: 72;heet: 74;heet: 76;heet: 78heet: 80;heet: 82;heet: NOTES;heet: 3heet: 49;heet: 37;heet: 39;heet: 41;heet: 43;heet: 45;heet: 62

Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:

3.11(B)-13.11 (B)-33.11 (B)-33.11 (B)-33.11 (B)-33.11 (B)-33.11 (B)-33.11 (B)-33.11 (B)-33.11(B)-33.11 (B)-33.11(B)-33.11(B)-33.11 (B)-23.11 (B)-43.11(B)-81.6-43.11(B)-13.11(B)-33.11(B)-33.11(B)-23.11 (B)-23.11(B)-33.11 (B)-33.11 (B)-33.11(B)-13.11 (B)-33.11 (B)-33.11 (B)-33.11 (B)-33.11 (B)-33.11(B)-33.11 (B)-33.11 (B)-33.11(B)-33.11 (B)-33.11 (B)-33.11(B)-83.11 (B)-33.11 (B)-83.11 (B)-33.11(B)-33.11 (B)-33.11 (B)-33.11 (B)-33.11 (B)-3

Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:Sheet:

1121416189824262830322014112103635246463656769713460777981832734384042444648



Table: 3.11(B)-3Table: 3.11(B)-3Table: 3.11(B)-3Table: 3.11(B)-3Table: 3.11 (B)-3Table: 3.11(B)-3Table: 3.11(B)-3Table: 3.11(B)-2Table: 3.11(B)-4Table: 3.11(B)-8

Figure: 3.11 (B)-12Figure: 3.11 (B)-23Figure: 3.11 (B)-21Figure: 3.11 (B)-1 9Figure: 3.11 (B)-1 7Figure: 3.11(B)-15Figure: 3.11 (B)-I 3Figure: 3.11 (B)-I 1Figure: 3.11 (B)-9Figure: 3.11(B)-7Figure: 3.11(B)-5Figure: 3.11 (B)-3Figure: 3.11 (B)-14Figure: 3.11 (B)-48Figure: 3.11 (B)-47Figure: 3.11 (B)-46Figure: 3.11 (B)-44Figure: 3.11 (B)-42Figure: 3.11 (B)-25Figure: 3.11 (B)-26Figure: 3.11 (B)-36Figure: 3.11 (B)-34Figure: 3.11(B)-32Figure: 3.11 (B)-30Figure: 3.11 (B)-28Figure: 3.11 (B)-40

Sheet: 61Sheet: 51Sheet: 53Sheet: 55Sheet: 57Sheet: 59Sheet: 47

Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:

3.11(B)-33.11(B)-33.11(B)-33.11(B)-33.11(B)-33.11(B)-33.11(B)-13.11 (B)-33.11(B)-53.11(B)-10

Sheet: 50Sheet: 52Sheet: 54Sheet: 56Sheet: 58Sheet: 35

Figure: 3.11 (B)-24Figure: 3.11 (B)-22Figure: 3.11 (B)-20Figure: 3.11 (B)-1 8Figure: 3.11(B)-1 6Figure: 3.11 (B)-IFigure: 3.11 (B)-27Figure: 3.11(B)-1 0Figure: 3.11 (B)-8Figure: 3.11(B)-6Figure: 3.11 (B)-4Figure: 3.11 (B)-2Figure: 3.11 (B)-38Figure: 3.11 (B)-49Figure: 3.11(B)Figure: 3.11 (B)-45Figure: 3.11 (B)-43Figure: 3.11 (B)-41Figure: 3.11 (B)-39Figure: 3.11 (B)-37Figure: 3.11 (B)-35Figure: 3.11 (B)-33Figure: 3.11 (B)-31Figure: 3.11 (B)-29Figure: 3.11 (B)-7AFigure: 3.11 (B)-9A

14-021 REVISE THE USAR TO REFLECT THE ADDITION OF A NEW CATHODICPROTECTION BUIDLING NEAR THE FIRING RANGE TO PROTECT THENEW ESSENTIAL SERVICE WATER PIPELINE ON THE LIST OFPRINCIPLE STRUCTURES.

Page: 1.2-6 Page: 1.2-7



14-022 REVISE THE USAR TO REFLECT THE INSTALLATION OF ANALTERNATE JOCKEY PUMP TO PROVIDE PRESSURE MAINTENANCEFOR THE FIRE PROTECTION WATER SYSTEM.

Page: 9.5-7 Page: 9.5-5

Table: 9.5A-1Table: 9.5A-1 Sheet: 45 Sheet: 44

14-023

Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:

Table:Table:Table:Table:Table:Table:Table:Table:Table:Table:

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

3.0-xxxv2.0-xxxiii3.0-xxxiv2.0-xxvii2.5-2552.4-742.5-702.5-2023.7(S)-33C-22.5-2013.8-709.4-853.5-132.5-622.5-2229.4-882.5-246

2.4-162.5-372.5-67A3.5-39.2-52.5-322.5-54A3.4-13.7(S)-22.5-36


2.0-xxx2.0-xxxii2.0-xxxvi2.0-xxvi2.5-2242.5-592.4-752.5-2592.5-1173.8-643.5-113.8-633C-103.8-679.2-52.5-2252.5-2369.2-7


2.0-xxxix2.0-xxxi2.0-xxxvii3.0-xxxviii2.0-xxiv2.5-612.5-2002.5-2202.5-2583.8-653.8-603.8-759.2-322.5-2352.5-3523.5-122.5-2399.2-11


2.0-xxxviii2.0-xxxv2.0-xxxiv3.0-xxiv2.5-2322.5-69241-23.8-692.5-1993.8-769.2-92.5-2333C-9241-12.5-2212.5-2342.5-2453.4-1

Sheet: 2

Sheet:Sheet:Sheet:

Sheet:

Sheet:Sheet:Sheet:Sheet:

213

Table: 2.5-36Table: 2.5-37Table: 3.3-1Table: 2.5-36Table: 3.7(S)-iTable: 2.5-54ATable: 3.2-1Table: 3.4-2Table: 3C-1Table:2.5-37

Sheet: 3Sheet: 3

Sheet: 2

Sheet: 2Sheet: 21

Sheet: 2Sheet: 1

Figure: 2.5-36qqqqFigure: 2.5-36jjjjFigure: 2.5-361111Figure: 2.5-36nnnn

1-21-31-31-3

Figure:2.5-36iiiiFigure:2.5-36kkkkFigure:2.5-36mmmmFigure:2.5-30

Sheet:Sheet:Sheet:

1-31-31-4



Figure: 2.5-36ppppFigure: 2.5-36rrrrFigure: 2.5-36ttttFigure: 2.5-36mmmFigure: 2.5-36vvvvFigure: 2.5-36yyyFigure: 2.5-36nnnFigure: 2.5-36pppFigure: 2.5-36rrrFigure: 2.5-36hhhhFigure: 2.5-36ggggFigure: 2.5-36aaaaFigure: 2.5-36ccccFigure: 2.5-36eeeeFigure: 2.5-36wwwFigure: 2.5-36wwwwFigure: 3.8-135Figure: 3.8-136Figure: 3.8-138Figure: 3.5-1Figure: 3.8-142Figure: 3.8-144Figure: 3C-4Figure: 2.5-105Figure: 2.5-105wFigure: 2.5-51Figure: 2.5-62dFigure: 2.5-36vvvFigure: 3.8-132Figure: 2.5-36zzzzFigure: 2.5-105yFigure: 2.5-36sssFigure: 2.5-107aFigure: 2.5-105r

