Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr| ML20206N839 |
| Person / Time |
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| Site: |
Catawba  |
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| Issue date: |
05/04/1999 |
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| From: |
DUKE POWER CO. |
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| To: |
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| Shared Package |
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| ML20206N823 |
List: |
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| References |
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| CNEI-0400-24, CNEI-0400-24-R16, CNEI-400-24, CNEI-400-24-R16, NUDOCS 9905180085 |
| Download: ML20206N839 (9) |
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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20206N8391999-05-0404 May 1999
Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr
ML20206N8261999-04-22022 April 1999
Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included
ML20203A4041998-12-22022 December 1998
Rev 14 to CNEI-0400-24, Catawba Unit 1 Cycle 11 Colr
ML20203A4101998-12-22022 December 1998
Rev 16 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr
ML20154H0151998-10-0101 October 1998
Rev 15 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr
ML20154G9951998-08-12012 August 1998
Rev 13 to CNEI-0400-24, Catawba Unit 1 Cycle 11 Colr
ML20154H0011998-08-0606 August 1998
Rev 14 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr
ML20197E4951997-11-30030 November 1997
Rev 12 to CNEI-0400-24, Catawba Unit 1 Cycle 11 COLR for Nov 1997
ML20212E4171997-08-14014 August 1997
Rev 13 to CNEI-0400-25, Catawba,Unit 2,Cycle 9 Colr
ML20210P7851997-07-31031 July 1997
Rev 11 to CNEI-0400-24, Catawba Unit 1,Cycle 10 Colr
ML20210P8161997-07-31031 July 1997
Rev 12 to CNEI-0400-25, Catawba Unit 2,Cycle 9 Colr
ML20148S4641997-05-29029 May 1997
0 to Catawba Unit 1 Cycle 10 COLR for May 1997
ML20140E0431997-04-14014 April 1997
Cycle 9 COLR, Rev 9
ML20140E0391997-04-0909 April 1997
Cycle 9 Colr,Qa Condition 1, Rev 10
ML20137S4231997-03-18018 March 1997
Rev 8 to Catawba Unit 2 Cycle 8 Colr
ML20128M6611996-09-17017 September 1996
Cycle 8 Colr
ML20117K4981996-08-0202 August 1996
Rev 9 to Catawba Unit 1 Cycle 10 Colr
ML20093H9391995-10-17017 October 1995
Cycle 8,Core Operating Limits Rept
ML20098B0851995-09-30030 September 1995
Cycle 9,Core Operating Limits Rept, Sept 1995
ML20098B1641995-09-27027 September 1995
Cycle 7,Core Operating Limits Rept,Sept 1995,QA Condition 1
ML20084A0341995-05-22022 May 1995
Rev 3 to GGNS COLR Sr
ML20082K1561995-04-12012 April 1995
Cycle 7 Colr
ML20082K1651995-04-12012 April 1995
Cycle 9 Colr
ML20078Q4671995-02-15015 February 1995
Rev 6 to Catawba Unit 1 Cycle 9 Colr
ML20080B8791994-11-30030 November 1994
Cycle 8 Colr
ML20076K4741994-10-24024 October 1994
Rev 3 to Catawba Unit 2 Cycle 7 Colr
ML20076K4831994-10-24024 October 1994
Rev 4 to Catawba Unit 1 Cycle 8 Colr
ML20069C2481994-05-20020 May 1994
Rev 2 to Catawba Unit 2 Cycle 7 Colr
ML20065M0581994-04-14014 April 1994
Rev 1 to CNEI-0400-25, Catawba Unit 2 Cycle 6 Colr
ML20065M0751994-04-14014 April 1994
Rev 3 to CNEI-0400-24, Catawba Unit 1 Cycle 8 Colr
ML20065D0471994-03-24024 March 1994
Reload Rept Catawba Unit 2 Cycle 7
ML20138D2961993-02-10010 February 1993
Rev 0 to Catawba Unit 2,Cycle 6 Colr
ML20126F0141992-12-15015 December 1992
Reload Rept,Catawba Unit 2,Cycle 6
ML20116C5761992-10-26026 October 1992
Core Operating Limits Rept,Oct 1992
ML20118A6251992-09-0808 September 1992
Rev 0 to CNEI-0400-24, Catawba Unit 1 Cycle 7 Core Operating Limits Rept for Sept 1992
ML20099G3161992-08-0505 August 1992
