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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML17229A7101998-04-30030 April 1998 Analysis of Capsule 263 from FPL St Lucie Unit 2 Reactor Vessel Radiation Surveillance Program. ML17229A5711997-10-31031 October 1997 Criticality Safety Analysis for Spent Fuel Storage Rack Using Soluble Boron Credit. ML17229A0421996-09-30030 September 1996 Rev 1 to CEN-405-NP, Application of Reactor Vessel Surveillance Data for Embrittlement Mgt. ML17228B2261995-06-30030 June 1995 Generic Upper Shelf Values for Linde 1092,124 & 0091 Reactor Vessel Welds, Final Rept ML17228B1901995-05-31031 May 1995 Joint Applications Rept for Safety Injection Tank Aot/Sti Extension. ML17228B1831995-05-31031 May 1995 Joint Applications Rept for LPSI Sys AOT Extension. ML17228B1801995-05-31031 May 1995 Joint Applications Rept for EDGs AOT Extension. ML17228B4991993-07-31031 July 1993 Nonproprietary Version of Application of Reactor Vessel Surveillance Data for Embrittlement Mgt. ML17228A4591991-09-30030 September 1991 Suppl 1 to Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis St Lucie Nuclear Power Plant Unit 1. ML17228A4581991-09-30030 September 1991 Boric Acid Concentration Reduction Effort Technical Bases & Operational Analysis St Lucie Power Plant Unit 1. ML20011F4981989-11-30030 November 1989 Verification of Acceptability of 1-Pin Burnup Limit of 60 Mwd/Kg for St Lucie Unit 2. ML20153G0921988-09-0101 September 1988 Boric Acid Concentration Reduction ML17221A5971988-01-22022 January 1988 Concentration Reduction Effort,Technical Bases & Operational Analysis. ML17221A5881987-03-31031 March 1987 Rev 0 to Criticality Safety Analysis St Lucie New Fuel Storage Vault W/4.5% Enriched 14x14 Fuel Assemblies. ML17219A2621986-10-31031 October 1986 I Steam Generator Allowable Tube Wall Degradation. ML20238F2591986-08-31031 August 1986 Tube Burst & Leakage Testing of Intergranular Attack & IGSCC Defects Representative of Those Found in St Lucie Unit One Steam Generators ML20155B1281986-03-20020 March 1986 Loca/Eccs Analysis W/11% Steam Generator Tube Plugging ML17216A6161986-02-28028 February 1986 Rev 1 to St Lucie Unit 1:New & Spent Fuel Storage Criticality Safety Evaluation for Natural U Axial Blanket Fuel. ML20140E1961985-12-31031 December 1985 Suppl 1 to St Lucie Unit 1 Revised LOCA-ECCS Analysis W/15% Steam Generator Tube Plugging Break Spectrum & Exposure Results ML17216A3461985-11-0505 November 1985 Revised LOCA-ECCS Analysis W/15% Steam Generator Tube Plugging. ML17346B1711985-07-31031 July 1985 Retran Code Transient Analysis Model Qualification. ML17215A3691984-04-30030 April 1984 Nonproprietary Conservatism of Axial Shape Index DNB Limiting Condition for Operation Below 30% Power. ML20085H5511983-08-16016 August 1983 Core Support Barrel Insp,Repair & Analysis & Thermal Shield Removal ML20083N2661983-01-0707 January 1983 Plant Transient Analysis for St Lucie Unit 1 ML20083N2481983-01-0707 January 1983 Rev 1 to St Lucie Unit 1 Cycle 6 Sar ML20083N2091982-12-20020 December 1982 LOCA Analysis Using Exem/Pwr ECCS Model ML20039F8671981-12-31031 December 1981 Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for St Lucie 1 & 2 Reactor Vessels. ML17208A8921980-07-31031 July 1980 RCS Asymmetric Loads Evaluation,Numerical Results - Evaluation of C-E Fuel, App A,Nonproprietary Version