Sheet: 1-2

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

Sheet:Sheet:Sheet:

1-31-31-3

Figure: 2.5-36ffffFigure: 2.5-36ssssFigure: 2.5-36uuuuFigure: 2.5-36yyyyFigure: 2.5-36ooooFigure: 2.4-55Figure: 2.5-36oooFigure: 2.5-36qqqFigure: 2.5-36tttFigure: 2.5-36xxxFigure: 2.5-36zzzFigure: 2.5-36bbbbFigure: 2.5-36ddddFigure: 2.5-47Figure: 2.5-107bFigure: 3.8-134Figure: 3.8-135aFigure: 3.8-137Figure: 2.5-108Figure: 2.5-36uuuFigure: 3.8-143Figure: 3.8-145Figure: 2.5-98Figure: 3.8-139Figure: 2.5-36xxxxFigure: 2.5-62cFigure: 2.5-62eFigure: 2.5-105jFigure: 2.5-105vFigure: 2.5-105xFigure: 2.5-105zFigure: 2.5-118Figure: 2.5-114Figure: 1.2-43

Sheet:Sheet:Sheet:Sheet:

Sheet:Sheet:Sheet:

Sheet:Sheet:Sheet:

1-31-21-21-2

1-21-31-3

1-31-31

Sheet: 1-2

Sheet: 1-3

Sheet: 1-3

Sheet: 1-3

Sheet: 1-2

Sheet: 1-2

Sheet: 1-3Sheet: 1-5

Sheet: 1-2

Sheet: 1-2

Sheet: 1



14-024 REVISE THE USAR TO REFLECT A CHANGE IN THE MAIN GENERATORNAMEPLATE 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

THISOF

PREVIOUSLY APPROVED CHANGES THATINCORPORATED.

WERE NOT CORRECTLY

Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:

Table:Table:Table:

14-026

2.0-xix3.0-xi3.0-vii2.0-xxii2.0-iv1.0-v9.0-vii15.0-v11.0-vi9.0-xv3.0-xxiv6.0-xxi6.0-i3.5-13

Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:

3.0-xxii3.0-xix3.0-iii3.0-xxxiv2.0-iii1.0-iv2.0-xxxiv13.0-iv11.0-ii9.0-viii8.0-iii6.0-xix18.0-v10.4-11

Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:

3.0-xvii3.0-ix3.0-ii2.0-xvii2.0-ii1.0-i9.0-xi13.0-iii10.0-vii3.0-xxiii8.0-i6.0-xviii3.0-xxxv

Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:Page:

3.0-xvi3.0-xviii10.0-iii2.0-v1.0-vii2.0-xxiv18.0-iii13.0-i10.0-i9.0-iv7.0-ix6.0-ix2.5-224

11.5-311.5-17.4-1

Table: 11.5-2Table: 11.5-1 Sheet: 1

Table: 3.6-3 Sheet: 24Sheet: 2Sheet: 2

REVISE THE USAR TO REFLECT C. D. HAWES AS THESUPERINTENDENT OPERATIONS SUPPORT (TRAINING).

Page: 13.1-19 Page: 13.1-17

14-027 REVISE THE USAR TO CHANGE THE VACUUM FLOW RATE ONGERE092 FROM 2.6 TO 3.0 SCFM.

Table: 11.5-3



14-028 REVISE THE USAR TO REFLECT THE REPLACEMENT OF THE FIREALARM SYSTEM COLOR GRAPHICS TOUCH SCREEN ANNUNCIATORSYSTEM WITH A NEW STATE-OF-THE-ART SYSTEM.

Page: 9.5-16

14-029 THE USAR IS BEING REVISED TO REFLECT THE COMPLETION OF THENEW EMERGENCY OFFSITE FACILITY AND ALTERNATE TECHNICALSUPPORT CENTER FACILITY. THE NEW FACILITY IS REQUIRED DUETO 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 VOICEOVER INTERNET PROTOCOL (VOIP) PHONE TECHNOLOGY THATREPLACED THE PRIVATE BRANCH EXCHANGE (PBX) TELEPHONESYSTEM.

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 pHVERSUS TIME.

Figure: 6.5-5

15-002 REVISE THE USAR TO REFLECT THE ADDITION OF FOUR 345 kVTRANSMISSION LINES. ONE FROM THE RENO SUBSTATION TOSUMMIT SUBSTATION, ONE FROM ROSE HILL SUBSTATION TO THESOONER SUBSTATION, AND TWO FROM WICHITA TO THISTLE.

Page: 8.2-3

Figure: 8.2-5 Figure: 8.2-1

Attachment III to WO 15-0005Page 1 of 3

Attachment III to WO 15-0005

Revisions 55 through 58 to the Technical Requirements Manual


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 headerfor TR 3.3.17 was identified as Explosive Gas Monitoring Instrumentation, TR 3.3.16. Theheader 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, "BorationInjections System - Shutdown," pages B 3.1.9-6 and B 3.1.10-4 were revised to delete thesentence, "All of the boron solution volume of the BATs is considered to be usable." Areview of WCRE-03, "Wolf Creek Tank Document," identified that the total volume of oneBoric Acid Tank (BAT) as 27,755 gallons. Updated Safety Analysis Report (USAR) Table9.3-9 and document 10466-M-10BG, "System Description Chemical and Volume ControlSystem," specify the usable capacity of a BAT as 24,000 gallons. Based on thisinformation, the statements in the TRM do not reflect the information in the USAR andsystem description documents. This change revises the TRM to be consistent with thesystem description documents and the USAR.

3. Technical Surveillance Requirement (TSR) 3.7.20.2 (Snubber Functional Tests) andassociated TR Bases were revised to change the TSR Frequency to be consistent withSubsection ISTD of the 2009 edition of the ASME Operation and Maintenance (ASMEOM-2009) Code. The changes to TSR 3.7.20.2 are consistent with ISTD-5240, "TestFrequency," which states: Tests of snubbers from the facility shall be performed every fuelcycle. Snubber testing may begin no earlier than 60 days before a scheduled refuelingoutage." Specifically the Note to TSR 3.7.20.2 was revised from "This surveillance shallnot be performed in MODES 1 and 2." to "This surveillance shall begin no earlier than 60days before a scheduled refueling outage." The TSR Frequency is revised from "18months" to "Once each refueling".

4. Technical Requirement Manual (TRM) page 3.3-30 is revised to correct the headerassociated with TR 3.3.17. The header for TR 3.3.17 is currently identified as Primary toSecondary LEAKAGE Detection Instrumentation, TR 3.3.18. The header should beReactivity Control and Power Distribution Alarms, TR 3.3.17.

5. TR 3.7.7, "Component Cooling Water (CCW) System Instrumentation," and associatedTR Bases were revised to remove from TR 3.7.7 the requirement for the RadwasteBuilding loop high flow instrumentation to be FUNCTIONAL. Design Change Package(DCP) 13540, Rev. 0, provides a modification to restrict flow to the non-safety relatedCCW 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 CCWto Radwaste high flow trips, the requirements in TR 3.7.7 to maintain the loop high flowinstrumentation 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 anerror 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


Specification 5.2.2 and the minimum staffing necessary to meet plant operationalrequirements and radiological emergency response staffing requirements.

