Rev 0 to Calculation M-99-0017, Deterministic Operational Assessment for Freespan ODSCC Degradation at Crystal River Unit 3| ML20202E675 |
| Person / Time |
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| Site: |
Crystal River  |
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| Issue date: |
01/22/1999 |
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| From: |
Sexton L
FLORIDA POWER CORP. |
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| To: |
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| Shared Package |
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| ML20202E648 |
List: |
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| References |
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| M-99-0017, M-99-0017-R00, M-99-17, M-99-17-R, NUDOCS 9902030123 |
| Download: ML20202E675 (6) |
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Category:ARCHIVE RECORDS
MONTHYEARML20202E6751999-01-22022 January 1999
Rev 0 to Calculation M-99-0017, Deterministic Operational Assessment for Freespan ODSCC Degradation at Crystal River Unit 3
ML20202E6911999-01-21021 January 1999
Rev 0 to Calculation AES-C-3543-1, Deterministic Operational Assessment for Free-Span Outside Diameter Stress Corrosion Cracking Degradation at Crystal River,Unit 3
ML20198N6091998-09-30030 September 1998
Rev 0 to FPC Calculation F-98-0010, FTI Calculation 32-5000218-00,Adjusted Ref Temperatures for 32 EFPY for CR-3
ML20198N5941998-09-30030 September 1998
Rev 0 to FPC Calculation F-98-0013, FTI Calculation 32-5001746-00,CR-3 32 EFPY P/T Limits
ML20217G6991998-04-0606 April 1998
Post-LOCA Boron Concentration Mgt for CR-3
ML20217G3831998-03-25025 March 1998
Rev 1 to M-98-0012, Leak Near RWV-129
ML20203K4891998-02-23023 February 1998
Rev 6 to Calculation M97-0098, Boron Dilution by Hot Leg Injection
ML20203J3151997-12-12012 December 1997
Rev 0 to S97-0541, Confirmatory Study of Selected Safe Shutdown Equipment Anchorage for USI A-46
ML20203F0791997-12-11011 December 1997
Rev 0 to M-97-0146, Post-LOCA Boron Concentration Mgt for CR-3
ML20203J3031997-12-0909 December 1997
Rev 0 to S97-0316, Seismic Evaluation of Emergency Feedwater Tank EFT-2
ML20203J3851997-12-0909 December 1997
Rev 0 to S97-0542, CR3 Structural Seismic Margin Evaluation (Study)
ML20203J3701997-12-0404 December 1997
Rev 1 to S-96-0013, Qualification of Tanks Per USI A-46
ML20203F1281997-11-28028 November 1997
Rev 0 to Calculation M97-0121, Pipe Stress Analysis, Evaluation of Effects of Pressurizer Surge Line LOCA Break on Svc Water Piping Sys at Crystal River,Unit 3
ML20202E3781997-11-0101 November 1997
Rev 1 to M97-0097, Low Pressure Auxiliary Spray Flow Rate for Boron Precipitation. W/Simulator Exercise ROT-9-200, Boron Precipitation Control
ML20203K4801997-09-0707 September 1997
Rev 0 to Calculation M97-0088, Hydraulic Analysis for LPI Hotleg Injection to Rcs
ML20196H0381997-07-18018 July 1997
to CR-3 15 EFPY Lwop Limits
ML20212D0011997-07-15015 July 1997
Rev 2 to CR3 15 EFPY LTOP Limits
ML20133K2671997-01-16016 January 1997
Press Release II-97-10, NRC Staff to Hold Predecisional Enforcement Conference to Discuss Crystal River Engineering Concerns W/Fl Power Corp
ML20133C6891997-01-0707 January 1997
Press Release II-97-04, NRC Names New Senior Resident Inspector at Crystal River Npp
ML20133B1891997-01-0202 January 1997
Press Release II-97-01, NRC Schedules Meeting at FPC Crystal River Plant
ML20135E3721996-12-0909 December 1996
Press Release II-96-103, NRC Commissioner Diaz to Visit Crystal River Nuclear Plant
ML20134N6561996-11-26026 November 1996
