ULNRC-05808, Facility Operating License NPF-30, License Amendment Application Supplement for a Technical Specification Change That Would Relocate Specific Surveillance Frequencies to a Licensee Controlled Program (LDCN 10-0020)

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Facility Operating License NPF-30, License Amendment Application Supplement for a Technical Specification Change That Would Relocate Specific Surveillance Frequencies to a Licensee Controlled Program (LDCN 10-0020)
ML112061672
Person / Time
Site: Callaway Ameren icon.png
Issue date: 07/25/2011
From: Graessle L
Ameren Missouri
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME4506, ULNRC-05808, LDCN 10-0020
Download: ML112061672 (14)
v • d • e


Text

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WAmeren MISSOURI Callaway Plant July 25, 2011 ULNRC-05808 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Ladies and Gentlemen:

10 CFR 50.90 DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.

FACILITY OPERATING LICENSE NPF-30 LICENSE AMENDMENT APPLICATION SUPPLEMENT FOR A TECHNICAL SPECIFICATION CHANGE THAT WOULD RELOCATE SPECIFIC SURVEILLANCE FREQUENCIES TO A LICENSEE CONTROLLED PROGRAM (LDCN 10-0020) (TAC NO. ME4506)

Reference:

1. AmerenUE Letter (ULNRC-05725) dated August 5, 2010
2. Ameren Missouri Letter (ULNRC-05762) dated March 23,2011
3. Ameren Missouri Letter (ULNRC-05779) dated May 3, 2011 In letter ULNRC-05725 (Reference 1), Union Electric Company (dba Ameren Missouri) submitted an application for amendment to Facility Operating License Number NPF-30 for the Callaway Plant. The proposed amendment would modify Callaway Plant Unit 1 Technical Specifications (TS) by relocating specific surveillance frequencies to a licensee-controlled program consistent with Nuclear Energy Institute (NEI) 04-10, "Risk-Informed Technical Specification Initiative 5b, Risk-Informed Method for Control of Surveillance Frequencies." The amendment application was supplemented by Ameren Missouri letters ULNRC-05762 and ULNRC-05779 (References 2 and 3, respectively).

Recently, during creation of the final amendment pages, several administrative changes were identified to the Table of Contents (TOC) for the TS, which were not included in the license amendment request.

These changes were due to pagination changes associated with the incorporation of changes and/or additional text into the TS such that some of the page numbers listed on the TOC were affected.

This supplement to Ameren Missouri's amendment request is therefore being provided to include the changes required to the TOC for the TS. Accordingly, Attachment 1 contains a markup of the TOC changes now being requested, Attachment 2 contains the retyped TOC reflecting these changes.

PO Box 620 Fulton, MO 65251 AmerenMissouri.com

ULNRC-05808 July 25, 2011 Page 2 It should be noted that the conclusions of the No Significant Hazards Consideration determination provided in the original submittal are not altered by the additional information provided in this letter.

If there are any questions, please contact Mr. Tom Elwood at (314) 225-1905. This letter does not contain new commitments.

I declare under penalty of perjury that the foregoing is true and correct.

Sincerely, Executed on: 7-.l-S -.J 0 ( I Luke H. Graessle Director, Operations Support BFHlnls - Proposed Technical Specification Table of Contents Changes (Mark-Up) - Retyped Technical Specification Table of Contents Pages

ULNRC-05808 July 25, 2011 Page 3 cc:

U.S. Nuclear Regulatory Commission (Original and 1 copy)

Attn: Document Control Desk Washington, DC 20555-0001 Mr. Elmo E. Collins, Jr.

Regional Administrator U.S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. Mohan C. Thadani (2 copies)

Senior Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8G 14 Washington, DC 20555-2738 Mr. James Polickoski Project Manager, Callaway Plant Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 0-8B 1 A Washington, DC 20555-2738

ULNRC-05808 July 25,2011 Page 4 Index and send hardcopy to QA File A160.0761 Hardcopy:

Certrec Corporation 4200 South Hulen, Suite 422 Fort Worth, TX 76109 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)

Electronic distribution for the following can be made via Tech Spec ULNRC Distribution:

A. C. Heflin F. M. Diya C. O. Reasoner III L. H. Graessle S. A. Maglio S. L. Gallagher NSRB Secretary T. B. Elwood Ms. Diane M. Hooper (WCNOC)

Mr. Tim Hope (Luminant Power)

Mr. Ron Barnes (APS)

Mr. Tom Baldwin (pG&E)

Mr. Wayne Harrison (STPNOC)

Ms. Linda Conklin (SCE)