7. The Bases for TSR 3.7.7.2 Frequency were revised for consistency with TechnicalSpecification Surveillance Requirement (SR) 3.7.7.2. The revision allows individual valvesto be tested during power operation under appropriate administrative controls. TSR3.7.7.2 requires a CHANNEL CALIBRATION that includes verifying valves EGHV0069A/Band EGHV0070A/B close from surge tank level instrumentation. Prior to conversion to theImproved TS (Amendment No. 123 - 1999), TS Surveillance Requirement 4.7.3c. stated:"At least once per 18 months during shutdown, by performing a CHANNEL CALIBRATIONof the surge tank level and flow instrumentation which provide automatic isolation of thenon-nuclear safety-related portion of the system." The TSR Bases requirement to onlyperform the TSR during shutdown conditions is overly conservative and the performanceof the TSR at power will not impact plant operation. Revising the TSR 3.7.7.2 Bases to beconsistent with TS SR 3.7.7.2 provides for consistency of testing requirements.

Enclosure I to WO 15-0005Page 1 of 2

Enclosure I to WO 15-0005

CD-ROM containing Updated Safety Analysis Report, Revision 28

Enclosure I to WO 15-0005Page 2 of 2

SubjectEnclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated SafetyAnalysis Report (WCGS USAR), Revision 28. In accordance with 10 CFR 2.390, WCGS USARChapters 2, 3, 8, 9, and 12 contain sensitive unclassified information and therefore warrantwithholding.

Contact NameMailing Address

E-Mail AddressPhone Number

Lucille RockersWolf Creek Nuclear Operating CorporationP.O. Box 411Burlington, KS 66839lurocke(Dwcnoc.com620-364-8831 ext. 4898

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

001_USAR.pdf002_USARC01 .pdf003_USARC02.0.pdf004_USARC02 Figures.pdf005 USARC03.pdf006 USARC04.pdf007 USARC05.pdf008 USARC06.pdf009 USARC07.pdf010 USARC08.pdf011 USARC09.pdf012 USARC10.pdf013 USARC11.pdf014 USARC12.pdf015 USARC13.pdf016 USARC14.pdf017 USARC15.pdf018 USARC16.pdf019 USARC17.pdf020 USARC18.pdf021_USARNRCQ.pdf022_USAR Rev. 28-loep.pdf

238 KB, sensitive unclassified information774 KB, publicly available

34.7 MB, sensitive unclassified information35.4 MB, sensitive unclassified information15.4 MB, sensitive unclassified information2.24 MB, publicly available2.36 MB, publicly available10.5 MB, publicly available1.82 MB, publicly available2.14 MB, sensitive unclassified information7.0 MB, sensitive unclassified information1.4 MB, publicly available941 KB, publicly available776 KB, sensitive unclassified information857 KB, publicly available338 KB, publicly available

4.96 MB, publicly available56 KB, publicly available64 KB, publicly available

1.15 MB, publicly available348 KB, publicly available405 KB, publicly available

Enclosure II to WO 15-0005Page 1 of 2

Enclosure II to WO 15-0005

CD-ROM containing Updated Safety Analysis Report Controlled Figure Drawings

Enclosure II to WO 15-0005Page 2 of 2

SubjectEnclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated SafetyAnalysis Report (WCGS USAR) controlled figure drawings that are considered incorporated byreference into the WCGS USAR. In accordance with 10 CFR 2.390, this enclosure isconsidered sensitive unclassified information and therefore warrants withholding.



Lucille RockersWolf Creek Nuclear Operating CorporationP.O. Box 411Burlington, KS 66839lurocke@,wcnoc.com620-364-8831 ext. 4898

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

001_Chapter 1 .pdf002_Chapter 2.pdf003_Chapter 5.pdf004_Chapter 6.pdf005 Chapter 7.pdf006_Chapter 8.pdf007_Chapter 9.pdf008_Chapter 10.pdf009_Chapter 11 .pdf010_Chapter 12.pdf011_Chapter 18.pdf012_Index Removed Figure List.pdf

9.15 MB, sensitive unclassified information2.34 MB, sensitive unclassified information1.16 MB, sensitive unclassified information2.38 MB, sensitive unclassified information

932 KB, sensitive unclassified information1.28 MB, sensitive unclassified information22.6 MB, sensitive unclassified information6.77 MB, sensitive unclassified information4.10 MB, sensitive unclassified information1.16 MB, sensitive unclassified information

227 KB, sensitive unclassified information89 KB, sensitive unclassified information

Enclosure III to WO 15-0005Page 1 of 2

Enclosure III to WO 15-0005

CD-ROM containing Updated Safety Analysis Report Fire Hazards Analysis and QualityProgram Manual

Enclosure III to WO 15-0005Page 2 of 2

SubjectEnclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated SafetyAnalysis Report Fire Hazards Analysis and Wolf Creek Quality Program Manual (WCQPM),both of which are considered incorporated by reference into the WCGS USAR. In accordancewith 10 CFR 2.390, the WCGS USAR Fire Hazards Analysis is considered sensitiveunclassified information and therefore warrants withholding.



Lucille RockersWolf Creek Nuclear Operating CorporationP.O. Box 411Burlington, KS 66839lurocke(-wcnoc.com620-364-8831 ext. 4898

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

001_WCQPM Rev 9.pdf002_E-1 F9900 Rev 9.pdf003_E-1 F9905 Rev 6.pdf004_E-1 F9910 Rev 12.pdf005_XX-E-013 Rev 3.pdf006_XX-E-013 Rev 3_CN003.pdf007_XX-E-013 Rev 3_CN004.pdf008_XX-E-013 Rev 3_CN005.pdf009_XX-E-013 Rev 3_CN007.pdf010_M-663-00017A W05 1 to B1-98.pd011_M-663-00017A W05 Bl-99 to B2-40.pdf012_M-663-00017A W05 B2-41 to B6-2.pdf013_M-663-00017A W05 B6-3 to B7-79.pdf014_M-663-00017A W05 B7-80 to B8-147.pdf015_M-663-00017A W05 B8-148 to B13-25.pdf016_M-663-00017A W05 B13-26 to G1A-63.pdf017_M-663-00017A W05 G1A-64 to G1A-123.pdf018_M-663-00017A W05 G1A-124 to G2A-3.pdf019_M-663-00017A W05 G2B-1 to G2B79.pdf020_M-663-00017A W05 Att G3 to G3D-26.pdf021_M-663-00017A W05 G3D-27 to G4D-19.pdf022_M-663-00017A W05 Att G5 to Att H.pdf

5.13 MB, publicly available5.30 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 unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassifiedsensitive unclassified

informationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformationinformation

Enclosure IV to WO 15-0005Page 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 15-0005Page 2 of 2

SubjectEnclosed is the CD-ROM submittal of the Wolf Creek Generating Station Updated SafetyAnalysis 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 theWCGS USAR. In accordance with 10 CFR 2.390, the WCGS EQSD-I, EQ Summary DocumentSection I Program Description, and EQSD-II, EQ Master List Section II, is considered sensitiveunclassified information and therefore warrants withholding.



Lucille RockersWolf Creek Nuclear Operating CorporationP.O. Box 411Burlington, KS 66839l urocke(awcnoc.com620-364-8831 ext. 4898

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

001_EQSD-l Rev 7.pdf002_EQSD-II Rev 27.pdf003_EQSD-ll-027-CN01 .pdf

11.3 MB, sensitive unclassified information1.26 KB, sensitive unclassified information187 KB, sensitive unclassified information

Enclosure V to WO 15-0005Page 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 AlarmsTR 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 hournonfunctional. Specification Surveillance

Requirement (SR) 3.2.3.1.