Startup Rept Quarterly Update Catawba Unit 2 Cycle 1. W/
ML20095B0241992-04-13013 April 1992
Reload Rept,Catawba Unit 1 Cycle 7. TS & Bases Included in Section 8.1
ML20092H8301992-02-12012 February 1992
Startup Rept Quarterly Update Catawba Unit 2,Cycle 1. W/
ML20092F0041991-11-22022 November 1991
Rev 0 to Catawba Unit 2,Cycle 5 Core Operating Limits Rept
ML20126F0261991-11-22022 November 1991
Rev 0 to Catawba Unit 2,Cycle 6 Colr
ML20077D8111991-05-31031 May 1991
Rev 0 to Catawba Nuclear Station Unit 1 Cycle 6 Core Operating Limits Rept
ML20066C2081990-12-31031 December 1990
Rev 1 to Catawba Unit 2 Cycle 4 Core Operating Limits Rept
ML20066E0701990-10-31031 October 1990
Reload Rept Catawba Unit 1,Cycle 6
ML20063Q0281990-08-31031 August 1990
Rev 0 to Catawba Unit 2 Cycle 4 Core Operating Limits Rept
ML20236Q9961987-09-30030 September 1987
Reload Safety Evaluation,Catawba Nuclear Station Unit 2 Cycle 2
ML20210G1001986-08-31031 August 1986
Rev 1 to Safety Evaluation for Operation of Catawba Units 1 & 2 W/Positive Moderator Coefficient
1999-05-04
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20212J1891999-10-0101 October 1999
Safety Evaluation Supporting Exemption from 10CFR54.17(c)re Schedule to Apply for Renewed Operating Licenses
ML20212A6271999-09-30030 September 1999
Rev 0 to WCAP-15243, Anaylsis of Capsule V & Capsule Y Dosimeters from Duke Energy Catawba Unit 2 Reactor Vessel Radiation Surveillance Program
ML20217H0201999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2
05000413/LER-1999-015, :on 990616,discovered That Auxiliary Bldg Filtered Ventilation Exhaust Sys Was Inoperable.Caused by Improperly Positioned Vortex Damper.Damper Was Repositioned Correctly & Sys Was Retested Successfully1999-09-27027 September 1999
- on 990616,discovered That Auxiliary Bldg Filtered Ventilation Exhaust Sys Was Inoperable.Caused by Improperly Positioned Vortex Damper.Damper Was Repositioned Correctly & Sys Was Retested Successfully
05000414/LER-1999-004-01, :on 980906,error During Tagout Caused de-energization of Vital Bus & Actuation of Ltop.Caused by Inadequate Work Practices.Individuals Involved Were Counseled1999-09-27027 September 1999
- on 980906,error During Tagout Caused de-energization of Vital Bus & Actuation of Ltop.Caused by Inadequate Work Practices.Individuals Involved Were Counseled
ML20212G2511999-09-22022 September 1999
Safety Evaluation Supporting Amends 180 & 172 to Licenses NPF-35 & NPF-52,respectively
05000413/LER-1999-008, :on 990610,operations Prohibited by TS 3.5.2, Was Violated.Caused by Inoperable Centrifugal Charging Pump. Operators Swapped to CCP 1A & Sys Parameters Were Returned to Normal.With1999-09-21021 September 1999
- on 990610,operations Prohibited by TS 3.5.2, Was Violated.Caused by Inoperable Centrifugal Charging Pump. Operators Swapped to CCP 1A & Sys Parameters Were Returned to Normal.With
05000414/LER-1999-005-02, :on 990727,missed Emergency DG TS Surveillance Concerning Verification of Availability of Offsite Power Sources,Was Declared.Caused by Defective Procedure.Revised Affected Procedure1999-09-20020 September 1999
- on 990727,missed Emergency DG TS Surveillance Concerning Verification of Availability of Offsite Power Sources,Was Declared.Caused by Defective Procedure.Revised Affected Procedure
05000413/LER-1999-009, :on 990518,inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits Was Noted. Caused by Inadequate Retest Following Surveillance Test Failure.Valve Was Retested & Returned to Service1999-09-15015 September 1999
- on 990518,inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits Was Noted. Caused by Inadequate Retest Following Surveillance Test Failure.Valve Was Retested & Returned to Service