ML17208A8931980-07-31031 July 1980 RCS Asymmetric Loads Evaluation,Eccs Analysis Approach W/Reduced Area Coolant Channels in Peripheral Assemblies, App B ML19310A2331980-02-29029 February 1980 Statistical Combination of Uncertainties Methodology,Part 3:C-E Calculated Departure from Nucleate Boiling & Linear Heat Rate Limiting Conditions for Operation for St Lucie Unit 1, Nonproprietary Version ML19310A2241980-01-31031 January 1980 Ceaw:Method of Analyzing Sequential Control Element Assembly Group Withdrawal Event for Analog Protected Sys, Nonproprietary Version ML19310A2311980-01-31031 January 1980 Statistical Combination of Uncertainties Methodology,Part 2:Combination of Sys Parameter Uncertainties in Thermal Margin Analyses for St Lucie Unit 1, Nonproprietary Version ML19310A2271979-12-31031 December 1979 Statistical Combination of Uncertainties Methodology,Part 1:C-E Calculated Local Power Density & Thermal Margin/Low Pressure LSSS for St Lucie Unit 1, Nonproprietary Version ML19310A2261979-11-30030 November 1979 Fiesta:One Dimensional,Two Group Space-Time Kinetics Code for Calculating PWR Scram Activities. 1998-04-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17241A4891999-10-0707 October 1999 LER 99-004-00:on 990912,noted That MSSV Surveillance Was Outside of TS Requirements.Caused by Setpoint Drift.Subject MSSVs Are Being Refurbished & Retested Prior to Unit Startup from SL1-16 Refueling Outage.With 991007 Ltr ML17241A4951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for St Lucie,Units 1 & 2.With 991014 Ltr ML17241A4741999-08-31031 August 1999 Rev 1 to PCM 99016, St Lucie Unit 1,Cycle 16 Colr. ML17241A4591999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for St Lucie,Units 1 & 2.With 990913 Ltr ML17241A4301999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for St Lucie Units 1 & 2.With 990805 Ltr ML17241A4111999-07-16016 July 1999 LER 99-007-00:on 990610,unplanned Cooldown Transient Occurred Due to Personnel Error.Trained & Briefed Personnel & Revised Procedures.With 990716 Ltr ML17241A4031999-07-0606 July 1999 LER 99-006-00:on 990605,sub-critical Reactor Trip Occurred Due to Inadvertent MSIV Opening.Caused by Personnel Error. Provided Operation Supervision Instruction to Operating Crews,Stand Down Meetings & Operator Aids.With 990706 Ltr ML17241A4041999-07-0606 July 1999 LER 99-005-00:on 990604,CEA Drop Resulted in Manual Reactor Trip.Caused by Procedural Inadequacies.Procedure Changes Are Planned to Correct Lack of Procedural Guidance for CEA Subgroup Power Switch Replacement.With 990706 Ltr ML17241A4091999-06-30030 June 1999 Monthly Operating Repts for June 1999 for St Lucie,Units 1 & 2.With 990712 Ltr ML17241A3941999-06-30030 June 1999 LER 99-004-01:on 990415,as Found Cycle 10 Psv Setpoints Were Outside TS Limits.Caused by Manufacturing Process Defect. All Three Psvs Were Replaced with pre-tested Valves During Cycle 11 Refueling Outage.With 990630 Ltr ML17355A3681999-06-30030 June 1999 Revised Update to Topical QA Rept, Dtd June 1999 ML17241A3551999-06-0404 June 1999 LER 99-002-00:on 990505,both Trains of Safety Injection Actuation Were Blocked During Surveillance.Caused by Procedure Error.Procedure Revised.With 990604 Ltr ML17241A3631999-05-31031 May 1999 Monthly Operating Repts for May 1999 for St Lucie Units 1 & 2.With 990610 Ltr ML17241A3321999-05-17017 May 1999 LER 99-004-00:on 990415,determined