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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
_
- m% Florida INTEROFFICE CORRESPONDENCE
& att Power A C-1L~
Q""*"'" Nuclear Engineering NTO2 240-3188 OMce MAC Telephone
SUBJECT:
Crystal River Unit 3 Quality Record Transmittal Analysis / Calculation To: Records Management - NR2A The following analysis / calculation package is submitted as the QA Record copy DoCNO (FPC DOCUMENT IDENTIFICATION NUMDER) REV SYSTEM (S) tot AL PAGES TR ANSMITTED M 97-0098 6 RCS,DH G4; TITLE Boron Dilution by Hot Leg injection KWDs DDEPmFY KEYWORDS FOR LATER RETR: EVAL) sun,p decay heat, LPI DXREF (REFERENCES OR FLES . LIST PRIMARY FLE FtRsT) 51-5000519-06 VEND (VENDCR NAMC) VENDOR DOCUMENT NUMBER (DXREF) SUPERSEDED DOCUMENTS (DXREl)
FTl 51-5000519-06 M 97 0098 Rev 4 DHP 1 A,1B l DHV 3,4,5,6 l ,
MUP-1 A,18,1 C l l DH 1 FE1, FE2 l l DH-38-FE l l COMMENTS (USAGE RESTRtCTIONS. PROPR'ETARY. ETC )
Revision 5 of the FTl document was not issued as an FPC document. Revision 6 is issued as FPC calculation M 97-0098 Revision 6, to maintain consistency with the FTl revision level NOTE:
Use Tag number onl/ for valid tag numbers (i.e , RCV-8 SWV-34, DCH-99); otherwise, use Part number field) e, CSC14599, AC1459). If more space is required, wnte"See Attachment" and list on separate sheet.
- *FOR RECORDS MANAGEMENT USE ONLY '-
Quality Record Transmittal received and information entered irto SEEK.
Entered by: Date (Return copy of Quality Record Transmittal to NOE Support Specialist.)
DE31GN ENGINEER ##8M/ DATE VER:FICATION ENGINEER DATE SupERV!SCR, NUCLEAR ENO CATE
.fCuad %,f4-
~
y 4 4/97 M/.4 -Wm w 2-/43h?
cc: Nuclear Projats (If MAR /CGWR!PEERE Calculation Review form Part 111 actions required Oyes [No Return to service Related) O Yes E No (If Yes, send copy of the form to Nuclear Regulatory Assurance and a supervisor, Config Mgt. Info. copy of the Calculation to the Responsible Organization (s) identified in Mgr., Nucl. Operations Eng. (Original) w/ attach Part til on the Calculation Review form.)
y'g(/ [ set?!UD al. SkKM 9803050105 980227 PDR ADOCK 05000302 P PDR _ _ _ _ _ _ _ _ _ _ _ _ _
j
-- _---- -.. - - . . - _ _ - - . _ - _ - . - . . . . - ~ . _ .. - . - -
f , y' N...........
g ANALYSIS / CALCULATION 4-C4vM rau
SUMMARY
a olSCIPUNE CONTROL No.
nocOMENT IDENTIFICATION NUMBER PEVISION LEVEL M 97-0098 6 TITLt CLAS$$iCAtl0N (CHECE ONE)
Boron Dilution by Hot Leg Injection @ safety Rested Non Safety Related M AR.SetCowR.etEnt nun'stR N/A VTNDOR DOCUMENT NUMBER 51-500019-06 APPROVAL PRINTED SIGNATURES NAME Dssign Engineer MA g My4_ V. M. Esquillo Dste of/hff Verification Engineer N/A Date Supervisor ^ R. W. Knoll Date .2/30/#
ITEMS REVISED Revision 6 takes into account higher LPl temperatures, and addresses CR-3 comments. This document replaces Revision 0 completely. All FPC comments were incorporated into the final FTl document.
PURPO51 SUMM AA Y The purposa of this calculation is to demonstrate the effectiveness of the hot leg injection (HLI) method for post LOCA boron concentration control. This method directs flow from one low pressure injection (LPI) pump backward through the other (inactive) LPI pump, and through the decay heat drop line into the hot leg.
Ultimately, a reverse flow through the core to the break is induced.