ML20216E5401999-09-0707 September 1999
Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826
05000413/LER-1999-014, :on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed1999-09-0101 September 1999
- on 990816,missed Surveillances & Operation Prohibited by TS Was Noted.Caused by Defective Procedures or Programs Inappropriate TS Requirements.Affected Procedures/ Programs Were Revised & Testing Was Performed
05000414/LER-1999-004, :on 990616,CIV 2NM-221A Was Returned to Svc Without Testing,As Required by TS 3.6.3.Caused by Programmatic Deficiency.Test Procedure Has Been Revised & Subject Valve Was Successfully Tested & Returned to Svc1999-09-0101 September 1999
- on 990616,CIV 2NM-221A Was Returned to Svc Without Testing,As Required by TS 3.6.3.Caused by Programmatic Deficiency.Test Procedure Has Been Revised & Subject Valve Was Successfully Tested & Returned to Svc
ML20212B4711999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2
05000414/LER-1999-003, :on 990612,unplanned Actuation of ESFAS Occurred Due to a SG High Level.Caused by Inadequate Procedural Guidance.Msiv 2SM-7 Was Closed & SG 2A Level Was Returned to Normal1999-08-31031 August 1999
- on 990612,unplanned Actuation of ESFAS Occurred Due to a SG High Level.Caused by Inadequate Procedural Guidance.Msiv 2SM-7 Was Closed & SG 2A Level Was Returned to Normal
ML20211B1281999-08-31031 August 1999
Dynamic Rod Worth Measurement Using Casmo/Simulate
ML20217H0321999-08-31031 August 1999
Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2
05000413/LER-1999-012, :on 990727,adverse Sys Interaction Between Annulus Ventilation Sys & Auxiliary Building Ventilation Sys Was Discovered.Caused by Inadequate Design.Compensatory Actions Developed & Implemented.With1999-08-26026 August 1999
- on 990727,adverse Sys Interaction Between Annulus Ventilation Sys & Auxiliary Building Ventilation Sys Was Discovered.Caused by Inadequate Design.Compensatory Actions Developed & Implemented.With
ML20211A9791999-08-20020 August 1999
Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2
ML20211F3441999-08-17017 August 1999
Updated non-proprietary Page 2-4 of TR DPC-NE-2009
ML20211C1291999-08-17017 August 1999
ISI Rept Unit 1 Catawba 1999 RFO 11
ML20210U8341999-08-13013 August 1999
Safety Evaluation Supporting Amends 179 & 171 to Licenses NPF-35 & NPF-52,respectively
ML20210R1051999-08-0606 August 1999
Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced
ML20210S2891999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2
ML20212B4871999-07-31031 July 1999
Revised Monthly Operating Rept for July 1999 for Catawba Nuclear Station,Units 1 & 2
05000413/LER-1999-009, :on 990518,inoperability of Containment Valve Injection Water Sys Valve Was Noted in Excess of TS Limits. Caused by Inadequate Testing Following Surveillance Test Failure.Valve Was Retested & Restored to Service1999-07-19019 July 1999
- on 990518,inoperability of Containment Valve Injection Water Sys Valve Was Noted in Excess of TS Limits. Caused by Inadequate Testing Following Surveillance Test Failure.Valve Was Retested & Restored to Service
05000414/LER-1999-004-02, :on 990610,violation of TS 3.6.3 Was Noted Due to CIV 2NM-221A Being Returned to Service Without Testing. Caused by Procedure Deficiency.Civ 2NM-221A Was Tested & Returned to Operable Status1999-07-15015 July 1999
- on 990610,violation of TS 3.6.3 Was Noted Due to CIV 2NM-221A Being Returned to Service Without Testing. Caused by Procedure Deficiency.Civ 2NM-221A Was Tested & Returned to Operable Status
ML20209E4361999-07-0909 July 1999
SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation
05000414/LER-1999-003-02, :on 990612,unplanned Actuation of Esfa Sys Due to a SG High Level Was Noted.Caused by Inadequate Procedural Guidance.Long Term Corrective Actions to Prevent Recurrence of Event Are Being Developed1999-07-0808 July 1999
- on 990612,unplanned Actuation of Esfa Sys Due to a SG High Level Was Noted.Caused by Inadequate Procedural Guidance.Long Term Corrective Actions to Prevent Recurrence of Event Are Being Developed
ML20196K6631999-07-0707 July 1999
Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers
ML20210S2951999-06-30030 June 1999
Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2
ML20209H4501999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2
05000414/LER-1999-002-03, :on 990504,plant Was Forced to Shutdown as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Affected Piping Was Cleaned & Flow Tested1999-06-0303 June 1999
- on 990504,plant Was Forced to Shutdown as Result of Flow Restriction Caused by Corrosion of Afs Assured Suction Source Piping Due to Inadequate Testing. Affected Piping Was Cleaned & Flow Tested
ML20196L1881999-05-31031 May 1999
Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology
ML20196A0001999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2
ML20209H4561999-05-31031 May 1999
Revised Monthly Operating Rept for May 1999 for Catawba Nuclear Station,Units 1 & 2
ML20206T4771999-05-31031 May 1999
Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology
ML20206P5201999-05-14014 May 1999
Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves
ML20206N8391999-05-0404 May 1999
Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr
ML20206R1811999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
ML20196A0041999-04-30030 April 1999
Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
ML20206N8261999-04-22022 April 1999
Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included
ML20205S5551999-04-21021 April 1999
Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
05000413/LER-1999-004, :on 990310,operation Prohibited by TSs Was Noted.Caused by Incorrect TS Requirements for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation.Submitted Lar.With1999-04-12012 April 1999
- on 990310,operation Prohibited by TSs Was Noted.Caused by Incorrect TS Requirements for Cravs & Auxiliary Bldg Filtered Ventilation Exhaust Sys Actuation Instrumentation.Submitted Lar.With
ML18016A9011999-04-12012 April 1999
Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected
ML20205N3651999-04-12012 April 1999
Safety Evaluation Accepting IPE of External Events Submittal
ML20205N2381999-04-0909 April 1999
Safety Evaluation Supporting Amends 178 & 170 to Licenses NPF-35 & NPF-52,respectively
ML20205P9521999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2
ML20206R1931999-03-31031 March 1999
Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2
ML20205B3101999-03-26026 March 1999
Safety Evaluation Supporting Amends 176 & 168 to Licenses NPF-35 & NPF-52,respectively
05000413/LER-1999-001-01, :on 990215,inoperable Refueling Water Storage Tank Level Channels Resulted in Operation Outside Design Basis.Caused by Inadequate Program Design.Reviewed Procedure & Communication Improvements Between Groups1999-03-17017 March 1999
- on 990215,inoperable Refueling Water Storage Tank Level Channels Resulted in Operation Outside Design Basis.Caused by Inadequate Program Design.Reviewed Procedure & Communication Improvements Between Groups
1999-09-07
[Table view] |
Text
CNEl-0400-24 Page 1 of 24 Revision 16 j
,F Catawba Unit 1 Cycle 12
(
Core Operating Limits Report Revision 16 May 1999 Calculation Number: CNC-1553.05-00-0314 Duke Power Company Date Prepared By:
d 6 #!ff u
i Checked By:,u / L-4%
g/W71 Checked By:
U.(fhepn.