That as Found Cycle 10 Psv Setpoints Outside TS Limits.Root Cause Under Investigation.Psvs Replaced with pe-tested Valves During Cycle 11 ML17241A3271999-05-0606 May 1999 LER 99-003-00:on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With 990506 Ltr ML17241A3331999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for St Lucie,Units 1 & 2.With 990517 Ltr ML17229B0801999-04-0707 April 1999 LER 99-002-00:on 990311,SG ECT Error Caused Operation with Condition Prohibited by Ts.Caused by Deficiencies in Data Analysis Guideline Instructions.Licensee Will Change Data Analysis Guidelines for Lead Analysts.With 990407 Ltr ML17229B0841999-04-0707 April 1999 Rev 2 to PSL-ENG-SEMS-98-102, Engineering Evaluation of ECCS Suction Lines. ML17229B0791999-04-0707 April 1999 LER 99-001-00:on 990309,discovered Inadequate Design & IST SRs for Iodine Removal Sys (Irs).Caused by Original Design Inadequacies & Personnel Error.Naoh Tank Vent Valve V07233 Was Tagged Open.With 990407 Ltr ML17229B0961999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for St Lucie,Units 1 & 2.With 990408 Ltr ML17229B0541999-03-10010 March 1999 LER 99-001-00:on 990211,inadequate TS SRs for SIT & SDC Isolation Valves Were Noted.Caused by Failure to Correctly Implement TS Srs.Submitted LAR to Align Required TS SR with Design Bases Requirements Being Verified.With 990310 Ltr ML17229B0461999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for St Lucie,Units 1 & 2.With 990310 Ltr ML17229B0051999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for St Lucie,Units 1 & 2.With 990211 Ltr ML17229A9901999-01-20020 January 1999 LER 98-009-00:on 981223,noted That Facility Operated Outside of Design Basis.Caused by non-conservative MSLB Analysis Inputs.Will Review SR Component Differences Between Units & Will re-baseline LTOP Analysis.With 990120 Ltr ML17229A9961999-01-14014 January 1999 SG Tube Inservice Insp Special Rept. ML17229A9821999-01-0404 January 1999 LER 98-010-00:on 981207,RCS Boron Sample Frequency Required by Ts,Was Exceeded by Twelve Minutes.Caused by Personnel Error.Equipment Clearance Order Was Lifted to Draw Required Sample & Operations Procedure Was Changed.With 990104 Ltr ML17229A9831998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for St Lucie,Units 1 & 2.With 990111 Ltr ML17229A9611998-12-22022 December 1998 LER 97-002-01:on 981204,containment Sump Debris Screen Was Not IAW Design.Caused by Inadequate C/As for Sump Screen Anamolies.All Identified Sump Screen Deficiencies Were Dispositioned &/Or Repaired.With 981222 Ltr ML17229A9561998-12-15015 December 1998 LER 98-008-00:on 981118,missed TS SG U Tube Insp.Caused by Encoding Errors While Using Remote Positioning Fixtures.All SG Tube Surveyed.With 981215 Ltr ML17241A3581998-12-0909 December 1998 Changes,Tests & Experiments Made as Allowed by 10CFR50.59 for Period of 970526-981209. ML17229A9421998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for St Lucie,Units 1 & 2.With 981215 Ltr ML17229A9301998-11-25025 November 1998 LER 98-005-01:on 980807,discovered That New MOV Methodology Caused Past PORV Block Valve Operability Problem.Caused by Inadequacies in Original Vendor MOV Methodology.Planned Valve Mods Will Be Implemented During Cycle 11 1998 Outage ML17229A9021998-11-0404 November 1998 LER 98-008-00:on 981008,inadequate Reactor Protection Sys Trip Bypass TS Was