Press Release II-96-98, NRC Staff Issues Appraisal of Performance at Crystal River Nuclear Power Plant in Fl
ML20134G4401996-11-12012 November 1996
Press Release II-96-91, NRC Establishes Restart Panel for Crystal River Plant,Schedules Corrective Action Meeting in Atlanta
ML20129B6291996-10-22022 October 1996
Press Release II-96-86, NRC Reschedules Two Meetings 961031 at Crystal River Npp
ML20128K4231996-10-0707 October 1996
Press Release II-96-84, NRC Postpones Two Meetings Scheduled for Wednesday,961009 at Fl Power Corp Crystal River Plant
ML20129F0901996-10-0303 October 1996
Press Release II-96-82, NRC Schedules Two Meetings at Fl Power Corp Crystal River Plant
ML20116J8191996-08-0101 August 1996
Rev 0 to Qualification of Pipe Supports MSH-13B & MSH-27B
ML20116J9881996-08-0101 August 1996
Rev 0 to Evaluation of Effect of Bent Hanger Rod on Piping Analysis CR-5
ML20107L1821996-04-22022 April 1996
Rev 1 to 102075RCS01, Comparison of Calculated & Measured Pressures at Junction of Makeup Tank Surge Line & Pump Suction Pipe
ML20101M5941996-04-0404 April 1996
Mut/Bwst Hytran Analysis
ML20101M5891996-04-0404 April 1996
Mut Vapor Pressure Evaluation
ML20101M5801996-04-0404 April 1996
Mut Dissolved Gas Evolution Analysis
ML20101M5841996-04-0404 April 1996
Mut Vortexing Evaluation
ML20101M5641996-03-12012 March 1996
Allowable MUT-1 Indicated Overpressure Vs Indicated Level
ML20101M5611996-02-13013 February 1996
Effect of Mut Temp on Max Allowable Mut Pressure
ML20137G2831996-02-0909 February 1996
Rev 0 to S-96-0013, Qualification of Tanks Per USI A-46
ML20101M5521996-01-24024 January 1996
Potential Uncertainty in Total Head Loss from Bwst to Mut Tie-In
ML20101M5441996-01-17017 January 1996
Combination of Mut Pressure & Level Errors
ML20101M5291996-01-11011 January 1996
Mut Pressure
ML20101M5111996-01-11011 January 1996
Max Allowable Mut Pressure
ML20101M5201996-01-0505 January 1996
Head Loss in Bwst to Makeup Pump Flow
ML20084U2521995-06-0101 June 1995
EFIC - Main Steam Instrumentation Loop String Accuracy & Setpoints
ML20084U2701995-04-13013 April 1995
Rc Pressure (Wide Range) Loop Accuracy,RC-158-PT & RC-159-PT
ML20080U2461995-02-23023 February 1995
Nonproprietary Version of CR-3,Pressurizer Surge Nozzle Stresses
ML20078A3971994-12-0606 December 1994
Allowable Swhe Tube Blockage Vs Vhs Temp
ML20116J8051994-11-18018 November 1994
Rev 0 to Piping Analysis CR-5 Rev 0:Main Steam from Pen 107 to Turbine Stop Valve
ML20116J8121994-09-23023 September 1994
Rev 0 to Piping Analysis CR-6 Rev 0:Main Steam from Pen 201 to Turbine Stop Valve
ML20069M7091994-04-0808 April 1994
Rev 0 to CR-3 Analysis of S/N ECT Data for SG Tubes
ML20069M6951994-04-0808 April 1994
Rev 0 to Statistical Analysis of Defect Depth of SG Tubes
ML20069M7161994-03-25025 March 1994
Allowable Tube Wall Degradation for Pit-Type Defects
1999-01-22
[Table view]
Category:OPERATIONS SUPPORT-CALCULATIONS
MONTHYEARML20202E6751999-01-22022 January 1999
Rev 0 to Calculation M-99-0017, Deterministic Operational Assessment for Freespan ODSCC Degradation at Crystal River Unit 3
ML20202E6911999-01-21021 January 1999
Rev 0 to Calculation AES-C-3543-1, Deterministic Operational Assessment for Free-Span Outside Diameter Stress Corrosion Cracking Degradation at Crystal River,Unit 3
ML20198N5941998-09-30030 September 1998
Rev 0 to FPC Calculation F-98-0013, FTI Calculation 32-5001746-00,CR-3 32 EFPY P/T Limits
ML20198N6091998-09-30030 September 1998
Rev 0 to FPC Calculation F-98-0010, FTI Calculation 32-5000218-00,Adjusted Ref Temperatures for 32 EFPY for CR-3
ML20217G6991998-04-0606 April 1998
Post-LOCA Boron Concentration Mgt for CR-3