Mr. John O'Neill (pillsbury Winthrop Shaw Pittman LLP)

Missouri Public Service Commission Mr. Dru Buntin (DNR)

ULNRC-05808 Proposed Technical Specification Table of Contents Changes (Mark-Up)

TABLE OF CONTENTS 1.0 USE AND APPLICATION........................................................................ 1.1-1 1.1 Definitions.......................................................................................... 1.1-1 1.2 Logical Connectors............................................................................ 1.2-1 1.3 Completion Times.............................................................................. 1.3-1 1.4 Frequency.......................................................................................... 1.4-1 2.0 SAFETY LIMITS (SLs).......................................................................... 2.0-1 2.1 SLs................................................................................................... 2.0-1 2.2 SL Violations.................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY..... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS..................................................... 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM)........................................................ 3.1-1 3.1.2 Core Reactivity

............................................................................... 3.1-2 3.1.3 Moderator Temperature Coefficient (MTC)...................................... 3.1-4 3.1.4 Rod Group Alignment Limits............................................................ 3.1-7 3.1.5 Shutdown Bank Insertion Limits

..................................................... 3.1-11 3.1.6 Control Bank Insertion Limits........................................................... 3.1-13 3.1.7 Rod Position Indication.................................................................... 3.1-16 3.1.8 PHYSICS TESTS Exceptions - MODE 2........................................ 3.1-19 3.1.9 RCS Boron Limitations < 500°F....................................................... 3.1-21 3.2 POWER DISTRIBUTION LIMITS

......................................................... 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fa(Z))

(Fa Methodology)...................................................................... 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor

................................... 3.2-6 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology).................................................. 3.2-9 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

................................... 3.2-10 3.3 INSTRUMENTATION............................................................................ 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation................................... 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

~

Instrumentation.........................................................................

3.3-27 3.3.3 Post Accident Monitoring (PAM) Instrumentation........................... ~

3.3-51 3.3.4 Remote Shutdown System

............................................................ ~

3.3-56 CALLAWAY PLANT 1

Amendment 197

TABLE OF CONTENTS 3.3 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12 3.4.13 3.4.14 3.4.15 3.4.16 3.4.17 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 3.6 3.6.1 3.6.2 3.6.3 INSTRUMENTATION (continued)

Loss of Power (LOP) Diesel Generator (DG) Start In~trumentation.................................. :....................................... ~

.;~~~ 1 Containment Purge Isolation Instrumentation................................ ~

Control Room Emergency Ventilation System (CREVS)

Actuation Instrumentation

........................................................ ~

3.3-67 I Emergency Exhaust System (EES) Actuation Instrumentation

........................................................................ ~

3.3-731 Boron Dilution Mitigation System (BDMS)

..................................... ~

3.3-79 REACTOR COOLANT SYSTEM (RCS)................................................ 3.4-1 RCSPressure, Temperature, and Flow Departure from Nucleate Boiling (ON B) Limits................................................... 3.4-1 RCS Minimum Temperature for Criticality....................................... 3.4-3 RCS Pressure and Temperature (PIT) Limits.................................. 3.4-4 RCS Loops - MODES 1 and 2......................................................... 3.4-6 RCS Loops - MODE 3..................................................................... 3.4-7 RCS Loops - MODE 4..................................................................... 3.4-10 RCS Loops - MODE 5, Loops Filled................................................ 3.4-12 RCS Loops - MODE 5, Loops Not Filled......................................... 3.4-15 Pressurizer....................................................................................... 3.4-17 Pressurizer Safety Valves................................................................ 3.4-19 Pressurizer Power Operated Relief Valves (PORVs)...................... 3.4-21 Cold Overpressure Mitigation System (COMS)............................... 3.4-25 RCS Operational LEAKAGE............................................................ 3.4-30 RCS Pressure Isolation Valve (PIV) Leakage

................................ 3.4-32 RCS Leakage Detection Instrumentation....................................... ~.3:--.4:---=:36~ __ _

RCS Specific Activity...................................................................... 3.4-40 Steam Generator (SG) Tube Integrity............................................. ~

3.4-43 EMERGENCY CORE COOLING SYSTEMS (ECCS).......................... 3.5-1 Accumulators.................................................................................. 3.5-1 ECCS - Operating.......................................................................... ~

3.5-4 ECCS - Shutdown........................................................................... U-e 3.5-7 Refueling Water Storage Tank (RWST)

........................................ ~

3.5-9 Seal Injection Flow.......................................................................... ~

