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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20154E4211998-01-31031 January 1998
Amend 1 to CE NPSD-911, Analysis of Moderator Temperature Coefficients in Support of Change in TSs End of Cycle Negative Mtc Limit. App a Consists of Responses to 970226 NRC RAI
ML20141L9791997-02-28028 February 1997
Suppl 8 to Annual Rept on Abb CE ECCS Performance Evaluation Models, Final Rept
ML20112G5301996-06-10010 June 1996
Annual Report on Abb CE ECCS Performance Evaluation Models
ML20082H4011995-02-28028 February 1995
Annual Rept on Abb CE ECCS Performance Evaluation Models, Feb 1995
ML20073D4561994-09-30030 September 1994
Verification of Cecor Coefficient Methodology for Application to PWRs of Entergy Sys
ML20063C7571993-12-31031 December 1993
Qualification of Reactor Methods for Pressurized Water Reactors of Entergy Sys
ML20079C1621993-05-31031 May 1993
Analysis of Moderator Temp Coefficients in Support of Change in TS of EOC Negative Mtc Limit
ML20044G5181993-04-30030 April 1993
Suppl 4 to Annual Rept on C-E ECCS Codes & Methods for 10CFR50.46, Final Rept
ML20127M2731992-11-30030 November 1992
Analysis of Capsule W-97 Entergy Operations,Inc Waterford Generating Station,Unit 3,Reactor Vessel Matl Surveillance Program
ML20153E0561988-05-31031 May 1988
Errata to Handbook on Flaw Evaluation Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds, Consisting of Page Inadvertently Omitted from Original Rept
ML20154D6281988-05-31031 May 1988
Handbook of Flaw Evaluation Waterford Unit 3 Reactor Vessel Outlet Nozzle to Shell Welds
W3P86-3328, Boric Acid Concentration Reduction Effort,Technical Bases & Operational Analysis,Waterford Nuclear Power Plant Unit 31986-10-31031 October 1986
Boric Acid Concentration Reduction Effort,Technical Bases & Operational Analysis,Waterford Nuclear Power Plant Unit 3
ML20215H6961986-10-31031 October 1986
Nonproprietary Statistical Combination of Uncertainties for Waterford 3
ML20203M8701986-07-31031 July 1986
Nonproprietary Waterford Unit 3,Cycle 2 Shoulder Gap Evaluation
ML20155J5231986-05-31031 May 1986
Rev 1 to Functional Design Requirement for Core Protection Calculator
ML20155J5051986-05-31031 May 1986
Rev 1 to Functional Design Requirements for Control Element Assembly Calculator
ML20155J4911986-05-31031 May 1986
Rev 0 to Core Protection Calculator/Control Element Assembly Calculator Software Mods for CPC Improvement Program Reload Data Block
ML20151Z0521986-01-31031 January 1986
Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure
ML20151Z0641986-01-31031 January 1986
Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines
ML20134N3021985-07-31031 July 1985
Rev 00 to Functional Design Requirement for Core Protection Calculator
ML20134N2941985-07-31031 July 1985
Rev 00 to Functional Design Requirement for Control Element Assembly Calculator
ML20080Q4551984-01-16016 January 1984
Nonproprietary, Response to NRC Question on Waterford-3 Bypass Flowrate
ML20077J6801983-07-15015 July 1983
Nonproprietary Rev 1 to Final Assessment of Waterford-3 Fuel Structural Integrity Under Faulted Conditions. Info Deleted
ML20028F9431982-12-31031 December 1982
Responses to Questions on Cesec.
ML20050B1721982-03-31031 March 1982
Nonproprietary Version of Cpc/Ceac Protection Algorithm Test Plan.
ML20050C5301982-03-31031 March 1982
Nonproprietary Version of Cpc/Ceac Software Mod for Waterford 3.
ML20050C5311982-03-31031 March 1982
Nonproprietary Version of Safety Evaluation of Reactor Power Cutback Sys.