Noted.Caused by Poorly Worded Ts. Submitted LAR to Clarify Power Requirements for High Rate of Power Trips.With 981104 Ltr ML17241A4931998-11-0101 November 1998 Statement of Account for Period of 981101-990930 for Suntrust Bank,As Trustee for Florida Municipal Power Agency Nuclear Decommissioning Trust (St Lucie Project). ML17229A9051998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for St Lucie,Units 1 & 2.With 981110 Ltr ML17229A8871998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1 Which Was Machined with Improper Length.C/A Includes Insp Equipment That Will 100% Identify Short Length ML17229A8781998-10-19019 October 1998 Part 21 Rept Re Potential Defect in Swagelok Stainless Steel Front Ferrule,Part Number SS-503-1,which Was Machined with Improper Length.Insp Equipment That Will 100% Identify Short Length ML17229A8771998-10-14014 October 1998 LER 98-006-00:on 980918,inadvertent Afas Actuation Was Noted.Caused by Degradation of Multiple Afas Power Supplies. Replaced Afas Power Supplies & Revised Procedures.With 981014 Ltr ML17229A8761998-10-14014 October 1998 LER 98-007-00:on 980918,identified Discrepancies Between Fire Protection Design Requirements & Field Conditions. Caused by Inadequate Translation & Implementation of Fire Protection Requirements.Procedures Revised.With 981014 Ltr ML17229A8721998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for St Lucie Units 1 & 2.With 981009 Ltr ML17229A8511998-09-0202 September 1998 LER 98-005-00:on 980807,discovered That PORV Margins Were Insufficient to Accommodate Addl Conservatism.Caused by Inadequacies in Original Vendor MOV Methodology.Will Implement Planned Valve Actuator mods.W/980902 Ltr ML17229A8611998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for St Lucie,Units 1 & 2.With 980911 Ltr ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML17229A8481998-08-0707 August 1998 Rev 1 to PSL-ENG-SEFJ-98-013, St Lucie Unit 2,Cycle 10 Colr. ML17229A9461998-08-0707 August 1998 Rev 0 to PCM 98016, St Lucie Unit 2,Cycle 11 Colr. ML17229A8301998-07-31031 July 1998 Monthly Operating Repts for July 1998 for St Lucie,Units 1 & 2.W/980814 Ltr ML17229A8201998-07-29029 July 1998 LER 98-007-00:on 980630,inadequate Procedure May Have Resulted in SBO Recovery Complications.Caused by Inadequate Procedures.Attached Caution Tags to Appropriate Control switches.W/980729 Ltr ML17229A7981998-06-30030 June 1998 Monthly Operating Repts for June 1998 for St Lucie,Units 1 & 2.W/980713 Ltr ML17229A7701998-05-31031 May 1998 Monthly Operating Repts for May 1998 for St Lucie,Units 1 & 2.W/980612 Ltr ML17229A7411998-05-28028 May 1998 LER 98-004-00:on 980430,discovered Waste Gas Decay Tank Operation W/O Available Oxygen Analyzers,Which Is Prohibited by Ts.Caused by Inadequate Licensee Review of License Amend. Oxygen Analyzer recalibrated.W/980528 Ltr 1999-09-30
[Table view] |
Text
SUPPLEMENT 1 TO BORIC ACID CONCENTO TION REDUCTION EFFORT CEN-353(P)
TECHNICAL BASES AND OPERATIONAL ANALYSIS SAINT LUCIE NUCLEAR POWER PLANT UNIT 1 PREPARED FOR FLORIDA POWER&.LIGHT COMPANY BY ABB COMBUSTION ENGINEERING NUCLEAR SERVICES 9403070179 940222 PDR ADOCK OS00033S~P..PDR Boric Acid Concentration Reduction E ort.Su l.l TABLE OF CONTENTS CEN-353 F 1.0 2.0 3.0 40 PURPOSE AND SCOPE
SUMMARY
OF RESULTS TECHNICAL BASES FOR REVISIONS 3.1 REVISED BAMT VOLUME REQUIREMENTS
3.2 REVISED
BASES SECTION 3/4.