3.5-11 CONTAINMENT SYSTEMS.................................................................. 3.6-1 Containment

................................................................................... 3.6-1 Containment Air Locks..................................................................... 3.6-3 Containment Isolation Valves

......................................................... 3.6-7 CALLAWAY PLANT 2

Amendment 197

TABLE OF CONTENTS 3.6 3.6.4 3.6.5 3.6.6 3.6.7 3.7 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 3.7.13 3.7.14 3.7.15 3.7.16 3.7.17 3.7.18 3.7.19 3.8 3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.8.9 CONTAINMENT SYSTEMS (continued)

Containment Pressure..................................................................... 3.6-16 Containment Air Temperature......................................................... 3.6-17 Containment Spray and Cooling Systems...................................... 3.6-18 Recirculation Fluid pH Control (RFPC) System............................... 3.6-21 PLANT SYSTEMS................................................................................. 3.7-1 Main Steam Safety Valves (MSSVs)............................................... 3.7-1 Main Steam Isolation Valves (MSIVs), Main Steam Isolation Valve Bypass Valves (MSIVBVs), and Main Steam Low Point Drain Isolation Valves (MSLPDIVs)

................................. 3.7-5 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs), and Main Feedwater Regulating Valve Bypass Valves (MFRVBVs).............................................. 3.7-9 Atmospheric Steam Dump Valves (ASDs)...................................... 3.7-12 Auxiliary Feedwater (AFW) System................................................. 3.7-15 Condensate Storage Tank (CST).................................................... 3.7-19 Component Cooling Water (CCW) System..................................... 3.7-21 Essential Service Water System (ESW).......................................... 3.7-23 Ultimate Heat Sink (UHS)................................................................ 3.7-26 Control Room Emergency Ventilation System (CREVS)................. 3.7-28 Control Room Air Conditioning System (CRACS)........................... 3.7-32 Not Used.......................................................................................... 3.7-35 Emergency Exhaust System (EES)................................................. 3.7-36 Not Used.......................................................................................... 3.7-39 Fuel Storage Pool Water Level........................................................ 3.7-40 Fuel Storage Pool Boron Concentration.......................................... 3.7-41 Spent Fuel Assembly Storage......................................................... 3.7-43 Secondary Specific Activity.............................................................. 3.7-45 Secondary System Isolation Valves (SSIVs)................................... 3.7-46 ELECTRICAL POWER SYSTEMS........................................................ 3.8-1 AC Sources - Operating...............................................................r

.. ">:f.1L-_ ~---""'-

AC Sources - Shutdown................................................................. ~

3.8-18 Diesel Fuel Oil, Lube Oil, and Starting Air...................................... ~

3.8-22 DC Sources - Operating................................................................. ~

3.8-25 DC Sources - Shutdown................................................................. ~

3.8-28 Battery Cell Parameters.................................................................. ~

3.8-30 Inverters - Operating....................................................................... ~

3.8-34 Inverters - Shutdown........................................................................ ~

3.8-36 Distribution Systems - Operating..................................................... ~

3.8-38 CALLAWAY PLANT 3

Amendment 199

TABLE OF CONTENTS 3.8 3.8.10 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 3.9.7 4.0 4.1 4.2 4.3 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 ELECTRICAL POWER SYSTEMS (continued)

Distribution Systems - Shutdown.................................................... ~

3.8-40 REFUELING OPERATIONS................................................................. 3.9-1 Boron Concentration....................................................................... 3.9-1 Unborated Water Source Isolation Valves...................................... 3.9-3 Nuclear Instrumentation................................................................... 3.9-5 Containment Penetrations.............................................................. 3.9-7 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level.................................................. 3.9-9 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level................................................... 3.9-11 Refueling Pool Water Level............................................................ ~3.9-14 DESIGN FEATURES...............................................................................4.0-1 Site Location.................................................................................... 4.0-1 Reactor Core................................................................................... 4.0-1 Fuel Storage....................................................................................4.0-1 ADMINISTRATIVE CONTROLS........................................................... 5.0-1 Responsibility................................................................................... 5.0-1 Organization.................................................................................... 5.0-2 Unit Staff Qualifications................................................................... 5.0-4 Procedures...................................................................................... 5.0-5 Programs and Manuals..................................................................... 5.0-6 Reporting Requirements.................................................................. 5.0-22 High Radiation Area......................................................................... 5.0-27 CALLAWAY PLANT 4