ML20039F8661981-12-31031 December 1981
Evaluation of Pressurized Thermal Shock Effects Due to Small Break LOCAs W/Loss of Feedwater for Waterford Reactor Vessel.
1998-01-31
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217F2891999-10-13013 October 1999
Drill 99-08 Emergency Preparedness Exercise on 991013
ML20217G7211999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Waterford 3 Ses. with
ML20211Q2141999-08-31031 August 1999
Monthly Operating Rept for Aug 1999 for Waterord 3 Ses.With
ML20210Q6361999-07-31031 July 1999
Corrected Monthly Operating Rept for July 1999 for Waterford 3
ML20210S0581999-07-31031 July 1999
Monthly Operating Rept for July 1999 for Waterford 3.With
ML20210D8951999-07-23023 July 1999
Safety Evaluation Accepting First 10-yr Interval Inservice Insp Plan Requests for Relief ISI-018 - ISI-020
ML20209H3781999-06-30030 June 1999
Monthly Operating Rept for June 1999 for Waterford 3 Ses. with
ML20195J8951999-06-17017 June 1999
Safety Evaluation Granting Relief for Listed ISI Parts for Current Interval,Per 10CFR50.55a(g)(5)(iii)
ML20207E8631999-06-0303 June 1999
Safety Evaluation Accepting Licensee 990114 Submittal of one-time Request for Relief from ASME B&PV Code IST Requirements for Pressure Safety Valves at Plant,Unit 3
ML20195K3391999-05-31031 May 1999
Monthly Operating Rept for May 1999 for Waterford 3 Ses.With
ML20195C3041999-05-28028 May 1999
Annual Rept on Abb CE ECCS Performance Evaluation Models
ML20206S7401999-04-30030 April 1999
Monthly Operating Rept for Apr 1999 for Waterford 3.With
ML20205T2621999-04-22022 April 1999
LER 99-S02-00:on 990216,contract Employee Inappropriately Granted Unescorted Access to Plant Protected Area.Caused by Personnel Error.Security Personnel Performed Review of Work & Work Area That Individual Was Involved with
ML20205N9671999-03-31031 March 1999
Monthly Operating Rept for Mar 1999 for Waterford 3 Ses.With
ML20205E8531999-03-30030 March 1999
Corrected Pages COLR 3/4 1-4 & COLR 3/4 2-6 to Rev 1, Cycle 10, Colr
ML20205A6331999-03-25025 March 1999
SER Accepting Request to Use Mechanical Nozzle Seal Assemblies as an Alternative Repair Method,Per 10CFR50.55a(a)(3)(i) for Reactor Coolant Sys Applications at Plant,Unit 3
ML20204H1401999-03-23023 March 1999
Rev 1 to Engineering Rept C-NOME-ER-0120, Design Evaluation of Various Applications at Waterford Unit 3
ML20204H1231999-03-22022 March 1999
Rev 1 to Design Rept C-PENG-DR-006, Addendum to Cenc Rept 1444 Analytical Rept for Waterford Unit 3 Piping
ML20204H2451999-03-22022 March 1999
Rev 2 to C-NOME-SP-0067, Design Specification for Mechanical Nozzle Seal Assembly (Mnsa) Waterford Unit 3
ML20204F0791999-03-17017 March 1999
Rev 1 to Waterford 3 COLR for Cycle 10
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207F3491999-03-0505 March 1999
LER 99-S01-00:on 990203,contraband Was Discovered in Plant Protected Area.Bottle Was Determined to Have Been There Since Original Plant Construction.Bottle Was Removed & Security Personnel Performed Search of Area.With
ML20204B5141999-02-28028 February 1999
Monthly Operating Rept for Feb 1999 for Waterford 3.With
ML20203H8591999-02-17017 February 1999
Safety Evaluation Accepting Licensee Second Ten Year ISI Program & Associated Relief Requests for Plant,Unit 3
ML20199H6261999-01-21021 January 1999
Safety Evaluation Accepting Classification of Instrument Air Tubing & Components for Safety Related Valve Top Works.Staff Recommends That EOI Revise Licensing Basis to Permit Incorporation of Change