1.2 REFERENCES
10 12 TABLES TABLE 3-1 BAMT BORATION VOLUME TABLE 3-2 REQUIRED BAMT STORAGE VOLUME FIGURES FIG.3-1 ST.LUCIE 1 MINIMUM BAMT VOLUME vs.STORED BAMT CONCENTRATION APPENDIX A TECHNICAL SPECIFICATION INPUT FOR ST.LUCIE UNIT 1 A-1 ABB Combustion Engineering Nuclear Services Page 2 of 12 Boric Acid Concentration Reduction E ort.Su l.1 CEN-353(F 1.0 Purpose and Scope The purpose of this Supplement to the Boric Acid Concentration Reduction (BACR)report is.to provide an adjustment to the Boric Acid Makeup Tank (BAMT)Volume and concentration requirements for the St.Lucie Unit 1 Technical Specifications Section 3.1.2.8.This adjustment is due only to revising an assumption that was made in the BACR Report, CEN-353(F), Rev 03.This supplement modifies an original assumption that the BAMT would be needed as the source of fluid for depressurization of the RCS from 2200 psia to the High Pressure Safety Injection (HPSI)pump shutoff head.The depressurization would require additional inventory if the motor operated valve between the Refueling Water Tank (RWT)and the charging pump suction, V2504, failed to open automatically,and could not be opened manually.Once the depressurization occurred, the cooldown could be continued using fluid from the RWT.This revision now assumes that V2504 can be opened manually, therefore, the BAMT inventory needed to depressurize to the HPSI pump shutoff head is no longer required.This results in revision of the required BAMT boration volumes and the Technical Specification BAMT storage requirements.
This Supplement is applicable to St.Lucie Unit 1 only.Revision of the BAMT Volume requirements will also result in a change to the BAMT volumes listed in the Technical Specification BASES Section 3/4.1.2.The ll BASES values were presented on pages 32 and 33 of the report.In the report, the text of the Bases insert used the exact BAMT boration volume, rather than the ABB Combustion Engineering Nuclear Services Page 3 of l2 Boric rlcid Concelurntion Reduction E orr.Su l.i CEJV-353IF required storage volume.The BASES text was revised to correspond to the required storage volumes, which were conservative.
Since the assumption change of this calculation revises the volume adjustment between the BAMT boration volume and the required storage volume, the BASES insert will be revised.2.0 Summar of Results The proposed Technical Specification inputs for St.Lucie Unit 1 for Section 3.1.2.8 and BASES Section 3/4.1.2 are contained in Appendix A.The revised values supplied in Appendix A are derived in Section 3.1 and 3.2 below.3.0 Technical Bases for Revisions 3.1 Revised BAMT Volume Requirements As stated above, the purpose of this supplement is to document the revision of the adjustment between the BAMT boration volumes and the Technical Specification BAMT storage requirements.
In the previous revision to this report, manual operation of V2504 (the motor operated valve between the RWT and the charging pump suction)was not assumed for a postulated failure to open automatically.
Since RWT water would be riBB Colnbustion Engineering nuclear Services Pnge 4 of 12 Boric Acid Concentration Reduction E ort.Su l.1 CEN-353(F unavailable through the CVCS for cooldown with V2504'closed, additional water inventory requirements were imposed on the BAMTs to allow for depressurization of the RCS down to HPSI shutoff head (1200 psia)using auxiliary spray.A volume adjustment of 1000 gallons was used, to cover the 905.9 gallons required for the depressurization (CEN-353(F), Rev.03, Page 29).The boration volumes were adjusted by rounding up to the next 50 gallons and then adding 1000 gallons to cover the depressurization volume.Manual handwheel operation of motor operated valve V2504 is acceptable for St.Lucie Unit 1 cooldown scenarios.
Revising this assumption will make the St.Lucie Unit 1 analysis agree with the Unit 2 analysis for this assumption.