B. Rod Insertion Limit Alarm B.1 Perform Technical Once per 4 hoursnonfunctional. Specification SR 3.1.6.2.

C. Rod Position Deviation C.1 Perform Technical Once per 4 hours

Alarm nonfunctional. Specification SR 3.1.4.1.

(continued)

Wolf Creek - Unit 1 TRM3R 3.3-28 Revision 55

Reactivity Control and Power Distribution AlarmsTR 3.3.17

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

APPLICABLE MODESOR OTHER

ANNUCIATOR SPECIFIEDFUNCTION 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.

With THERMAL POWER > 50% RTP.

Wolf Creek - Unit 1 TRM 3.3-30 Revision 56

CCW System InstrumentationTR 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 FUNCTIONALfor each CCW train.

APPLICABILITY: MODES 1, 2, 3, and 4 when non-essential loads are supplied by associatedCCW train.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One or more required A.1 Restore required 72 hourschannel(s) nonfunctional. channel(s) to

FUNCTIONAL status.

B. Required Action and B.1 Initiate Condition Report. Immediatelyassociated CompletionTime not met.

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

SnubbersTR 3.7.20

TECHNICAL SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

TSR 3.7.20.2 --------- NOTE -.-.--............-----------This surveillance shall begin no earlier than 60 daysbefore a scheduled refueling outage.

Perform a functional test on a representative sample Once eachof each type of snubber in accordance with Table TR refueling3.7.20-4.

TSR 3.7.20.3 Verify that the service life of mechanical snubbers is In accordance withnot exceeded. Snubber Service

Life Program

TSR 3.7.20.4 Perform an inspection of all required snubbers Within 6 monthsattached to sections of systems that have following the eventexperienced an unexpected potentially damagingtransient in accordance with Table TR 3.7.20-1.

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

OrganizationTR 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 OperationalRequirements

POSITION MODE 1, 2, 3, or 4 MODE 5 or 6 At All Times

SM 1 1 (b) 1CRS 1 None 1RO 2 1 2

NSO 2 1 5 (c)(d)

STA 1 (a) None 1 (e)

CHM None None 2HP 1 1 3

ENS Communicator None None 1Offsite Communicator None None 1

SMCRSRONSOSTACHMHP

Shift Manager with a Senior Operator license on Unit 1Control Room Supervisor with a Senior Operator license on Unit 1Individual with an Operator license on Unit 1Nuclear Station OperatorShift Technical Advisor (Shift Engineer)Chemistry PersonnelHealth Physics Personnel

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

(b) One individual with a Senior Operator license, either Shift Manager or Control RoomSupervisor.

(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, thisposition is not required to be filled by an individual qualified as a STA.

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

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENT MANUAL

PAGE (1) REVISION NO. (2) CHANGE DOCUMENT (3) DATE EFFECTIVE/IMPLEMENTED (4)

TAB - Title Page TRMTitle Page

TAB - Table of Contentsi 43 DRR 10-3738 12/28/10ii 35 DRR 08-0727 8/28/08iii 54 DRR 13-2529 10/25/13TAB - 1.0 USE AND APPLICATION1.0-1 41 DRR 10-1702 10/1/101.0-2 41 DRR 10-1702 10/1/10TAB - 3.0 APPLICABILTY3.0-1 41 DRR 10-1702 10/1/103.0-2 41 DRR 10-1702 10/1/103.0-3 41 DRR 10-1702 10/1/103.0-4 20 DRR 04-1410 10/7/04

TAB - 3.1 REACTIVITY CONTROL SYSTEMS3.1-1 41 DRR 10-1702 10/1/103.1-2 3 DRR 99-1581 12/18/993.1-3 34 DRR 08-0256 3/11/083.1-4 34 DRR 08-256 3/11/083.1-5 41 DRR 10-1702 10/1/103.1-6 37 DRR 09-0287 3/20/093.1-7 41 DRR 10-1702 10/1/103.1-8 41 DRR 10-1702 10/1/103.1-9 11 DRR 02-0412 4/5/023.1.10 48 DRR 12-0266 2/2/12

TAB - 3.3 INSTRUMENTATION3.3-13.3-23.3-33.3-43.3-53.3-63.3-73.3-83.3-93.3-103.3-113.3-123.3-133.3-143.3-153.3-163.3-173.3-183.3-193.3-203.3-213.3-22

41412341412323434141393939493939413951515151

DRR 10-1702DRR 10-1702DRR 05-0708DRR 10-1702DRR 10-1702DRR 05-0708DRR 05-0708DRR 10-3738DRR 10-1702DRR 10-1702DRR 09-1775DRR 09-1775DRR 09-1775DRR 12-0673DRR 09-1775DRR 09-1775DRR 10-1702DRR 09-1775DRR 13-0371DRR 13-0371DRR 13-0371DRR 13-0371

10/1/1010/1/104/20/0510/1/1010/1/104/20/054/20/0512/28/1010/1/1010/1/10

10/28/0910/28/0910/28/094/10/1210/28/0910/28/0910/1/10

10/28/092/26/132/26/132/26/132/26/13

Wolf Creek - Unit 1 i Revision 57



TAB - 3.3 INSTRUMENTATION (continued)3.3-23 51 DRR 13-0371 2/26/133.3-24 51 DRR 13-0371 2/26/133.3-25 51 DRR 13-0371 2/26/133.3-26 51 DRR 13-0371 2/26/133.3-27 51 DRR 13-0371 2/26/133.3-28 55 DRR 14-0344 2/27/143.3-29 51 DRR 13-0371 2/26/133.3-30 56 DRR 14-1570 7/1/143.3-31 51 DRR 13-0371 2/26/133.3-32 51 DRR 13-0371 2/26/133.3-33 51 DRR 13-0371 2/26/133.3-34 51 DRR 13-0371 2/26/133.3-35 51 DRR 13-0371 2/26/133.3-36 51 DRR 13-0371 2/26/133.3-37 51 DRR 13-0371 2/26/13

TAB - 3.4 REACTOR COOLANT SYSTEM (RCS)3.4-1 37 DRR 09-0287 3/20/093.4-2 3 DRR 99-1581 12/18/993.4-3 41 DRR 10-1702 10/11/103.4-4 41 DRR 10-1702 10/11/103.4-5 3 DRR 99-1581 12/18/993.4-6 33 DRR 07-1554 9/28/073.4-7 33 DRR 07-1554 9/28/073.4-8 41 DRR 10-1702 10/1/103.4-9 41 DRR 10-1702 10/1/103.4-10 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 SYSTEMS3.6-1 17 DRR 04-0452 5/26/043.6-2 37 DRR 09-0287 3/20/093.6-3 17 DRR 04-0452 5/26/04

TAB - 3.7 PLANT SYSTEMS3.7-13.7-23.7-33.7-43.7-53.7-63.7-73.7-83.7-93.7-103.7-113.7-12

572852414141263750505650

DRR 14-1878DRR 06-1349DRR 13-0658DRR 10-1702DRR 10-1702DRR 10-1702DRR 06-0050DRR 09-0287DRR 12-1537DRR 12-1537DRR 14-1570DRR 12-1537

9/30/147/24/063/28/1310/1/1010/1/1010/1/102/28/063/20/098/30/128/30/127/1/148/30/12