ML20199C9101998-12-31031 December 1998
Monthly Operating Rept for Dec 1998 for Waterford 3.With
ML20196F4911998-12-0101 December 1998
SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2
ML20206N4131998-11-30030 November 1998
Monthly Operating Rept for Nov 1998 for Waterford 3.With
ML20195C4841998-11-0606 November 1998
SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program
ML20195E5161998-10-31031 October 1998
Monthly Operating Rept for Oct 1998 for Waterford 3.With
ML20155C1351998-10-26026 October 1998
Rev B to Entergy QA Program Manual
ML20154K0801998-09-30030 September 1998
Monthly Operating Rept for Sept 1998 for Waterford 3 Ses. with
ML20151W8331998-08-31031 August 1998
Monthly Operating Rept for Aug 1998 for Waterford,Unit 3. with
ML20237B6831998-08-17017 August 1998
LER 98-S01-00:on 980723,discovered That Waterford 3 Physical Security Plan,Safeguards Document Was Not Under Positive Control of Authorized Person at All Times.Caused by Human Error/Inappropriate Action.Counseled Employee Involved
ML20237C5661998-08-17017 August 1998
Safety Evaluation Accepting Licensee Request for Exemption from Section Iii.O of Appendix R to 10CFR50
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
ML20237B5261998-07-31031 July 1998
Monthly Operating Rept for July 1998 for Waterford 3
ML20236S9031998-07-22022 July 1998
SER Accepting Rev 19 to Quality Assurance Program for Waterford Steam Electric Station,Unit 3
ML20198H3911998-07-14014 July 1998
Non-proprietary Rev 5 to HI-961586, Thermal-Hydraulic Analysis of Waterford-3 Spent Fuel Pool
ML20236N4181998-06-30030 June 1998
Monthly Operating Rept for June 1998 for Waterford,Unit 3
ML20248E7781998-06-0101 June 1998
Annual Rept on Abb CE ECCS Performance Evaluation Models
ML20249A4711998-05-31031 May 1998
Monthly Operating Rept for May 1998 for Waterford 3 Ses
ML20196A4051998-05-31031 May 1998
Rept of Facility Changes,Tests & Experiments,Per 10CFR50.59 for 970601-980531. with
ML20198H4681998-05-20020 May 1998
Non-proprietary Rev 1 to HI-981942, Independent Review of Waterford Unit 3 Spent Fuel Pool Cfd Model
ML20247A3891998-05-0101 May 1998
SG Eddy Current Examination (8th Refueling Outage)
ML20247F6761998-04-30030 April 1998
Monthly Operating Rept for Apr 1998 for Waterford,Unit 3.W/
ML20217M8951998-04-30030 April 1998
QA Program Manual
ML20217P8281998-04-0707 April 1998
Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i)
ML20216B1751998-03-31031 March 1998
Monthly Operating Rept for Mar 1998 for Waterford 3 Ses
ML20217M1411998-03-0303 March 1998
Rev 2 of Waterford 3 Cycle 9 Colr
1999-09-30
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _
ARD477M/2 WATERFORD STEAM ELECTRIC STATION UNIT 3 CEN-343(C)-NP
?
- g 4 Statistical Combination of Uncertainties for Waterford-3 i
I I
October 1986 Nuclear Power Systems
! COMBUSTION ENGINEERING, INC.
Windsor, Connecticut m
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'O 8610240093 861013 PDR ADOCK0500g2 P
ARD477M/3 l LEGAL NOTICE
, l This report was prepared as an account of work sponsored by (
Combustion Engineering, Inc. Neither Combustion Engineering nor any person '
acting on its behalf: t
~
- 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 usefulness of
- the information contained in this report, or that the use of any information, 4 apparatus, method, or process disclosed in this report may not infringe l privately owned rights; or .