ML20217G3831998-03-25025 March 1998
Rev 1 to M-98-0012, Leak Near RWV-129
ML20203K4891998-02-23023 February 1998
Rev 6 to Calculation M97-0098, Boron Dilution by Hot Leg Injection
ML20203J3151997-12-12012 December 1997
Rev 0 to S97-0541, Confirmatory Study of Selected Safe Shutdown Equipment Anchorage for USI A-46
ML20203F0791997-12-11011 December 1997
Rev 0 to M-97-0146, Post-LOCA Boron Concentration Mgt for CR-3
ML20203J3031997-12-0909 December 1997
Rev 0 to S97-0316, Seismic Evaluation of Emergency Feedwater Tank EFT-2
ML20203J3851997-12-0909 December 1997
Rev 0 to S97-0542, CR3 Structural Seismic Margin Evaluation (Study)
ML20203J3701997-12-0404 December 1997
Rev 1 to S-96-0013, Qualification of Tanks Per USI A-46
ML20203F1281997-11-28028 November 1997
Rev 0 to Calculation M97-0121, Pipe Stress Analysis, Evaluation of Effects of Pressurizer Surge Line LOCA Break on Svc Water Piping Sys at Crystal River,Unit 3
ML20202E3781997-11-0101 November 1997
Rev 1 to M97-0097, Low Pressure Auxiliary Spray Flow Rate for Boron Precipitation. W/Simulator Exercise ROT-9-200, Boron Precipitation Control
ML20203K4801997-09-0707 September 1997
Rev 0 to Calculation M97-0088, Hydraulic Analysis for LPI Hotleg Injection to Rcs
ML20196H0381997-07-18018 July 1997
to CR-3 15 EFPY Lwop Limits
ML20212D0011997-07-15015 July 1997
Rev 2 to CR3 15 EFPY LTOP Limits
ML20116J9881996-08-0101 August 1996
Rev 0 to Evaluation of Effect of Bent Hanger Rod on Piping Analysis CR-5
ML20116J8191996-08-0101 August 1996
Rev 0 to Qualification of Pipe Supports MSH-13B & MSH-27B
ML20107L1821996-04-22022 April 1996
Rev 1 to 102075RCS01, Comparison of Calculated & Measured Pressures at Junction of Makeup Tank Surge Line & Pump Suction Pipe
ML20101M5941996-04-0404 April 1996
Mut/Bwst Hytran Analysis
ML20101M5891996-04-0404 April 1996
Mut Vapor Pressure Evaluation
ML20101M5841996-04-0404 April 1996
Mut Vortexing Evaluation
ML20101M5801996-04-0404 April 1996
Mut Dissolved Gas Evolution Analysis
ML20101M5641996-03-12012 March 1996
Allowable MUT-1 Indicated Overpressure Vs Indicated Level
ML20101M5611996-02-13013 February 1996
Effect of Mut Temp on Max Allowable Mut Pressure
ML20137G2831996-02-0909 February 1996
Rev 0 to S-96-0013, Qualification of Tanks Per USI A-46
ML20101M5521996-01-24024 January 1996
Potential Uncertainty in Total Head Loss from Bwst to Mut Tie-In
ML20101M5441996-01-17017 January 1996
Combination of Mut Pressure & Level Errors
ML20101M5111996-01-11011 January 1996
Max Allowable Mut Pressure
ML20101M5291996-01-11011 January 1996
Mut Pressure
ML20101M5201996-01-0505 January 1996
Head Loss in Bwst to Makeup Pump Flow
ML20084U2521995-06-0101 June 1995
EFIC - Main Steam Instrumentation Loop String Accuracy & Setpoints
ML20084U2701995-04-13013 April 1995
Rc Pressure (Wide Range) Loop Accuracy,RC-158-PT & RC-159-PT
ML20080U2461995-02-23023 February 1995
Nonproprietary Version of CR-3,Pressurizer Surge Nozzle Stresses
ML20078A3971994-12-0606 December 1994
Allowable Swhe Tube Blockage Vs Vhs Temp
ML20116J8051994-11-18018 November 1994
Rev 0 to Piping Analysis CR-5 Rev 0:Main Steam from Pen 107 to Turbine Stop Valve
ML20116J8121994-09-23023 September 1994
Rev 0 to Piping Analysis CR-6 Rev 0:Main Steam from Pen 201 to Turbine Stop Valve
ML20069M7091994-04-0808 April 1994
Rev 0 to CR-3 Analysis of S/N ECT Data for SG Tubes
ML20069M6951994-04-0808 April 1994
Rev 0 to Statistical Analysis of Defect Depth of SG Tubes
ML20069M7161994-03-25025 March 1994
Allowable Tube Wall Degradation for Pit-Type Defects
ML20151J5101994-02-14014 February 1994
Rev 0 to Seismic Verification of Tanks - SQUG Methodology