With manual operation of V2504, adjustment of the boration volume to include the volume for depressurization will no longer be required.In CEN-353(F), Rev.03, the BAMT boration volumes for each combination of BAMT and RWT concentrations was provided in Table 2-34 on page 73.These values are repeated in Table 3-1 below.ABB Cotnbustion Engineering Nuclear Services Page 5 of 12 Boric Acid Concentration Reduction E ort, Su l.i TABLE 3-1 CEJV-353 F BORIC ACID MAKEUP TANK MINIMUM BORATION VOLUMES VS STORED BORIC ACID CONCENTRATION FOR MODES 1, 2, 3 AND 4 MINIMUM VOLUME (GALLONS)BAMT at wt%1720 1850 RWT at RWT at RWT at 2000 RWT at RWT at 2150 2300 ppm ppm ppm ppm ppm 2.50 2.75 3.00 3.25 3.50 8194.5 7703.9.6966.8 6607.9 6185.4 5689.8 5406.0 5065.4 4887.7 4535.6 7221.1 6129.9 5235.2 4594.0 4130.1 6714.5 6019.3 5577.7 4946.8 4769.9 4187.7 4130.1 3650.9 3713.2 3213.1 During the St.Lucie Unit 2 BACR analysis, 500 gallons were added to the BAMT boration volumes for conservatism.
To be consistent with Unit 2, 500 gallons will be added to the St.Lucie Unit 1 BAMT boration volumes to define the revised Technical Specification BAMT Storage volume requirements.
The boration volumes;vill be rounded up to the next 50 gallons, and 500 gallons will be added for conservatism.
The resulting Required BAMT Storage Volumes are contained in Table 3-2 and are plotted in Figure 3-1.Figure 3-1 provides the revised storage requirements to replace Figure 2-6 on page 82 of the main report.ABB Combustion Engineering Nuclear Services Page 6of l2
Boric Acid Concentration Reduction E ort.Su I.l CEN-353/'F TABLE 3-2 MINIMUM BORIC ACID MAKEUP TANK VOLUME VS.STORED BORIC ACID MAKEUP TANK CONCENTRATION MINIMUM VOLUME (GALLONS)BAMT at wt,%1720 1850 2000 RWT at RWT at RWT at RWT at 2150 RWST at 2300 ppm ppm ppm ppm ppm 2.50 8700 8250 7750 7250 6550 2.75 7500 7150 6650 6100 5450 3.00 6700 6200 5750 5300 4700 3.25 3.50 5950 5400 5600 5100 5050 4650 4650 4250 4200 3750 FP&L currently requests that only one curve be presented in the Required BAMT Volume curve, Technical Specification Figure 3.1-1, rather than the family of curves for various RWT concentrations.
FP&L requests that only the curve for the RWT at 1720 ppm be provided.The new Technical Specification Figure 3.1-1 is contained in Appendix A.ABB Cotnbustion Engineering Nttclear Services Page 7 of 12 Boric Acid Concentration Reduction E ort.Su l.l CEN-353(F Since the new Required BAMT volumes can be contained in one tank for the full range of boric acid concentrations, some of the text for Technical Specification Section 3.1.2.8 can be deleted.When the volume requirement for the full range of concentrations could not fit in one tank, the current specification required a boric acid concentration between 3.2-3.5 weight percent.The revised specification is contained in Appendix A.ABB Combustion Engineering Nuclear Services Page 8 of 12 Boric Acid Concentration Reduction E ort Su>~l.I CEN-353 F FIGURE 3-1 ST,LUCIE 1 IVIIN BAMT VOLUME vs STORED BAMT CONCENTRATION Q 7 g~6 0~5 2.6 2.8 3.0 3.2 STORED BAMT CONC (wt%boric acid)3.4 3.6~1720PPM~1850PPM~2000PPM~2150PPM~2300PPM IH RWT IN RWT IN RWT IN RWT IH RWT ABB Combustion Engineering Nuclertr Set vices Page 9 of l2 Boric Acid Concentration Reduction E ort.Su l.l CEN-353(F 3.2 Technical S ecification BASES Section 3/4.1.2 The Technical Specification BASES Section 3/4.1.2 was originally presented on pages 32 and 33 of CEN-353(F), Rev.03.The purpose of that section was to determine the new BAMT and RWT volume values for the Technical Specification BASES section.The section used the BAMT boration volumes as inputs to determine the required RWT volume for the cooldown depending on the BAMT concentration used.It also determined the RWT volume required if no BAMT volume was used.While the actual BAMT Boration Volume values were used in the section, the revised text of the BASES Section should report the BAMT Storage Volume Requirements as the volume used.Since the BAMT Storage Volume Requirements are greater, this is conservative.