Wolf Creek - Unit 1 ii Revision 57



TAB - 3.7 PLANT SYSTEMS (continued)3.7-13 50 DRR 12-1537 8/30/123.7-14 50 DRR 12-1537 8/30/123.7-15 50 DRR 12-1537 8/30/123.7-16 50 DRR 12-1537 8/30/123.7-17 50 DRR 12-1537 8/30/123.7-18 50 DRR 12-1537 8/30/123.7-19 50 DRR 12-1537 8/30/123.7-20 50 DRR 12-1537 8/30/123.7-21 50 DRR 12-1537 8/30/123.7-22 50 DRR 12-1537 8/30/123.7-23 50 DRR 12-1537 8/30/123.7-24 50 DRR 12-1537 8/30/123.7-25 50 DRR 12-1537 8/30/123.7-26 50 DRR 12-1537 8/30/123.7-27 50 DRR 12-1537 8/30/123.7-28 50 DRR 12-1537 8/30/123.7-29 50 DRR 12-1537 8/30/123.7-30 50 DRR 12-1537 8/30/123.7-31 50 DRR 12-1537 8/30/123.7-32 50 DRR 12-1537 8/30/123.7-33 50 DRR 12-1537 8/30/123.7-34 50 DRR 12-1537 8/30/123.7-35 50 DRR 12-1537 8/30/123.7-36 50 DRR 12-1537 8/30/123.7-37 54 DRR 13-2529 10/25/133.7-38 54 DRR 13-2529 10/25/13

TAB - 3.8 ELECTRICAL POWER SYSTEMS3.8-1 47 DRR 11-2404 11/16/113.8-2 47 DRR 11-2404 11/16/113.8-3 47 DRR 11-2404 11/16/113.8-4 47 DRR 11-2404 11/16/113.8-5 47 DRR 11-2404 11/16/11

TAB- 3.9 REFUELING OPERATIONS3.9-1 3 DRR 99-1581 12/18/993.9-2 41 DRR 10-1702 10/1/103.9-3 41 DRR 10-1702 10/1/10

TAB - 3.10 EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORING3.10-1 3 DRR 99-15813.10-2 37 DRR 09-02873.10-3 37 DRR 09-02873.10-4 3 DRR 99-15813.10-5 37 DRR 09-02873.10-6 3 DRR 99-1581

12/18/993/20/093/20/0912/18/993/20/0912/18/99

Wolf Creek - Unit 1 iii Revision 57



TAB - 5.0 ADMINISTRATIVE CONTROLS5.0-1 51 DRR 13-0371 2/26/135.0-2 57 DRR 14-1878 9/30/145.0-3 24 DRR 05-1376 6/28/055.0-4 41 DRR 10-1702 10/1/105.0-5 17 DRR 04-0452 9/28/055.0-6 25 DRR 05-1996 2/16/055.0-7 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 tobe issued by Document Control.

Wolf Creek - Unit 1 iv Revision 57

Boration Injection System - OperatingTR B 3.1.9

BASES

TECHNICALSURVEILLANCEREQUIREMENTS

TSR 3.1.9.2 (continued)

unusable volume. The combined BAT boron solution volume may becontained in one or both of the BATs. If one BAT meets the minimumboron solution volume requirement, that BAT is the only boron solutionsource required for the associated boration injection subsystem to beconsidered FUNCTIONAL. If both BATs are necessary to meet theminimum boron solution volume requirement, both BATs are required tobe FUNCTIONAL for the associated boration injection subsystem to beconsidered FUNCTIONAL.

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

TSR 3.1.9.3

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

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

TSR 3.1.9.4

Verifying the correct-alignment for each boration injection subsystemmanual, power operated, and automatic valve provides assurance that theproper flow paths exist for boration injection subsystem operation. ThisTSR 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 - ShutdownTR B 3.1.10

BASES

TECHNICALSURVEILLANCEREQUIREMENTS

TSR 3.1.10.2

This surveillance requires verification every 7 days that the RWST boronsolution volume is at least 394,000 gallons or the combined boron solutionvolume of the BATs is at least 17,658 gallons in MODE 4. The maximumexpected boron injection capability requirement value of 17,658 gallons iscalculated based on blending the concentrated boric acid solution withreactor makeup water, assuming offsite power, to form the final boronconcentration required for the RCS. In MODE 5 or 6, the minimumrequired boron solution volume of the RWST is 55,416 gallons or therequired BAT volume is 2,968 gallons. The minimum boron solutionvolume, along with the boron solution concentration requirements, ensurecold shutdown boron weight is available for injection (i.e., SDM equivalentto 1.3% Ak/k at 2000 F). The boron solution volume limit of the RWSTensures 83,754 gallons are available to inject the required cold shutdownboron weight in MODE 4 and 14,071 gallons are available to inject therequired cold shutdown boron weight in MODES 5 and 6. The boronsolution volume limits of the RWST include any unusable volume. Thecombined BAT boron solution volume may be contained in one or both ofthe BATs. If one BAT meets the minimum boron solution volumerequirement, that BAT is the only boron solution source required for theassociated boration injection subsystem to be considered FUNCTIONAL.If both BATs are necessary to meet the minimum boron solution volumerequirement, both BATs are required to be FUNCTIONAL for theassociated boration injection subsystem to be considered FUNCTIONAL.

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

TSR 3.1.10.7

Each required RHR suction relief valve shall be demonstratedFUNCTIONAL by verifying its RHR suction isolation valves are open. ThisSurveillance is only required to be performed if the RHR suction reliefvalve is being used to meet this TR.

The RHR suction isolation valves are verified to be opened every 72hours. The Frequency is considered adequate in view of otheradministrative controls such as valve status indications available to theoperator in the control room that verify the RHR suction isolation valvesare open.


CCW System InstrumentationTR 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 systemthat provides cooling water to selected Engineered Safety Features (ESF)components. The CCW System also contains another cooling watersupply loop, which is common to, but isolable from, both trains. This loopprovides a means of heat rejection for other non-essential equipmentfrom various reactor support systems (Ref. 1).

The non-essential CCW System loads which are shed include the PostAccident Sampling System (PASS) Cooling System, Nuclear SampleCooling System, and the Radwaste Building loads, which supply coolingwater to the various evaporators, recombiners, and waste gascompressors. Isolation of the PASS Cooling System is accomplishedthrough the closing of the series isolation supply valves EG HV-72 andEG HV-73 and the closing of the series isolation return valves EG HV-74and EG HV-75. Isolation of the Nuclear Sample Cooling System and theRadwaste Building loads is accomplished through the closing of theseries isolation supply valve EG HV-69A and EG HV-70A and the closingof the series isolation return valves EG HV-69B and EG HV-70B. Theprimary isolation signal, which isolates the non-essential CCW Systemloads, is a Safety Injection Signal (SIS).

This TR covers instrumentation associated with level switchesEGLSLL0001 and EGLSLL0002 and their instrumentation. Thisinstrumentation provides backup automatic isolation of the non-essentialCCW System loads.

CCW System and CCW System actuation instrumentation OPERABILITYrequirements regarding the intended support function of safety relatedsystems are specified in Technical Specifications LCO 3.3.2, "EngineeredSafety Feature Actuation System (ESFAS) Instrumentation," andLCO 3.7.7, "Component Cooling Water (CCW) System," and associatedBases (Refs. 2 and 3).