- b. Assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method or process disclosed in this report.
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ARD477M/4 STATISTICAL COMBINATION OF UNCERTAINTIES FOR WATERFORD-3 c.
Statistical Combination of Uncertainties (SCU) methods will be applied to the detennination of Limiting Conditions for Operation (LCO) end Limiting Safety System Setpoints (LSSS) on Linear Heat Rate (LHR) and Departure from Nucleate Boiling Ratio (DNBR) for Waterford Unit 3 beginning with Cycle 2. In the SCU program, the overall uncertainty factors for the Core Operating Limit Supervisory System (COLSS) and the Core Protection Calculator System (CPCS),
along with the minimum DNBR limit, are detennined at least at a 95/95 probability / confidence level.
The methodology used for Waterford-3 is similar to that described for SONGS Units 2 and 3 in Reference 1. Input and calculated data appropriate for Waterford-3 will be used to determine final COLSS and CPCS uncertainty factors and the minimum DNBR limit value.
Minor changes were made to the SCU methodology as part of the CPC Improvement Program (CIP, References 2 and 3). These changes, briefly discussed with NRC in November 1985, involve no substantial difference in basic methodology or results. The changes made to the SCU methodology as part of the CIP involve o
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Figure 1 shows the revised simulator flow paths replacing Figures
'of Reference 1 Part II and Figures of Reference 1
_i _ ._.
Part III.
.i Table 1 lists uncertainty components to be considered in the Waterford-3 SCU program, grouped according to application method.
I I
4 t
- - . . - . . . . . - _ . . - - . _ . - - . . . . - - .. .. ~ .. , - , -. . . -
ARD477M/7 Table 1 Uncertainty Components Considered in Waterford-3 SCU Program A. Combined Statistically in Minimum DNBR Limit (per Reference 1, Part I)
- 1. Inlet flow distribution uncertainties
- 2. Enthalpy rise factor
- 3. Systematic pitch uncertainties 4 Tystenatic clad 0.D. uncertainties
- 5. Mc4% _ flux factor
'6. C.i+1 (HF correlation uncertainties (including NRC imposed cross-vi:lidation uncertainty)
- 7. TORC code uncertainty
- 8. Fuel rod bow penalty on DNBR
i
- applied deterministically
~ ~
. . Y . . . - . . - _ _ _ -- _ _ - _____
~
~. -. . . . _ . . _ . . - . . - . . . .
I ARD477M/8
..===
Table 1 (continued) i C. Applied Statistically to Overall Uncertainty Factors in[ ]
w
- 1. Radial peaking factor measurement uncertainty
- 2. Fuel and poison rod bow penalty on radial peaking factors
- 3. Computer processing uncertainties
- 4. Reactor core simulator modeling error
- 5. LHR engineering factor (CPC)
D. Appl ed Determinist 1cally to Overall Uncertainty Factors in -
- 1. LHR engir.eering factor (COLSS)
- 2. LHR axial densification factor
~
- 3. F
- 4. CFC power calibration allowance E. No Longer Applied in SCU Program 1-
,1
g ,,p s. w e d . Awhme h4 bWM " MO N - h * *O' #
Me e FIGURE 1 FLOW CHART F0R COLSS AND CPCS UNCERTAINTY ANALYSIS M
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l 1
w M
?-~- -- . . . - _ AN?N .- - N
...______.._..__._1- . _ - . - . _ . . . _ _ . . . _ _ _ . . _ _ _ . _ _ _. . _ _
ARD477M/6 R_eferences
- 1. ' CEN-283(S)-P, " Statistical Combination of Uncertainties," Part I, June 1984, Part II and Part III, October 1984.
- 2. CEN-308-P-A, "CPC/CEAC Software Modifications for the CPC Improvement Program," April 1986.
- 3. CEN-310-P-A, "CPC and Methodology Changes for tt:e CPC Improvement Program," April 1986.
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