AtSutT$
SUMMARY
The analysis demonstrated that hot leg injection is an effective method for post-LOCA boron concentration control, in addition _to_this result, FTl recommended that to ensure the effectiveness of this method, the reversa flow through the decay heat drop line be maintained at 500 gpm. This minimum flow rate was found to be effective in both small break and large break LOCA scenarios.
1
)
i Rev. 3/97 4
[^^N
(/N N~
CALCULATION REVIEW CALCMV FRM Page 1 of 2 CALCULATION No /RIV.
,// f/- .x)ff M4 PART l - DESIGN ASSUMPTION / INPUT REVIEW: APPLICABLE @ Yes O No The following organizations have reviewed and concur with the design assumptions and inputb identified for this calculation:
Nuclear Plant Technical Support System Engr 2!t3[78 #tutf 54"**T Nuclear Plant Operations f M e"./M"Ar/4 OTHER(S) Sqnatwo;Date y m - Ift- 0 6 cLA c/d .2hshs Signatis/Dato C6 W Mk $cdond .
7.flSf97 g,y,poggg Segnatws/Date PART ll RESULTS REVIEW: APPLICABLE @ Yes O No 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.
Nuclear Plant Technical Support A 7 !!f P # //l85 System Engr SS"*'* '" V Nuclear Plant Operations # s @ # #fAf//-
senatwezomG Nuclear Plant Maintenance C Yes @M **"*'**'**
Nuclear Licensed Operator Training C Yes @M Manager, Site Nuclear Services O Yes @ N/A Sr. Radiation Protcction Engineer 55"*'* * **
O Yes @ N/A Nuclear Plant ECP Group ,
@ Yes D N/A 5 MN & AYMM smnewy. p m a q )gg y
$ Ift. $l$ R,<f 3heln C 83tEL ex.nu .1k.,_.... k dshs e.n. ma Rev_12,17 19 & / M i
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-[ / $
\* CALCULATION REVIEW Page 2 of 2 C*1CULAftoN Nolmfy.
M f7-Mf7 W A PART 111 CONFIGURATION CONTROL: ,,PPLICABLE
- O Yes @ No The following is a list of Plant procedures /lessan plans/other documents and Nuclear Engineering calculations which require updating based on calculation results review:
Document Date Reauired Resnonsible Orcanization r
Upon completion, forward a copy to the Manager, Nuclear Regulatory Asst.rance Group for tracking of actions if tny items are identified in Part 111. If calculations are listed, a copy shall be sent to Sl'e 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 calculation requires revision to these documentr.. If "Yes," the change authorizations must be listed below and issued concurrently with the calculation.
Fnhanced Design Basis Document O vos M No (Tcal Vendor O'.:alification PackageO ves 3 NorvoP')
FSAR O ves a No "-** Topicai Desian Basis Doc. O ves 2 NoffC8)
Improved Tech. Specific:. tion O ves E No it*"**> E/SQPM O ves E Norresi improved Tech. Spec. Bases O ves S No (L*"*8) Other Documents reviewed:
Config. Mgmt. Info. System O ves G No (ciopsi O yes O No iCn.Gs Dec asFEnENCu Analysis Dasis Document O ves E No (TC81 O ves O No ICHAhGC 00C. RtFERENC31 Desi0n Basis Document O ves @ No C*) O ves O No _
(CMANGE DOC. PEFEPEMCEI Appendix R Fire Study O ves 2 No (Tc8) O ves C No tCHANGt WOC. REFEPENCEI Fire Hazardous Analysis O vas G No ffC81 __
O ves O No ICMANGE DOC. REFte ~7sil NFPA Code Conformance Document O ves 3 No (Tcal C ves O No tCHANGE DOC. FEFERENCII PART V PLANT REVIEWS / APPROVALS FOR INSTRUMENT SETPOINT CHANGE PRC/DNPO approvalis required if a setpoint is to be physically changed in the plant throt'gh the NEP 2'3 process.
PRC Review Required Yes No PRC Chairman /Date DNPO Review Required Yes @ No DNPO lDate oESIGN ENGINEEADATE oEStGN ENGINEER . PRINTEO NAME I Y '
u F.ew.12/97
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . l
