ML20071L611
| ML20071L611 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 06/30/1994 |
| From: | Dandini V, Darby J, Staple B, Whitehead D SANDIA NATIONAL LABORATORIES, SCIENCE & ENGINEERING ASSOCIATES, INC. |
| To: | NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| CON-FIN-L-1923 NUREG-CR-6143, NUREG-CR-6143-V02PT2, NUREG-CR-6143-V2-P2, NUREG-CR-6143-V2PT2, SAND93-2440, NUDOCS 9408030187 | |
| Download: ML20071L611 (609) | |
Text
{{#Wiki_filter:. NUREG/CR-6143 SAN D93-2440 Vol. 2, Part 2 Eva:Luation 0:? Potentia: Severe Acciden~:s During Low Power anc Sautdown Operations at: Granc Gul:f, Uni: 1 Analysis of Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage 1 Internai Events Appendices A to H Prepared by J.1)arby,1). Whitehead,11. Staple, V.1)andini l br_ndia National Laboratories @peratcd by @andia Corporation j
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l Prepared for (U.S. Nuclear Regulatory Commission EsRS286"I32888216 P PDR
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NUREG/CR-6143 SAND 93-2440 Vol. 2, Part 2 Evaluation of Potential Severe Accidents During Low Power and Shutdown Operations at Grand Gulf, Unit 1 Analysis of Core Darnage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage Internal Events Appendices A to H Manuscript Cornpleted: April 1994 Date Published: Jt.ne 1994 Prepared by J. Darby*, D. Whitchead, II. Staple, V. Dandini Sandia National Laboratories l Albuquerque, NM 87185 ! l Prepared for Division of Safety Issue Resolution ofUce of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission , Washington, DC 20555-0001 l NRC FIN L1923 ! l
- Science and Enpneering Associates. Inc. 6100 Uptown lilvd. N li Albuquerque. NM 87110 1
1
Abstract This report provides supporting documentation for various tasks associated with the performance of the probabilistic risk assessment for Plant Operational State 5 (approximately Cold Shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage at Grand Gulf, Unit I as documented in Volume 2. Part 1 of NUREG/CR-6143. The report contains the following appendices: . A - Definition and Characterization of Plant Operational States (POSs) and POS Change Initiators B - Summary of the Detailed Review of Selected Grand Gulf Procedures C - Overview of Grand Gulf Power Plant D -Initiating Event Analysis from Screening Report E - Updated Success Criteria F - Supporting Calculations G - Calculation of the Frequency and Recovery of LOSP Plus Recovery of LOSP/DG Failures H - Event Trees i l I I i l l Vol. 2 Part 2 iii NUREG/CR-6143 '
i l Contents Acronyms . . . . . . . . . . . . . . . . . . . . . . . ......... . .......... xv Forewo rd . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... xvii Acknowledgements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . xix Appendix A. Definition and Characterization of Plant Operational States (POSs) and POS Change Initiators . . A-1 A.1 Introd uction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . A-1 A.2 Definition and Characterization of POSs . . . . . . . . . . . . . . . . . . . . . . . . . A1 A.3 Definition and Characterization of POS Change Initiators . . . . . . . . . . . . . . . . . . A-9 References for Appendix A . . . . . . . . . . . . . . . . . . . . . . .... ...... . A-13 Appendix B Summary of the Detailed Review of Selected Grand Gulf Procedures .. ........... B-1 B.1 Power Operations - #03-1-01-2 ................ .. ........ B-1 B.I.1 Low Power to Full Power Increase . ................. .... B-1 B.I.2 Full Power to Low Power Decrease ... ................... B-1 B.I.3 Rapid Power Reduction .... ....................... B-2 B.2 Plant Shutdown - #03-1-01 3 . . . . . . . . . . ................... B-2 , B.2.1 Cooldown with the MSIVs Open .. ....... ........... B-2 B.2.2 Cooldown with the MSIVs Closed . . . . . . . . . . . . . . . . . . . . . . . . B-2 B.3 Refueling - #03-1-01-5 . . . . . . . . . . . . . . . .............,.. B-2 B.3.1 Plant Cooldown and Entry into OC 5. . . . . .. ......... ... B-3 B.3.2 Reactor Pressure Vessel Reassembly and Entry into OC 4 ..... ....... B-3 B.4 Cold Shutdown to Generator Carrying Minimum Load - #03-1-01-1. . . . . . . . . . . . B-3 B.4.1 Reactor Startup . . . . . . . . .. ...... ... ........ B-3 B.4.2 Unit H er tup . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... B-4 B.4.3 Turbine Startup And Generator Synchronization ............. .... B-4 B.5 Inadequate Decay Heat Removal - #05-1-02.Ill-1 ..................... B-5 B.5.1 Fuel in the Vessel and the Unit in OC 4 ..................... B-5 B.5.2 Fuel in the Vessel and the RPV Head is Off . . . . . . . . . . . . . . . . . . . . B-5 Appendix C. Overview of Grand Gulf Power Plant . . . . . . . . . . . . . . . . . . . . . . . . . . C-1 References for Appendix C . . . . . . . . . . . . . . . ......... ........... C-6 Appendix D. Initiating Event Analysis from Screening Report ......... ...... . .. D-1 D.1 Approach and Summary . . . . . . . . . . ..... ... .. . .... D-1 D.2 Transient Initiating Events . . . ..... ... .... . . ........ D-1 D.2.1 Background . . . . ............................ D-1 i' D.2.2 Introduction . . . . . . .......................... D-1 D.3 LOCA Initiating Events . . . . .......................... D-6 D.3.1 Background . . . . .......................... D-6 D.3.2 Introd uction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D-6 i D.3.3 LOCA Events from NUREG 4550 . . . . . . . . . . . . . . . . . . . . . . . . D-6 D.3.3.1 LOCA Categories . . . . . . . . . ................ D-12 l D.3.3.2 Interfacing System LOCA . . . ........ .. ...... D-12 D.3.3.3 Vessel Rupture . . . . . . . . . ............ . .. D 12 D.3.4 LOCA Events Unique to Low Power / Shutdown Operations ............ D-12 l D.3.4.1 Recoverable Diversion of Vessel Inventory (H) . . . . . . . . . . . . . . D-12 D.3.4.1.1 Residual Heat Removal System ............... D-13 D.3.4.1.2 Reactor Water Cleanup System . . . . . . . . . . . . . . . . D-13 D.3.4.1.3 Reactor Core Isolation Cooling (RCIC) .... ....... D-13 D.3.4.1.4 High Pressure Core Spray (HPCS) . . . . ......... D-13 D.3.4.1.5 Low Pressure Core Spray (LPCS) .............. D-13 D.3.4.2 LOCA in Operating Connected System ........... ..... D-13 D.3.4.3 Maintenance / Test Induced LOCAs ......... ........ D-14 Vol. 2, Part 2 v NUREG/CR-6143