Amendment 198

VLNRC-05808 Retyped Technical Specification Table of Contents Pages

TABLE OF CONTENTS 1.0 USE AND APPLICATION........................................................................ 1.1-1 1.1 Definitions.......................................................................................... 1.1-1 1.2 Logical Connectors............................................................................ 1.2-1 1.3 Completion Times.............................................................................. 1.3-1 1.4 Frequency.......................................................................................... 1.4-1 2.0 SAFETY LIMITS (SLs).......................................................................... 2.0-1 2.1 SLs................................................................................................... 2.0-1 2.2 SL Violations.................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY..... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS..................................................... 3.1-1 3.1.1 SHUTDOWN MARGIN (SDM)........................................................ 3.1-1 3.1.2 Core Reactivity

............................................................................... 3.1-2 3.1.3 Moderator Temperature Coefficient (MTC)...................................... 3.1-4 3.1.4 Rod Group Alignment Limits...................................... :..................... 3.1-7 3.1.5 Shutdown Bank Insertion Limits

..................................................... 3.1-11 3.1.6 Control Bank Insertion Limits........................................................... 3.1-13 3.1.7 Rod Position Indication.................................................................... 3.1-16 3.1.8 PHYSICS TESTS Exceptions - MODE 2........................................ 3.1-19 3.1.9 RCS Boron Limitations < 500°F....................................................... 3.1-22 3.2 POWER DISTRIBUTION LIMITS

......................................................... 3.2-1 3.2.1 Heat Flux Hot Channel Factor (Fa(Z))

(Fa Methodology)...................................................................... 3.2-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor

................................... 3.2-6 3.2.3 AXIAL FLUX DIFFERENCE (AFD) (Relaxed Axial Offset Control (RAOC) Methodology).................................................. 3.2-9 3.2.4 QUADRANT POWER TILT RATIO (QPTR)

................................... 3.2-10 3.3 INSTRUMENTATION............................................................................ 3.3-1 3.3.1 Reactor Trip System (RTS) Instrumentation................................... 3.3-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS)

Instrumentation.......................................................................... 3.3-27 3.3.3 Post Accident Monitoring (PAM) Instrumentation............................ 3.3-51 3.3.4 Remote Shutdown System

............................................................. 3.3-56 CALLAWAY PLANT Amendment 202

TABLE OF CONTENTS 3.3 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.4 3.4.1 3.4.2 3.4.3 3.4.4 3.4.5 3.4.6 3.4.7 3.4.8 3.4.9 3.4.10 3.4.11 3.4.12 3.4.13 3.4.14 3.4.15 3.4.16 3.4.17 3.5 3.5.1 3.5.2 3.5.3 3.5.4 3.5.5 3.6 3.6.1 3.6.2 3.6.3 INSTRUMENTATION (continued)

Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.......................................................................... 3.3-59 Containment Purge Isolation Instrumentation................................. 3.3-61 Control Room Emergency Ventilation System (CREVS)

Actuation Instrumentation

......................................................... 3.3-67 Emergency Exhaust System (EES) Actuation Instrumentation

......................................................................... 3.3-73 Boron Dilution Mitigation System (BDMS)

...................................... 3.3-79 REACTOR COOLANT SYSTEM (RCS)................................................ 3.4-1 RCSPressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits................................................... 3.4-1 RCS Minimum Temperature for Criticality....................................... 3.4-3 RCS Pressure and Temperature (prr) Limits.................................. 3.4-4 RCS Loops - MODES 1 and 2......................................................... 3.4-6 RCS Loops - MODE 3..................................................................... 3.4-7 RCS Loops - MODE 4..................................................................... 3.4-10 RCS Loops - MODE 5, Loops Filled................................................ 3.4-12 RCS Loops - MODE 5, Loops Not Filled......................................... 3.4-15 Pressurizer....................................................................................... 3.4-17 Pressurizer Safety Valves................................................................ 3.4-19 Pressurizer Power Operated Relief Valves (PORVs)...................... 3.4-21 Cold Overpressure Mitigation System (COMS)............................... 3.4-25 RCS Operational LEAKAGE............................................................ 3.4-30 RCS Pressure Isolation Valve (PIV) Leakage

................................ 3.4-32 RCS Leakage Detection Instrumentation........................................ 3.4-36 RCS Specific Activity....................................................................... 3.4-40 Steam Generator (SG) Tube Integrity.............................................. 3.4-43 EMERGENCY CORE COOLING SYSTEMS (ECCS)........................... 3.5-1 Accumulators................................................................................... 3.5-1 ECCS - Operating........................................................................... 3.5-4 ECCS - Shutdown............................................................................ 3.5-7 Refueling Water Storage Tank (RWST)