ML20151J4641993-10-0707 October 1993
Rev 0 to Floor Response Spectrum Generation
ML20151J4961992-12-30030 December 1992
Rev 0 to Floor Response Spectrum Generation
ML20216A9131991-06-27027 June 1991
Non-proprietary MK-B9 Spectrum LOCA Lhr Limit Analyses for 177-Fuel Assembly Lowered Loop Plants
1999-01-22
[Table view] |
Text
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Florida INTEROFFICE CORRESPONDENCE
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SUBJECT:
Crystal River Unit 3 Quality Record Transmitral - Analysis / Calculation i To: Records Management - NR2A The following analysis / calculation package is submitted as the OA Record copy-i occc.o one os.,:vure.7 iou.ripecarion e.uussa ac. s svstiu s. rotas pacts rm.suir c M- M-bol7 fo R- 34 TlTLt ET8'A #1/W/((~/[ hWAAIlN$$- S$NNENT $$ Sk$$S$Al 0NW bfGRAbn7~tpr1 A r [f r'STM byfR YMr 3.
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Use Tag number only for valid tag numbers (i.e., RCV-8, SWV-34, DCH 99); otherwise, use Part number field (i.e., CSC14599, AC1458,. If Tnore space is required, write See Attachment
- and list on separate sheet.
- *FOR RECORDS MANAGEMENT USE ONLY *
- Quality Record Transmittal received and information entered into SEEK.
Entered by: Date (Retum copy of Quality Record Transmittal to DE Support Specialist.)
! orsioN NEER DATE vtRIPICATioN EholN ER DATE SUPE / Iso I (No, DATE
/k2/99 n'/A n' 1 Y22.
cc: Nuclear Projecte (If MAR /CGWR/PEERE Calculation Review form Part lit actions required OY'. 6No l
'? No (if Yee. eend copy of the Calcutemn to the Responsiole Organization (s)
Returc to Service Related) O Yes I' 'l Supervisor, Config. Mot. Info. identified in Part 111 on the Csiculation Review form.)
Mgr., Design Engineenna (Original) w/ attach l
Mgr., Radiological Emergency Planning wlattach O Yes No l
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N~ $$- 00l7 PARTI. DESIGN ASSUMPTION / INPUT REVIEW: APPLICABLE Yes d No The following organizations have reviewed and concur with the design assumptions and inputs ,
identified for this calculation- l Systems Er..rineering l
$. . o. . I Nuclear Plant Operations -
O THE At9' _
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PARTIS- RESULTS REVIEW: APPLICABLE Yes N The following organizations have reviewed and concur with the results of this calculation and understand the actions which the organizations must take to implement the results.
System Engineering
- s. .o .
Comments:
Nuclear Plant Operations
.o Comments:
Safety Analysis Group Yes N/A S.n.=wo .
Comments:
Nuclear Plant Maintenance Yes N/A s>gn.twr.o.t.
Comments:
Nuclear Licensed Operator Training O Yes O N/A s u.o. .
Comments:
Manager, Nuclear Regulatory Compliance Yes N/A s..n .o .
Comments:
Sr. Radiation Protection Engineer Yes O N/A -
n .o .
Comments:
Nuclear Plant EOP Group O Yes N/A s n.-wo Comments:
Design Engineering [MObtdC&) [ Yes O N/A S,._ .o .
Comments:
OTHER: Yes N/A s .o .
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NM CALCULATION REVIEW Page 2 of 2 l
excutario o en I M Dot 7 de v' d i l PART lil CONFIGURATION CONTROL: APPLICABLE O Yes YNo PC # f, l The following is a list of Plant procedures / lesson plans /other documents and Nuclear Engineering calculations which require updating based on calculation results review:
Documen,t Date Recuired Responsible Oroanization g
Upon completion, generate a Precursor Card in accordance with CP 111 for tracking of actions for any items identified in Part 111. If calculations are listed, a copy shall be sent to the original file and the calculation log updated to reflect this impact.
