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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
ST. LUCIE 2 DOCKET 50-389 CEN-279(L) -NP Conservatism of the Axial Sha e Index DNB Limitin Condition for 0 eration Below 305 Power April 1984 COMBUSTION ENGINEERING, INC.
NUCLEAR POWER SYSTEMS POWER SYSTEMS GROUP WINDSOR, CONNECTICUT 06095 8405070324 840430 PDR ADOCK, 05000389 P PDR
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LEGAL NOTICE This report was prepared as an account of work sponsored by Combustion Engineering, Inc. Neither Combustion Engineering nor any person acting on its behalf:
A. Makes any warranty or representation, express or implied including the warranties of fitness for a particular purpose or merchantability, with respect to the accuracy, completeness, or usefullness of the information contained in this report, or that the use of any information, apparatus, method, or process disclosed in this. report may not infringe privately owned rights; or
- 8. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apoaratus, method or process disclosed in this report.
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Conservati sm of the Axi al Sha e Index DNB-LCO Below 305 Power On Figure 1, the solid lines drawn in the shape of a tent represent the DNB LCO ASI vs power limits that St. Lucie Unit 2 must operate within during Cycle 1.
This tent is a conservative depiction of the actual calculated values forming the DNB LCO." i These calculated values were generated using computer runs by starting with the DNB SAFDL (which was 1.20 for Cycle 1) and then "backing off" as much as is necessary over each portion (positi ve and negative ASI) to assure that the limiting transient (eg. CEA drop, Loss of Flow) provides sufficient margin to the SAFDL when initiated from anywhere within the LCO space.
As can be seen from Figure 1, as ~ower level drops the axial shape index permitted the DNC LCO becomes Q by In the igure this f This was done for convenience in plotting only; in realty the Superimposed on this Figure is the local power density (LPD) LSSS for St. Lucie 2 Cycle 1. It can be seen from the figure that the installed LSSS for local
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power density becomes more restriciti ve than the DNB LCO, at approximately 77" power i.e.,
that,'onservativ'ely, the Q This fact provides the basis of the position SSS for LPD may be treated as more limiting than the DNB LCO below 3(5 power.
Below are listed selected values of overpower margin for different power levels and axial shape indices.
POWER ASI RODS OVERPOWER MARGIN 12K - 3 12'D IL 12$ ling PDIL 3(5 -.3 30'f. PDIL 3(5 3(5 PDIL 50$ ~ 3 50K PDIL 5(5 ~ 4 5P/. PDIL
110
(-.15,100)
(+.15, 100) 80 g
0 -3,75) (+,3,75
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LCO~
g 0 CALCULATEDDNB DNB LCO, TECHNICAL SPEC IF I CAT ION FIGURE 3.24 LOCAL POWER DENSITY TRIP SETPOINT, TECHNICAL SPECIFICATION FIGURE 2.2-2
-.6 -,4 -I2 0.0 .2 .4 .6 ASI FIGURE ST. LUCIE 2, CYCLE 1 - DNB LCO AND LOCAL POWER DENSITY TRIP vs ASI 1
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STATE OP PLORIDA COUNTY OP DADE J. W. Williams Jr. , being first duly sworn, deposes and says:
That he is a Vice President of Florida Power R Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Enclosure 1 is proprietary, and therefore, exempt from public disclosure in accordance with Section 9.5 (4) of the NRC "Rules of Practice", Title 10, Code of Pederal Regulations, per Attachment 1 of the basic letter provided by Combustion Engineering, Inc.
J. W. Williams, Jr.
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Subscribed and sworn to before me this day of , 19~&
'OTARY PUBLIC, in and for the County
<of- Dade, State of Florida.
a ROTARY PUBLIC STATE OF FLORIOA HY COHNISSIOH EXP. FEB lf, IBBB BO!iOEO THRU GEHERAL IHS. UHO.
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AFFIOAVIT PURSUANT TO 10 CFR 2.790 Combustion Engineering, Inc.