......................................... 3.5-9 Seal Injection Flow........................................................................... 3.5-11 CONTAINMENT SYSTEMS.................................................................. 3.6-1 Containment

................................................................................... 3.6-1 Containment Air Locks..................................................................... 3.6-3 Containment Isolation Valves

......................................................... 3.6-7 CALLAWAY PLANT 2

Amendment 202

TABLE OF CONTENTS 3.6 3.6.4 3.6.5 3.6.6 3.6.7 3.7 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 3.7.13 3.7.14 3.7.15 3.7.16 3.7.17 3.7.18 3.7.19 3.8 3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.8.9 CONTAINMENT SYSTEMS (continued)

Containment Pressure..................................................................... 3.6-16 Containment Air Temperature......................................................... 3.6-17 Containment Spray and Cooling Systems

...................................... 3.6-18 Recirculation Fluid pH Control (RFPC) System............................... 3.6-21 PLANT SYSTEMS................................................................................. 3.7-1 Main Steam Safety Valves (MSSVs)............................................... 3.7-1 Main Steam Isolation Valves (MSIVs), Main Steam Isolation Valve Bypass Valves (MSIVBVs), and Main Steam Low Point Drain Isolation Valves (MSLPDIVs)................................. 3.7-5 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulating Valves (MFRVs), and Main Feedwater Regulating Valve Bypass Valves (MFRVBVs).............................................. 3.7-9 Atmospheric Steam Dump Valves (ASDs)...................................... 3.7-12 Auxiliary Feedwater (AFW) System................................................. 3.7-15 Condensate Storage Tank (CST).................................................... 3.7-19 Component Cooling Water (CCW) System..................................... 3.7-21 Essential Service Water System (ESW).......................................... 3.7 -23 Ultimate Heat Sink (UHS)................................................................ 3.7-26 Control Room Emergency Ventilation System (CREVS)................. 3.7-28 Control Room Air Conditioning System (CRACS)........................... 3.7-32 Not Used.......................................................................................... 3.7-35 Emergency Exhaust System (EES)................................................. 3.7-36 Not Used.......................................................................................... 3.7-39 Fuel Storage Pool Water Level........................................................ 3.7-40 Fuel Storage Pool Boron Concentration.......................................... 3.7-41 Spent Fuel Assembly Storage......................................................... 3.7-43 Secondary Specific Activity.............................................................. 3.7-45 Secondary System Isolation Valves (SSIVs)................................... 3.7-46 ELECTRICAL POWER SYSTEMS........................................................ 3.8-1 AC Sources - Operating................................................................... 3.8-1 AC Sources - Shutdown.................................................................. 3.8-18 Diesel Fuel Oil, Lube Oil, and Starting Air....................................... 3.8-22 DC Sources - Operating.................................................................. 3.8-25 DC Sources - Shutdown.................................................................. 3.8-28 Battery Cell Parameters................................................................... 3.8-30 Inverters - Operating........................................................................ 3.8-34 Inverters - Shutdown........................................................................ 3.8-36 Distribution Systems - Operating..................................................... 3.8-38 CALLAWAY PLANT 3

Amendment 202

TABLE OF CONTENTS 3.8 3.8.10 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 3.9.7 4.0 4.1 4.2 4.3 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 ELECTRICAL POWER SYSTEMS (continued)

Distribution Systems - Shutdown..................................................... 3.8-40 REFUELING OPERATIONS................................................................. 3.9-1 Boron Concentration........................................................................ 3.9-1 Unborated Water Source Isolation Valves....................................... 3.9-3 Nuclear Instrumentation................................................................... 3.9-5 Containment Penetrations............................................................... 3.9-7 Residual Heat Removal (RHR) and Coolant Circulation - High Water Level................................................... 3.9-9 Residual Heat Removal (RHR) and Coolant Circulation - Low Water Level.................................................... 3.9-11 Refueling Pool Water Level............................................................. 3.9-14 DESIGN FEATURES............................................................................... 4.0-1 Site Location.................................................................................... 4.0-1 Reactor Core................................................................................... 4.0-1 Fuel Storage.................................................................................... 4.0-1 ADMINISTRATIVE CONTROLS........................................................... 5.0-1 Responsibility................................................................................... 5.0-1 Organization.................................................................................... 5.0-2 Unit Staff Qualifications................................................................... 5.0-4 Procedures...................................................................................... 5.0-5 Programs and Manuals..................................................................... 5.0-6 Reporting Requirements.................................................................. 5.0-22 High Radiation Area......................................................................... 5.0-27 CALLAWAY PLANT 4

Amendment 202

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