APPLICABLE The design basis of the CCW System is for one CCW train to removeSAFETY ANALYSES the heat from components important to mitigating the consequences of a

loss-of-coolant-accident (LOCA) or a main steam line break (MSLB) andtransfer the heat to the Essential Service Water System.



BASES

APPLICABLE The accomplishment of these functions are provided through theSAFETY 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 thisTR 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 aseismically induced pipe break or crack or a non-mechanistic malfunctionin the moderate energy piping, no SIS would be generated for theautomatic isolation of the non-safety related radwaste service loads (viaclosure of valves EGHV0069A/B and EGHV0070A/B). For such anevent, the low-low level signal from the CCW surge tank level channels(initiated by transmitters EGLT0001 and EGLT0002) will isolate theradwaste service loads.

TR This TR requires that the instrumentation associated with the automaticisolation of the CCW System from non-safety related heat loads areFUNCTIONAL. For the CCW System instrumentation to be consideredFUNCTIONAL, the surge tank low level instrumentation must be capableof automatically isolating the Radwaste System, the PASS coolers, andthe Nuclear Sample Cooling System loads upon receipt of a surge tanklow level signal.

APPLICABILITY The CCW System instrumentation associated with this TR is required tobe FUNCTIONAL in MODES 1, 2, 3, and 4 when non-essential loads arebeing supplied by the associated CCW train since the CCW System isrequired to perform its safety function in MODES 1, 2, 3, and 4. TheCCW instrumentation associated with this TR is not required to beFUNCTIONAL in MODES 1, 2, 3, and 4 when the non-essential loads areisolated from the associated CCW train since the required function isperformed.

ACTIONS A.1

This Required Action provides direction to restore the inoperable CCWSystem instrumentation to FUNCTIONAL status. The Completion Time isconsidered a reasonable time to repair the equipment and is consistentwith the allowable outage time for an inoperable CCW train per TechnicalSpecification 3.7.7.



BASES

ACTIONS B..1(continued)

If the Required Action cannot be performed within the associatedCompletion Time, Required Action B.1 requires initiation of a ConditionReport (CR) immediately. As part of the initiation of the CR, action shallbe implemented in a timely manner to place the unit in a safe condition asdetermined by plant management. The CR should provide an accuratedescription of the problem, the Required Action and associatedCompletion Time not complied with. The intent of this Required Action isto utilize the corrective action program to assure prompt attention andadequate management oversight to minimize the additional time thechannel is nonfunctional.

TECHNICAL TSR 3.7.7.1SURVEILLANCEREQUIRMENTS 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 arecapable of performing their design functions upon the initiation of asimulated or actual actuation signal. The Frequency of 184 days isreasonable, based on plant-specific operating experience, instrumentreliability, 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 thesystem, assures that the channels will respond, within the required rangeand accuracy necessary for the continued FUNCTIONALITY of the circuit.The CHANNEL CALIBRATION must include all devices up to andincluding the associated automatic valves to provide complete testing ofthe required function. The 18 month Frequency is based upon the needto perform this TSR under conditions that apply during a unit outage andthe potential for an unplanned transient if the TSR were performed withthe reactor at power. However, individual valves may be tested duringpower operation under appropriate administrative controls, and if anactual actuation occurs during operation credit may be taken forautomatic operation of valves. Operating experience has shown thatthese components usually pass the TSR when performed at the 18 monthFrequency. Therefore, the Frequency is acceptable from a reliabilitystandpoint.

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

SnubbersTR B 3.7.20

BASES

TECHNICAL Surveillance Testing is performed in accordance with the applicableSURVEILLANCE requirements of ASME Section XI, "Rules for Inservice Inspection ofREQUIREMENTS 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 proposedalternative to use TRM, Section 3.7.20, for snubber visual inspection andfunctional testing in lieu of the applicable ASME Code requirementsspecified in Section Xl, Article IWF-5000 for the third 10-year inserviceinspection interval. The NRC safety evaluation specifies that changes tothe TRM snubber visual inspection and functional testing requirementsshall be submitted to the NRC for authorization pursuant to 10 CFR50.55a(a)(3) or as an exemption pursuant to 10 CFR 50.12.

Permanent or other exemptions from the surveillance program forindividual snubbers may be granted by the Commission if a justifiablebasis for exemption is presented and, if applicable, snubber lifedestructive testing was performed to qualify the snubber for the applicabledesign conditions at either the completion of their fabrication or at asubsequent date. Snubbers so exempted shall be listed in the list ofindividual snubbers indicating the extent of the exemptions.

In order to establish the inspection frequency for each type of snubber ona safety related system, it was assumed that the frequency of snubberfailures and initiating events is constant with time and that the failure ofany snubber could cause the system to be unprotected and to result infailure during an assumed initiating event. Inspections performed beforethat interval has elapsed may be used as a new reference point todetermine the next inspection. However, the results of such earlyinspections performed before the original required time interval haselapsed (nominal time less 25%) may not be used to lengthen therequired inspection interval. Any inspection whose results require ashorter 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 inTable TR 3.7.20-5. A pre-fuel load visual inspection and functional testhas been performed on each snubber using the acceptance criteria listedin Table TR 3.7.20-2. The baseline takes into account that the snubbershave experienced thermal cycling and normal operating service as aresult of previous hot functional testing. The initial inservice inspectionhas been performed on the snubbers prior to completion of the first


SnubbersTR B 3.7.20

BASES

TECHNICAL TSR 3.7.20.1 (continued)SURVEILLANCEREQUIREMENTS refueling outage. The frequency of subsequent surveillances depends on

the number of snubbers found nonfunctional from each previousinspection as provided in Table TR 3.7.20-3 and the Inservice InspectionProgram as described in TR 5.5.6.

The acceptance criteria and corrective actions are listed in Table TR3.7.20-2.

The visual inspections are designed to detect obvious indications ofnonfunctionality of the snubbers. Removal of insulation or direct contactwith the snubbers is not required initially. However, suspected causes ofnonfunctionality are to be investigated and all snubbers of the same typeand all snubbers subjected to the same failure mode are to be inspectedmore frequently.

The visual inspection frequency is based upon maintaining a constantlevel of snubber protection during an earthquake or severe transient andthe number of unacceptable snubbers found during the previousinspection. As a result, the required inspection intervals vary inverselywith the number of nonfunctional snubbers found during an inspection. Ifa snubber fails the visual acceptance criteria, the snubber is declaredunacceptable and cannot be declared FUNCTIONAL via functionaltesting. However, if the cause of rejection is understood and remedied forthat type of snubber and for any other type of snubbers that may begenerically susceptible and FUNCTIONALITY verified by testing, thatsnubber may be reclassified acceptable for the purpose of establishingthe next surveillance interval.

Snubbers may be categorized according to accessibility as noted in theNotes to Table TR 3.7.20-3. The accessibility of each snubber isdetermined based on radiation level as well as other factors such astemperature, atmosphere, location, etc. The recommendations ofRegulatory Guide 8.8, "Information Relevant to Maintaining OccupationalRadiation Exposure as Low a Practicable," (Ref. 7) and Regulatory Guide8.10, "Operation Philosophy for Maintaining Occupational RadiationExposure as Low as Practicable," (Ref. 8) are considered in planning andimplementing the visual inspection program.