State of Connecti cut County of Hartford I, P. L. NcGill, depose and say that I am the Vice President, Commercial, of Combustion Engineering, Inc., duly authorized to make this affidavit, and have reviewed or caused to have reviewed the information which is identified as I
proprietary and referenced in the paragraph immediately below. I am submitting this affidavit in conformance with the provisions of 10 CFR 2.790 of the Commission's regulations in conjunction with the application of Florida Power 5
'Light Company for withholding this information.
I The information for which proprietary treatment is sought is contairied in the fol 1 owi n g document:
CEN-279(L)-P, Conservatism of Axial Shape Index DNB Limiting Condition for Operation Below 305 Power, April 1984.
This document has been appropriately designated as proprietary.
I have personal knowledge of the criteria and procedures utilized by.
Combustion Engineering in designating information as a trade'ecret, privileged or as confidential commercial or financial information.
Pursuant to the provi sions of paragraph (b ) (4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure, included in the above referenced document, shoul'd be withheld.
- 1. The information sought to be withheld from public disclosure are the values of thermal margin calculated for the reactor core and how these values can be translated into plant operational flexibility, which is owned and has been held in confidence by Combustion Engineering.
- 2. The information consists of test data or other similar data concerning a process, method or component, the application of which results in a substantial competitive advantage to Combustion Engineering.
- 3. The information is of a type customarily held in confidence by Combustion Engineering and not customarily disclosed to the public. Combustion Engineering has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system
- to determine when and whether to hold certain types of information in confidence. The details of the aforementioned system were provided to the Nuclear Regulatory Commission via letter DP-537 from F.M. Stern to Frank Schroeder dated December 2, 1974. This system was applied in determining that the subject document herein are proprietary.
- 4. The information is being transmitted to the Commission in confidence under the provisions of 10 CFR 2.790 with the understanding that it is to be received in confidence by the Commission.
- 5. The information, to the best of my knowledge and belief, is not available in public sources, and any disclosure to third parties has been made pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence.
- 6. Public disclosure of the information is likely to cause substantial harm to the competitive position of Combustion Engineering because:
- a. A similar product is manufactured and sold by major pressurized water reactor competitors of Combustion Engineering.
- b. Development of this information by C-E required thousands of manhours and tens of thousands of dollars. To the best of my knowledge and belief a competitor would have to undergo similar expense in generating equi valent information.
- c. In order. to acquire such information, a competitor would also require considerable time and inconvenience related to the calculation of similar thermal margin values and the translation of those values into plant operating flexibility.
- d. The information required significant effort and expense to obtain the licensing approvals necessary for application of the information.
Avoidance of this expense would decrease a competitor's cost in applying the information and marketing the product to which the information is applicable.
- e. The information consists of values of thermal margin calculated for the reactor core and how these values can be translated into plant operational flexibility, the application of which provides a competitive economic advantage. The availability of such information to competitors would enable them to modify their product to better compete with Combustion Engineering, take marketing or other actions to improve their product's position or impair the position of Combustion Engineering's product, and avoid developing similar data and analyses in support of their processes, methods or apparatus.
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- f. In pricing Combustion Engineeri'ng's products and services, significant research, development, engineering, analytical, manufacturing, licensing, quality assurance and other costs and expenses must be included.
The ability of Combustion Engineering's competitors to utilize such information without similar expen'diture of resources may enable them to sell at prices reflecting significantly lower costs.
- g. Use of the information by competitors in the international marketplace would increase their ability to market nuclear steam supply systems by reducing the costs associated with thei r technology development. In addition, disclosure would have an adverse economic impact on Combustion Engineering's potential for obtaining or maintaining foreign licensees.
Further the deponent sayeth not.
P. L. NcGill Yice President Commercial Sworn to before me this ~~" day* of April /9$+
N ary Public
~W, A'. 3MT~T ~0><>y 3 STATE OF CONNECTICUT No. 68542 COMMISSIOII EXPIRES AMRCtf 31,-1939