The BAMT Storage Volumes are used to make the BASES Section consistent with the BAMT Storage Volumes contained in Figure 3.1-1 and Technical Specification Section 3.1.2.8'.Since the Technical Specification BAMT Storage Volume Requirements were revised in Section 3.1 above, The BASES Section should be revised to correspond to the new BAMT Storage Volume Requirements.
Since the BAMT Boration Volumes were used to calculate the RWT volume requirements, and the BAMT Boration Volumes have not changed, there is no need to revise the RWT volume requirements.
rhBB Combustion Engineering Nuclear Services Page 10 of 12 Boric Acid Concentration Reduction E ort.Su l.l CEN-353 F The revised text for the BASES Section is as follows: "The boration capability of either system is sufficient to provide a SHUTDOWN MARGIN from all operating conditions of 2000 pcm after xenon decay and cooldown to 200 degrees F.The maximum boration'apability requirement occurs at EOL from full power equilibrium xenon conditions.
This requirement can be met for a range of boric acid concentrations on the Boric Acid Makeup Tanks (BAMTs)and Refueling Water Tank (RWT).This range is bounded by 5400 gallons of 3.5 weight percent (6119 ppm boron)boric acid from the BAMTs and 17,000 gallons of 1720 ppm borated water from the RWT to 8700 gallons of 2.5 weight percent (4371 ppm boron)boric acid from the BAMTs and 13,000 gallons of 1720 ppm borated water from the RWT.A minimum of 45,000 gallons of 1720 ppm boron is required from the RWT if it is to be used to borate the RCS alone." This text is contained in Appendix A.ABB Combustion Engineering Nuclear Services Page ll of 12 Boric Acid Concentration Reduction E ort.Suo l.l CEN-353(F J
4.0 REFERENCES
4.1 ABB-CE Calculation 607784-MPS-1CALC-001, Revision 00,"St.Lucie Unit 1 Input to Technical Specifications 3.1.2.8 and 4.1.2.8", dated 9/25/90.4.2 ABB-CE Calculation F-MPS-CALC-002, Rev.00,"Input to St.Lucie Unit 1 Technical Specification System Bases", dated 9/26/91.4.3 St Lucie Unit 1 Technical Specifications, through Amendment 122, dated 5/03/93.4.4 ABB-CE Calculation F-MECH-CALC-016, Rev.00,"FP&L St.Lucie 1 Revision of Technical Specification Section 3.1.2.8 and BASES 3/4.1.2", dated 10/21/93.ABB Combustion Engineering Nuclear Services Page l2 of 12 Boric Acid Concentration Reduction E ort.Su l.l CEN-353(F)
APPENDIX A Technical Specification Input for St.Lucie Unit 1 ABB Combustion Engineering Nuclear Services Page A-l of 5 Boric Acid Concentration Reduction E urt.Su r l.l CEN-353 F FIGURE 3.1-1 ST.LUCIE 1 lVIIN BAMT VOLUME YS STORED BAMT CONCENTRATION 9,000 V)O 8,000 GJ CD (8700)ACCEPTABLE OPERATION (750 0)~7,000 O)I-~e,ooo Z'6700)UNACCEPTABLE OPERATION (6960)5,000 (6400)2.4 2.6 2.8 3 3.2 3.4 3.6 (4646 PPM)(5245 ppM)(6g44 PPM)(4196 PPM)(4896 PPM)(55g6 ppM)(62g4 ppM)STORED BAMT CONC (wt%boric acid)ST.LUCIE-UNIT I 3/4 1-1/ABB Combustion Engineering Nuclear Services Page A-2 of 5
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