fk9 Approved By: g /F M (d ;
(/y/M QA Condition 1 The contents of this document have been reviewed to verify that no material herein either directly or indirectly changes or affects the results and conclusions presented in the 10CFR50.59 Catawba 1 Cycle 12 Reload Safety Evaluation.
9905180085 990510 PDR ADOCK 05000413 P
PDR
CNEl-0400-24 Page 2 of 24 Revision 16 Catawba 1 Cycle 12 Core Operating Limits Report IMPLEMENTATION INSTRUCTIONS FOR REVISION 16 Revision 16 of the Catawba Unit 1 COLR contains limits specific to the Catawba Unit 1 Cycle 12 ccre design. This revision shall be implemented after no mode is reached and prior to the start of fuel loading in the Catawba Unit 1 EOC-11 outage.
O O
q i
CNEI-0400-24 i
Page 3 of 24 I
Revision 16 Catawba 1 Cycle 12 Core Operating Limits Report REVISION LOG Revision Effective Date Pages Affected COLR OriginalIssue September 8,1992 N/A CIC07 COLR Revision 1 October 10,1992 N/A CIC07 COLR rev 1 Revision 2 December 1,1993 N/A CIC08 COLR Revision 3 April 14,1994 N/A CIC08 COLR rev 1 Revision 4 October 24,1994 N/A CIC08 COLR rev 2 i
Revision 5 November 30,1994 N/A CIC08 COLR rev 3 Revision 6 February 15,1995 N/A CIC09 COLR Revision 7 April 12,1995 N/A CIC09 COLR rev 1 Revision 8 September 28,1995 N/A CIC09 COLR rev 2 Revision 9 August 2,1996 N/A C1C10 COLR Revision 10 May 28,1997 N/A CIC10 COLR rev 1 Revision 1I July 1997 N/A CIC10 COLR rev 2 Revision 12 November 1997 N/A CIC11 COLR Revision 13 August 1998 N/A CIC11 COLR rev 1 Revision 14 December 1998 N/A CIC11 COLR rev 2 l
Revision 15 April 1999 1-24 CIC12 COLR Revision 16 May 1999 1-4,20-24 CIC12 COLR, rev 1 l
l GV 1
L-
CNEl-0400-24 Page 4 of 24 Revision 16 Catawba 1 Cycle 12 Core Operating Limits Report INSERTION SHEET FOR REVISION 16 Remove Rev.15 pages Insert Rev.16 pages Pages 1,2,3,4,20,21,22,23,24 Pages 1,2,3,4,20,21,22,23,24 0
4 j
O
CNEl-0400-24 Page 20 of 24 Revision 16 l Catawba 1 Cycle 12 Core Operating Limits Report 2.9 Boron Dilution Mitigation System (TS 3.3.9) 2.9.1 Reactor Makeup Water Pump flow rate limits:
l Applicable Mode Limit Mode 3 s 150 gpm Mode 4 or 5 s 70 gpm 2.10 Accumulators (TS 3.5.1) 2.10.1 Boron concentration limits during modes 1 and 2, and mode 3 with RCS pressure
>1000 psi:
Parameter Limit U
Cold Leg Accumulator minimum boron concentration.
2,550 ppm l
Cold Leg Accumulator maximum boron concentration.
2,975 ppm 2.11 Refueling Water Storage Tank - RWST (TS 3.5.4) 2.11.1 Boron concentration limits during modes 1,2,3, and 4:
Parameter Limit Refueling Water Storage Tank minimum boron 2,750 ppm l
concentration.