Since the visual inspections are augmented by a functional testingprogram, the visual inspection need not be a hands on inspection, butshall require visual scrutiny sufficient to assure that fasteners ormountings for connecting the snubbers to supports or foundations haveno visible bolts, pins or fasteners missing, or other visible signs ofphysical damage such as cracking or loosening.

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

SnubbersTR B 3.7.20

BASES

TECHNICAL TSR 3.7.20.2SURVEILLANCEREQUIREMENTS 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 TableTR 3.7.20-5. The testing for these snubbers have been separated intotwo 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. Sampleplan 1 .b. (Figure TR 3.7.20-1) is typically used for snubbers with largepopulation. Figure TR 3.7.20-1 was developed using "Wald's SequentialProbability Ratio Plan" as described in "Quality Control and IndustrialStatistics" by Acheson J. Duncan.

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

Snubber functional testing is performed to the requirements of TableTR 3.7.20-4 and performed prior to the completion of each refuelingoutage. The once each refueling Frequency, in conjunction with the Note,is based on the need to perform this surveillance under the conditionsthat 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 inaccordance with the Snubber Service Life Program described in TR 5.5.5.The requirement to monitor the snubber service life is included to ensurethat the snubbers periodically undergo a performance evaluation in viewof their age and operating conditions.

TSR 3.7.20.4

If the plant has experienced an unexpected, potentially damagingsnubber transient, an inspection per Table TR 3.7.20-1 is performed onall snubbers attached to sections of systems that have experienced thetransient. The potential impact of the transient is assessed by reviewingoperating data and by visually inspecting the associated system. Inaddition to the visual inspection, the freedom-of-motion of the mechanicalsnubber(s) is verified per Table TR 3.7.20-1.


SnubbersTR 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 MaintainingOccupational Radiation Exposure as Low as Practicable."

9. WCAP-11618, "MERITS Program-Phase II, Task 5, CriteriaApplication," including Addendum 1 dated April, 1989, Section3.7.9.

10. NRC letter (D. Terao to R. Muench) dated June 2, 2006, "WolfCreek Generating Station - Relief Request 13R-03 for the Third10-Year Interval Inservice Inspection and Examination ofSnubbers (TAC NO. MC8571)."

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


LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENT MANUAL BASES


TAB - Table of Contents43 DRR 10-3738 12/28/10

ii 25 DRR 05-1996 9/28/05iii 54 DRR 13-2529 10/25/13

TAB - B 3.0 APPLICABILTYB 3.0-1 41 DRR 10-1702 10/1/10B 3.0-2 41 DRR 10-1702 10/1/10B 3.0-3 41 DRR 10-1702 10/1/10B 3.0-4 41 DRR 10-1702 10/1/10B 3.0-5 41 DRR 10-1702 10/1/10B 3.0-6 41 DRR 10-1702 10/1/10B 3.0-7 41 DRR 10-1702 10/1/10B 3.0-8 41 DRR 10-1702 10/1/10B 3.0-9 41 DRR 10-1702 10/1/10B 3.0-10 41 DRR 10-1702 10/1/10B 3.0-11 41 DRR 10-1702 10/1/10B 3.0-12 41 DRR 10-1702 10/1/10B 3.0-13 41 DRR 10-1702 10/1/10B 3.0-14 20 DRR 04-1410 10/7/04

TAB - B 3.1 REACTIVITY CONTROL SYSTEMSB 3.1.7-1 41 DRR 10-1702 10/1/10B 3.1.7-2 41 DRR 10-1702 10/1/10B 3.1.7-3 3 DRR 99-1581 12/18/99B 3.1.8-1 41 DRR 10-1702 10/1/10B 3.1.8-2 41 DRR 10-1702 10/1/10B 3.1.9-1 15 DRR 03-0861 7/10/03B 3.1.9-2 41 DRR 10-1702 10/1/10B 3.1.9-3 41 DRR 10-1702 10/1/10B 3.1.9-4 41 DRR 10-1702 10/1/10B 3.1.9-5 41 DRR 10-1702 10/1/10B 3.1.9-6 55 DRR 14-0344 2/27/14B 3.1.9-7 28 DRR 06-1349 7/24/06B 3.1.9-8 3 DRR 99-1581 12/18/99B 3.1.10-1 41 DRR 10-1702 10/1/10B 3.1.10-2 49 DRR 12-0674 4/10/12B 3.1.10-3 48 DRR 12-0266 2/2/12B 3.1.10-4 55 DRR 14-0344 2/27/14B 3.1.10-5 48 DRR 12-0266 2/2/12

TAB - B 3.3 INSTRUMENTATIONB 3.3.3-1 4B 3.3.3-2 4B 3.3.3-3 4B 3.3.3-4 4B 3.3.3-5 4B 3.3.3-6 2B 3.3.9-1 4B 3.3.9-2 4B 3.3.9-3 4

1.*1.1.1

.8

.111*l

DRR 10-1702DRR 10-1702DRR 10-1702DRR 10-1702DRR 10-1702DRR 06-1349DRR 10-1702DRR 10-1702DRR 10-1702

10/1/1010/1/1010/1/1010/1/1010/1/107/24/0610/1/1010/1/1010/1/10

Wolf Creek - Unit 1 Revision 58


PAGE (1) REVISION NO. (2) CHANGE DOCUMENT (3) DATE EFFECTIVE/

IMPLEMENTED (4)

TAB - B 3.3 INSTRUMENTATION (continued)B 3.3.9-4 8B 3.3.10-1 3B 3.3.10-2 41B 3.3.10-3 41B 3.3.11-1 41B 3.3.11-2 41B 3.3.11-3 41B 3.3.11-4 41B 3.3.11-5 39B 3.3.12-1 41B 3.3.12-2 37B 3.3.12-3 19B 3.3.13-1 41B 3.3.13-2 41B 3.3.13-3 41B 3.3.13-4 3B 3.3.14-1 51B 3.3.14-2 51B 3.3.14-3 53B 3.3.14-4 53B 3.3.14-5 51B 3.3.14-6 53B 3.3.14-7 51B 3.3.14-8 51B 3.3.14-9 51B 3.3.14-10 51B 3.3.14-11 51B 3.3.15-1 45B 3.3.15-2 45B 3.3.15-3 46B 3.3.15-4 45B 3.3.15-5 45B 3.3.16-1 41B 3.3.16-2 41B 3.3.16-3 41B 3.3.16-4 41B 3.3.16-5 41B 3.3.17-1 19B 3.3.17-2 41B 3.3.17-3 41B 3.3.17-4 41B 3.3.17-5 3B 3.3.18-1 14B 3.3.18-2 41B 3.3.18-3 49B 3.3.18-4 49B 3.3.18-5 49B 3.3.18-6 49B 3.3.18-7 49B 3.3.19-1 43B 3.3.19-2 43

DRR 01-0475DRR 99-1581DRR 10-1702DRR 10-1702DRR 10-1702DRR 10-1702DRR 10-1702DRR 10-1702DRR 09-1775DRR 10-1702DRR 09-0287DRR 04-1019DRR 10-1702DRR 10-1702DRR 10-1702DRR 99-1581DRR 13-0371DRR 13-0371DRR 13-1518DRR 13-1518DRR 13-0371DRR 13-1518DRR 13-0371DRR 13-0371DRR 13-0371DRR 13-0371DRR 13-0371DRR 11-0662DRR 11-0662DRR 11-0725DRR 11-0662DRR 11-0662DRR 10-1702DRR 10-1702DRR 10-1702DRR 10-1702DRR 10-1702DRR 04-1019DRR 10-1702DRR 10-1702DRR 10-1702DRR 99-1581DRR 02-1459DRR 10-1702DRR 12-0673DRR 12-0673DRR 12-0673DRR 12-0673DRR 12-0673DRR 10-3738DRR 10-3738