PART IV - NUCLEAR ENGINEERING DOCUMENTATION REVIEW The responsible Design Engineer must thoroughly review the below listed documents to assess if the calculetion requires revision to these documents, if "Yes," the change authorizations must be listed below and issued concur ntly with the calculation.
Ennanced Design Basie Document O vee nC vender cuetification Package 'voa'>
FSAR O Yes No As'**** Topical Design Basi Doc. O vee INo C81 rr t' improved Tech. Specificauci O vs. O No (L**8 E&SOPM O vee WNo rresi \
tmoroved Tech. Spec. Bases O vos O No Lam'81 Other Documente reviewed:
Config. Mgmt. Info. System O vee TNo IC'o**> 0 vee O No Design Basie Document O vos go rre O ve. O No man.on ooc. aussan=cs>
Appendix R Fire Study O vee No rTCa O ve. O No cau.seooc.asasaence Fira Hazardous Analysis O vee No frc O vee O No iC=aNGE o0C. asegetNCEb NF7A Code Conformance Document O vee No trc C v.e O No_
man cs occ. na.eazucri PART V PLANT REVIEWS / APPROVALS FOR INSTRUMENT SETPOINT CHANGE PRC/DNPO appravalis required if a setpoint is to be physically changed in the plant through the NEP 213 process.
PRC Review Required Yes No ,v[A PRC Chairman / /Date DNPO Review Required Yes No A DNPo /Date Ot$iGN ENGIN(1% Dart DislGN ENGIN(fR
- PRINTED NAME Rev. est g,xtve. 4 Nge313 grees3eeree
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18 APPLIED TECHNOLOGY FAX 382/863-4697 1
1 January 21,1999 l 1
Mr. Larry Sexton Florida Power Corporation Crystal River Energy Complex
' 15760 West Power Line Street l i
CrystalRiver, FL 34428-6708 RE: Carifications to APTECH's Calculation AFS-('AS4L1, " Deterministic Operational Assessment for Free-Span Outside Diameter Stress Corrosion Cracking Degradation at Crystal River, Unit 3" (AFTECH Pmject AES 98103543-10)
Dear Mr. Sexton:
Per your request, the following clarifications are provided conceming AFTF.CR'n Calenlation AES-C-35431 transmitted to you under separate cover dated December 23,1998.
- 1. The calculation used the terminology of EFPY for the term of operation evaluated in the calculation. 'Ihe intended definfrion of EFPY, in the calculation,is time at or above 500*F.
- 2. The bases for the calculation are as follows:
- Best estimate growth rate from field data
- Probability of detection based on resolution analyst calls that included all system error
- Extreme value statistics for deterruinins limiting flaw depth at end-of-cycle
- 95/95 confidence limits on burst pressure
- Rigorous Monte Carlo statistical simulation Please contact meif additionalinformation is required. I may be reachedin AITECH's Sunnyvale, California office at 408/745-7000 or paged at 888/580-0053.
Sinecrcly,
~
s i ota Kenneth R. Craig Program Manager. Nuclear 'sion KRC/ web Enclosure 3543 LTR. DOC APTECH ENGINEERING SERVICES, INC.
isee nsAuwooo avsNUE D SUNNYVALe "J CA Meet (40s) 746 7e00 0 FAX (40s) 7s44448 O BA4alL: apteeneuttu.netoom.com HOUSTON, TX D (281) 584 3200 0 PITrSaVRoH, PA D (412) 923 6833 O BETHLEHEM. PA O (610) 866-7347 CHAMLoTTE. NC D (704) 8654318 O CHATTANOOGA. TN O (423) 63777 O WASHWGTON, DQ O (3o1) 8664809
l 1
i i
l Clarifications to APTECH's Calculation AES-C-3543-1, l
" Deterministic Operational Assessment for Free-Span Outside Diameter Stress Corrosion Cracking Degradation at Crystal River, Unit 3 l
- 1. The calculation used the terminology of EFPY for the tenn of operation evaluated in the calculation. The intended definition of EFPY,in the calculation, is time at or above 500*F.
- 2. The bases for the calculation are as follows:
- Best estimate growth rate from field data
- Probability of detection based on resolution analyst calls that included all system erIOr
- Extreme value statistics for determining limiting flaw depth at end-of-cycle
- 95/95 confidence limits on burst pressure
- Rigorous Monte Carlo statistical simulation A dA \ /!90 Prepared by Date d d 0 Qutl-
( ~
C
- 2nrw99 Verified by Date 3543_LTR. DOC
.