Refueling Water Storage Tank maximum boron 2,975 ppm concentration.
Lv
CNEI-0400-24 Page 21 of 24 Revision 16 l Catawba 1 Cycle 12 Core Operating Limits Report
(]J L
2.12 5 pent Fuel Pool Boron Concentration (TS 3.7.15) 2.12.1 Minimum boron concentration limit for the spent fuel pool. Applicable when fuel assemblies are stored in the spent fuel pool.
Parameter Limit Spent fuel pool minimum boron concentration 2,750 ppm l
2.13 Refueling Operations - Boron Concentration (TS 3.9.1) 2.13.1 Minimum boron concentration limit for the filled portions of the Reactor Coolant System, refueling canal, and refueling cavity for mode 6 conditions. The minimum boron concentration limit and plant refueling procedures ensure that the
('3 Keff of the core will remain within the mode 6 reactivity requirement of Keff s k/
0.95.
Parameter Limit Minimum Boron concentration of the Reactor Coolant 2,750 ppm l
System, the refueling canal, and the refueling cavity.
2.14 Refueling Operations - Instrumentation (TS 3.9.2) 2.14.1 Reactor Makeup Water Pump Flow rate Limit:
Applicable Mode Limit Mode 6 s 70 gpm O
CNEI-0400-24 Page 22 of 24 Revision 16 l A
Catawba 1 Cycle 12 Core Operating Limits Report U
2.15 Borated Water Source-Shutdown (SLC 16.9-11) 2.15.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during mode 4 with any RCS cold leg temperature s 285 F, and modes 5 and 6.
Parameter Limit Boric Acid Storage System minimum contained 12,000 gallons borated water volume Boric Acid Storage System minimum boron 7,000 ppm concentration Boric Acid Storage System minimum water 585 gallons volume required to maintain SDM at 7,000 ppm Refueling Water Storage Tank minimum contained 45,000 gallons borated water volume Refueling Water Storage Tank minimum boron 2,750 ppm l
concentration Refueling Water Storage Tank minimum water 3,500 gallons volume required to maintain SDM at 2,750 ppm l
O
p l
CNEl-0400-24 Page 23 of 24 Revision 16 l i
l
,o Catawba 1 Cycle 12 Core Operating Limits Report Q
2.16 Borated Water Source - Operating (SLC 16.9-12) 2.16.1 Volume and boron concentrations for the Boric Acid Storage System and the Refueling Water Storage Tank (RWST) during modes 1,2,3, and mode 4 with all l
l RCS cold leg temperatures > 285 F.
Parameter Limit i
Boric Acid Storage System minimum contained 24,000 gallons borated water volume Boric Acid Storage System minimum boron 7,000 ppm concentration Boric Acid Storage System minimum water 12,300 gallons
~
volume required to maintain SDM at 7,000 ppm O
Refueling Water Storage Tank minimum contained 98,607 gallons td borated water volume Refueling Water Storage Tank minimum boron 2,750 ppm l
concentration Refueling Water Storage Tank minimum water 57,107 gallons volume required to maintain SDM at 2,750 ppm l
l l
l 1
l
CNEl-0400-24 Page 24 of 24 Revision 16 l Catawba 1 Cycle 12 Core Operating Limits Report 2.17 Standby Makeup Pump Water Supply - Boron Concentration (SLC-16.7-9.3) 2.17.1 Minimum boron concentration limit for the spent fuel pool. Applicable for modes 1,2, and 3.
1 1
Parameter Limit Spent fuel pool minimum boron concentration for 2,750 ppm l
l surveillance SLC-16.7-9.3.
NOTE: Data contained in the Appendix to this document was generated in the Catawba 1 Cycle 12 Maneuvering Analysis calculation file, CNC-1553.05-00-0304. The Plant Nuclear Engineering Section will control this information via computer file (s) and should be
[
contacted if there is a need to access this information.
l
,