5/1/0112/18/9910/1/1010/1/1010/1/1010/1/1010/1/1010/1/1010/28/0910/1/103/20/099/1/0410/1/1010/1/1010/1/1012/18/992/26/132/26/136/26/136/26/132/26/136/26/132/26/132/26/132/26/132/26/132/26/133/21/113/21/114/11/113/21/113/21/1110/1/1010/1/1010/1/1010/1/1010/1/109/1/0410/1/1010/1/1010/1/10

12/18/992/12/0310/1/104/10/124/10/124/10/124/10/124/10/1212/28/1012/28/10

Wolf Creek - Unit 1 ii Revision 58



TAB - B 3.3 INSTRUMENTATION (continued)B 3.3.19-3 43 DRR 10-3738 12/28/10B 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 2/28/02B 3.4.3-2 10 DRR 02-0122 2/28/02B 3.4.3-3 41 DRR 10-1702 10/1/10B 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 10/1/10B 3.4.10-2 41 DRR 10-1702 10/1/10B 3.4.16-1 3 DRR 99-1581 12/18/99B 3.4.16-2 41 DRR 10-1702 10/1/10B 3.4.16-3 33 DRR 07-1554 9/28/07B 3.4.17-1 41 DRR 10-1702 10/1/10B 3.4.17-2 35 DRR 08-0729 8/28/08B 3.4.17-3 41 DRR 10-1702 10/1/10B 3.4.17-4 35 DRR 08-0729 8/28/08B 3.4.17-5 41 DRR 10-1702 10/1/10B 3.4.17-6 41 DRR 10-1702 10/1/10B 3.4.17-7 41 DRR 10-1702 10/1/10B 3.4.17-8 41 DRR 10-1702 10/1/10B 3.4.17-9 41 DRR 10-1702 10/1/10B 3.4.18-1 3 DRR 99-1581 12/18/99B 3.4.18-2 41 DRR 10-1702 10/1/10B 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 12/18/99B 3.5.1-2 41 DRR 10-1702 10/1/10B 3.5.1-3 3 DRR 99-1581 12/18/99

TAB - B 3.6 CONTAINMENT SYSTEMSB 3.6.1-1 38 DRR 09-1010 7/16/09B 3.6.1-2 41 DRR 10-1702 10/1/10B 3.6.1-3 41 DRR 10-1702 10/1/10B 3.6.1-4 41 DRR 10-1702 10/1/10B 3.6.1-5 37 DRR 09-0287 3/20/09B 3.6.1-6 17 DRR 04-0452 5/26/04B 3.6.1-7 36 DRR 08-1845 12/9/08

TAB - B 3.7 PLANT SYSTEMSB 3.7.7-1B 3.7.7-2B 3.7.7-3B 3.7.7-4B 3.7.8-1

5757588

41

DRR 14-1878DRR 14-1878DRR 14-2330DRR 01-0475DRR 10-1702

9/30/149/30/1411/6/145/1/01

10/1/10

Wolf Creek - Unit 1 iii Revision 58



TAB - B 3.7 PLANT SYSTEMS (continued)B 3.7.8-2 52B 3.7.8-3 52B 3.7.13-1 41B 3.7.13-2 41B 3.7.13-3 41B 3.7.17-1 26B 3.7.17-2 41B 3.7.17-3 26B 3.7.19-1 5B 3.7.19-2 37B 3.7.19-3 5B 3.7.20-1 3B 3.7.20-2 50B 3.7.20-3 50B 3.7.20-4 50B 3.7.20-5 50B 3.7.20-6 50B 3.7.20-7 50B 3.7.20-8 56B 3.7.20-9 56B 3.7.20-10 56B 3.7.20-11 50B 3.7.20-12 56B 3.7.21-1 3B 3.7.21-2 37B 3.7.21-3 3B 3.7.21-4 3B 3.7.22-1 3B 3.7.22-2 41B 3.7.22-3 49B 3.7.24-1 41B 3.7.24-2 41B 3.7.24-3 44B 3.7.24-4 41B 3.7.24.5 37B 3.7.24-6 21

DRR 13-0658DRR 13-0658DRR 10-1702DRR 10-1702DRR 10-1702DRR 06-0050DRR 10-1702DRR 06-0050DRR 00-0958DRR 09-0287DRR 00-0958DRR 99-1581DRR 12-1537DRR 12-1537DRR 12-1537DRR 12-1537DRR 12-1537DRR 12-1537DRR 14-1570DRR 14-1570DRR 14-1570DRR 12-1537DRR 14-1570DRR 99-1581DRR 09-0287DRR 99-1581DRR 99-1581DRR 99-1581DRR 10-1702DRR 12-064

DRR 10-1702DRR 10-1702DRR 11-0496DRR 10-1702DRR 09-0287DRR 04-1535

3/28/133/28/1310/1/1010/1/1010/1/102/28/0610/1/102/28/068/17/003/20/0912/18/9912/18/998/30/128/30/128/30/128/30/128/30/128/30/127/1/147/1/147/1/14

8/30/127/1/14

12/18/993/20/09

12/18/9912/18/9912/18/9910/1/104/10/1210/1/1010/1/103/9/11

10/1/103/20/0912/1/04

TAB - B 3.8 ELECTRICAL POWER SYSTEMSB 3.8.1-1 47B 3.8.1-2 47B 3.8.1-3 47B 3.8.11-1 3B 3.8.11-2 41B 3.8.11-3 41B 3.8.11-4 54B 3.8.11-5 41B 3.8.11-6 41

DRR 11-2404DRR 11-2404DRR 11-2404DRR 99-1581DRR 10-1702DRR 10-1702DRR 13-2529DRR 10-1702DRR 10-1702

11/16/1111/16/1111/16/1112/18/9910/1/1010/1/10

10/25/1310/1/1010/1/10

Wolf Creek - UnIt 1 iv Revision 58



TAB - B 3.9 REFUELING OPERATIONSB 3.9.7-1 3 DRR 99-1581 12/18/99B 3.9.7-2 3 DRR 99-1581 12/18/99B 3.9.9-1 41 DRR 10-1702 10/1/10B 3.9.9-2 41 DRR 10-1702 10/1/10B 3.9.9-3 17 DRR 04-0452 5/26/04

TAB - B 3.10 EXPLOSIVE GAS AND STORAGE TANK RADIOACTIVITY MONITORINGB 3.10.1-1 3 DRR 99-1581 12/18/99B 3.10.1-2 37 DRR 09-0287 3/20/09B 3.10.1-3 3 DRR 99-1581 12/18/99B 3.10.2-1 3 DRR 99-1581 12/18/99B 3.10.2-2 37 DRR 09-0287 3/20/09B 3.10.2-3 41 DRR 10-1702 10/1/10B 3.10.3-1 3 DRR 99-1581 12/18/99B 3.10.3-2 37 DRR 09-0287 3/20/09B 3.10.3-3 37 DRR 09-0287 3/20/09B 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, thechange 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 pagesare issued by Document Control.

Wolf Creek - Unit 1 V Revision58

wolf creek generating station updated safety analysis ... · subject: docket no. 50-482: revision...

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