Contents (Continued) I D.4 Decay Heat Rernoval Challenge Initiators ......... ......... D-14 ' D.4.1 Introduction ............................ D-14 D.4.2 Identification and Estimatien. . . . . . . . ............ D-14 D.5 Special Events . . . . . . . . . . . . . . . . . . . . . . . ....... D-14 ' D.5.1 Introduction ... ................. . .... D-14 D.5.2 Criticality Events . .. . . .......... .... D-18 D.5.3 Support System Events . . .... ... ....... ... D-18 D.5.4 Other Events .. .. .. ... ............. D-23 References for Appendix D . . . . . . . . . . . ... .. ................ D-24 Appendix E. Updated Success Criteria ... .. ...... ................. E-1 E.1 Summary Description of the Success Criteria for the Systems vs POSs: L Low Pressure Conditions . ................... ........ E-1 E.2 Pressuritation Concerns and Success Criteria at Rated Pressure . . .......... E-7 E.3 Success Criteria . . . . . . . . .. ..... . .... ... .... E-8 References for Apper. dix E , . . . . . . . . . .. ... . ... . ........ E-27 i Appendix F. Supporting Calculations . ..... . .... .. . F-1 F.1 Calculation Files . .. . . . .. . . . .. .. . F-1 ; F.2 Scoping Calculations . . . . .... .. .. .. . ....... F-1 , F.2.1 Calculation #2 .... .. . . . . ..... F-1 F.2.2 Calculation #3 . . . . . . . . . . . .. . . .. . F-1 F.2.3 Calculation #7 . . . ... . .. . .. .. ...... F-5 F.2.4 Calculation #8 . . . .. . ... .... ... ... F-5 F.2.5 Calculation #9 . . .... ........... ....... F-6 , F.2.6 Calculation # DRAFT . . . . . . ... ... .... . . . F-6 F.2.7 Calculation #22. . . . . . . ..... .... ....... . .. F-6 F.3 Calculations for Multiple Initiators . .... . ..... .... ..... F-6 F.4 Detailed Calculations . . . . .. ... .... . . ..... F 21 ; F.4.1 Calculation #11. . . . . . . ... .. .. ..... ..... F-21 ; F.4.2 Calculation #4.1 . ...... ... . . .. ...... F-27 F.4.3 Calculation #6 . . . . ... .. .... ................ F-27 F.4.4 Calculation #17. ..... . ... . .. . . . . F-37
- F.4.5 Calcu. tion #5 . ..... ....... ....... .. .. F-37 ;
F.4.6 Calculation #10. . . . . ......... . .. . .. ..... F-38 F.4.7 Calculation #13. ..................... ...... .. F-38 I F.5 Operator Actions . . . . . . . .... .................. ... F-38 References for Appendix F . . . . . . . . . ..... ... .... . ......... . F-42 Appendix G. Calculation of the Frequency and Recovery of LOSP Plus Recovery of LOSP/DG Failures . . G-1 G.1 Calculation of the Frequency of LOSP . . . ... .... ... .. G-1
.. .. l G. I .1 Process . ........... .... .......... .. .. G-1 !
G.I.l.1 Overview .. .. ......... . . . ..... G-1 i G. I . I .2 Procedure , . . . . . .. . .... ......... G-1 G. I . l .2.1 Phase 1 . . . . . ... ... . . . . . G-1 , G.I.l.2.2 Phase 2 . .. . . ... .... .. . .... G-3 i G. I .2 Results ... . .... .. .... .............. G-4 t G.2 Determination of the Mean Probability of Recovery from LOSP at Different Times . .... G-17 G.2.1 Process . ..... . ..... . .... .. . ..... G-17 - G.2.1.1 Overview . .. . ........ ..... ....... G-17 G.2.1.2 Procedure . . . ......... . ...... ...... G-17 G.2.2 Results .... ... ...... .. ....... . . . G-18 NUREG/CR-6143 vi Vol. 2, Part 2
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Contents (Continued) G.3 Determination of Recovery Values for LOSP/DG-Failure Restorations: DG Fails to Start . . . . G-23 l G.3.1 Process . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-23 G.3.1.1 Overview ..... ...... ................ G-23 O.3.1.2 Procedure ............................. G-23 G.3.2 R esul ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-23 I G.4 Determination of Recovery Values for LOSP/DG-Failure Restorations: DG Fails To Run ... G-26 G.4.1 Process . . . . . . . . . ..................... . G-26 G.4.1.1 Overview .... ..,,......... .......... G-26 ! G.4.1.2 Procedure .............. .............. G-26 0.4.2 Results . . . ,. . . ..................... .... G-26 G.5 Determination of Recovery Value= for LOSP/DG Failure Restoration (LOSP Not an IE) : DG Fails to Run . . . . . . . .......................... G-29 G.5.1 Overview . . . . . ........................... G-29 G.5.2 Proced ure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-29 G.5.3 Results . . . ... .......................... G-29 G.6 Determination of Recovery Values for LOSP/DG Failure Restoration (LOSP not an IE): , DG Fails to Start . . . . . . . . . . . . . . . . . .. . .. ...... G-32 , G.7 Recovery / Correction Factors for Uncertainty Analysis ..... . . . ...... G-32 , G.7.1 LOSP as initiating Event (CF ) ... . .... . ......... G-32 ! G.7.2 LOSP as initiating Event: DU Fails to Run . . . . . . . . ... ..... G-32 G.7.3 LOSP as Initiating Event: DG Fails to Start . . . .. ......... .. G-34 G.7,4 LOSP as initiating Event: DG Fails to Start. Common Mode ... . .. . G-34 G.8 IRRAS Histogram Development .. . . .. . .. ..... G-36 References for Appendix G . . . . . ..... . . . . . . .. ... G-38 Attachments for Appendix G Attachment G-1 IE.BCK . ... ..... .. ..... .. .. G-39 Attachment G-2 IE.BCK . . . . ....................... G-42 Attachment G-3 LOSP_lE_PCGW.DAT . . . . . .. . .... ....... G-45 7 Attachment G-4 LOSP_lE_IV.DAT. . . .. .. ... .... ... G-48 Attachment G-5 IE.DAT . ... . .. ........... ... G-51 Attachment G-6 LOSP IE_PCGW.INP . . . . . . . .. .. .... ... G-57 i Attachment G-7 IEBAT.COM . . . . . . . .... ..... .. .. G-59 l Attachment G-7a IE. BAT.COM (SLOW B ATCil MODE) . . . . . . . . . . . . . . . . G-61 ; Attachment G-7b IEBAT.COM LOG FILE .. . . . . . . . . . . .......... G-63 i Attachment G-8 IE_PCGW.DAT (BEFORE UPDATE) ...... .. ... G-65 Attachment G-9 IE,,PCGW.DAT (AFTER UPDATE) . . .... ......... G-67 i Attachment G-10 IE.DAT ........... .. ............ G-69 Attachment G-il IEBAT.COM FOR CATEGORY IV ... ............ G-73 ) Attachment G-12 LOSP_lE_IV.lNP . . . . . . . . ................ G-75 Attachment G-13 IE IV.DAT. . . .... ........ ... ...... G-77 Attachment G-14 IE[lV.DAT. , ....... ................. G-79 : Attachment G-15 IEB AT. LOG FOR CATEGORY IV . . . . . . . . . . . . . . . . . . G-81 ' Attachment G-16 I E_IV . D AT . . . . . . . . . . . . . ............. G-83 , G-85 j Attachment G-17 I E_IV. D AT. . . . . . . . . . . . . . . . . . . ........ Attachment G-18 LilS.COM ,.. . ....... ........ G-87 i Attachment G-19 LHS.INP........... .. ...... ...... G-89 Attachment G-20 USRDST.FOR (Subroutine) . . . ... .. ....... G-91 Attachment G-21 LHS.OUT . ... . . . .. ......... G-94 Attachment G-22 LH S . D AT . . . . . . . . . . . . ... .. ...... G.99 Attachment G-23 REMOVECOL2.FOR .......... ..,... . ... G-110 Attachment G-24 LIISLOSP.INP .... .. . .. ...... G 112 Attachment G-25 LHSADDITION.FOR . . . . . ..... .. . ..... G-120 Vol. 2, Part 2 vii NUREG/CR-6143
Contents (Continued) Attachment G-26 LHSLOS P. D ATC . . .' . . . . . . . . . . . . . . . . . . . . . . G-122 Attachment G-27 REM OVECOL.FOR . . . . . . . . . . . . . . . . . . . . . . . G-127 Attachment G-28 PCGWLOSP. D AT . . . . . . . . . . . . . . . . . . . . . . . . . G-129 Attachment G-29 STAT S A S . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-134 Attachment G-30 STAT. LI S . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-136 Attachment G-31 GGG RI D. D AT . . . . . . . . . . . . . . . . . . . . . . . . . . G-139 Attachment G 32 GGWEAT.D AT . . . . . . . . . . . ....... ...... G-141 Attachment G-33 GG PC I . DAT . . . . . . . . . . . . . . . . . . . . . . . . . . . G 143 Attachment G-34 GGPC2.DAT . . . . ......... .......... G-145 Attachment G-35 GGPC3.DAT . . . . . . .... .. . .......... G-147 Attachment G-36 GG PC4.D AT . . . . . . . . . . . . . . . . . . ........ G-149 , Attachment G-37 MODEL.FOR. . . . . .... .............. . G-151 Attachment G-38 G AMM A.FOR , . . . . . . . . . ............... G-163 > Attachment G-39 MLE.OUT . . . . ................... ... G-165 Attachment G-40 AMOSLIB.FOR . . . . . ................. .. G-167 Attachment G-41 GG.D AT . . . . . . . .......... ......... G-188 Attachment G-42 COM M EAN. FOR . . . . . . . . . . . . . . . . . . . . . .. G-194 Attachment G-43 LOGNORM AL.D AT . . . . . . . . . . . . . . . . . . . . . . . . G-196 Attachment G-44 LHS Input File: LOSP.EKI . . . . . . . . . . . . . ....... G-198 Attachment G-45 FORTRAN Program: RLOSP . .................. G-200 Attachment G-46 IRRAS Histogram Development Spread Sheet Input ...... ... G-207 Attachment G-47 1RRAS llistogram Development Spread Sheet ............. G-223 Appendix H. Event Trees . . . . . . . . . . . . . . . . .......... ......... H1 NUREG/CR-6143 viii Vol. 2, Part 2 i
1 l List of FigurcS E.1-1 Functional Event Tree for Plant Operational States 4,5,6 and 7 . . . . . . . . . . . . . . . . . . . E-2 F.4 1 1 SRV, Water ...................... . ... .......... F-28 P.4-2 1 SRV, Steam .............. ........................ F-29 F.4 3 Vent Line, Water . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F-30 F.4-4 Vent Line, Steam . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F 31 F.4-5 Steaming with Makeup . . . . . . . . . . . . . . . . . . .' . . . . . . . . . . . . . . . . . F 32 P.4-6 Steammg with No Makeup . . . . . ............................ F-33 F.4-7 Decay H eat . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F-34 F.4-8 Pressure: Water Solid With 1 ECCS Pump ........................... F-35 F.4-9 Pressure: Water Solid With 2 ECCS Pump ......... ................. F-36 0.2-1 Probability of Recovery from LOSP vs. Time for the 5th,50th, and 95th Percentiles ......... G-20 0.2-2 Mean Probability of Recovery from LOSP vs. Time at Grand Gulf . . . . . . . . . . . .... G-22 0.7-1 CF Distribution Calculation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . G-33 l Attachment G-47-1 Example Plot of Cummutative Distribution Function . . . . . . . . ..... G-239 l Attachment G-47-2 Example ' Start Step" Plot of Cummulative Distribution Function . . . . . . . . . . . . G-240 H.1-1 A51SO Tree . . . . . . . .............. ................. H-2 l H.1-2 ADEP Tree ................ ........... . .. .... . H-3 l H.1-3 ADEPP Tree . . . . . . . . . . . . . . . . . . ..................... H-4 H.1-4 AD EPX Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-5 H.1-5 ADH Tree . . . . . . . . . ................... ..... ..... H-6 H.1-6 AIAD Tree . . . . . . . . . . . . . ....... ...... .. ......... H-7 H.1-7 AIADP Tree . . . . ........ ................... ... . H-8 j H.1-8 AIADX Tree . ............ ..... . . ............. H-9 H.1-9 AISD Tree . . . . . . . . . .. .... . ... .. ...... ... H-10 H.1-10 AISDP Tree .......... .. .. .............. ..... H-Il H.1-11 AISDX Tree . . . . . . . . . ..................... .. .... H-12 L -12 CAUX Tree ... ................... ...... .. ... H-13 H.1 - 13 CAUXN Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... H-14 H.1-14 CAUXP Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-15 H.1-15 CAUXX Tree . . . . . . . . . . . . . . . . . . . .......... ........ H 16 H.1-16 CB Tree . . . . . . . . . . . . . . . . .................. ..... H-17 H.1-17 CBI Trec ........................................ H-18 H.1 -18 CB I P Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........ H-19 H.1 - 19 CB l X Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-20 H.1-20 C32 Tree ........................................ H-21 H.1-21 CB2P Tree . . . . . . ............... ................. H-22 H.1 -22 CB 2X Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-23 H .1 -23 CB N Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... H-24 H.1-24 CBP Tree ........... ................ .. . ...... H-25 H.1 -25 CC Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..... H-26 H.1-26 CCI Tree .............................. ......... H-27 H.1 -27 CC I P Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-28 H.1-28 CCI X Tree . . . . . . . . . . . . . . .... . .................. H-29 H.1-29 CBX Tree . . . . . . . . . . .. .......................... H.30 H.1-30 CSTMN Tree . . . . . . . . . . . . . . . ....................... H-31 H.1-31 CSTM P Tree . . . . . . . . . . . . . . . . . . . . ... ..... ........ H-32 H.1 -3 2 CSTM X Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-33 H.1-33 CC2 Tree ................ .... .......... . ... H-34 H .1 -3 4 CC2 P Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... . H-35 H.1-35 CC2X Tree . . . . . . . . . . . . . . . ... ................. H-36 H.1-36 CCP Tree . . . . ...................... ... ... .... H-37 H.1-37 CCX Tree . . . . . . . . . . . . . . . . . .... . ..... .. ..... H-38 Vol. 2, Part 2 ix NUREG/CR-6143
,v
1 4 List of Figures (Continued) H .1 -3 8 CCN Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... .... H-39 H.1-39 CSTM Tree ......................... . ........... !!-40 H.1-40 DEP Tree ...................... . ...... ........ H-41 H.1 -41 E Tree . . . . . . . . . . . . . . . . . .............. ..... .. H-42 H.1-42 EA Tree . . . . . . ..... . ....... ...... . ....... H-43 H.1-43 EAP Tree ...... ....... ... ,... . .. .. ..... H-44 [ H .1 -44 EAX Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . ..... H-45 H.1-45 EC Tree . . . . . . . . . . . . . . . . . . . . ............. .... H-46 H.1-46 ECNP Tree . . . . . . . . .......... .. ........ ... ... H-47 H.1-47 ECP Tree ..... ..... . .... ........ .. .. .. H-48 ' H.1-48 ECX Tree . . . . . . . ............. ......... ... .. H-49 H.1-49 EP Tme . . . . . . . . . . . .... ..................... H-50 H.1-50 EX Tree . . . . . . . . . . . . . . , . . . . . . .... ............. H-51 H. I.51 F Tree . . . . . . . .. . ............ ............ ... H-52 H.1-52 FC Tree . . . . . . . ... ............. ... ....... H-53 H.1-53 FCP Tree ............. ............... ....... H-54 H.1-54 FCX Tree ........ ........... . .. . .... ... H-55 H.1-55 FNP Tree .. .. .... .... .......... .. , ,.. .. H-56 - H.1-56 FP Tree . . . . . . . . .. .. ....... .... . . . H-57 H.1-57 FX Tree . . . . . ......... . ....... ...... ... . H-53 H.1-58 HPSWA Tree. .... .. .. .. .. ... ... . . .. 11-5 9 H.1-59 HI SWR Tree . . . . ..... .... .. ..... ... ... H-60 H.1-60 HYDRO Tree. . , . . . .. . .. . . . . 11-6 1 H.1-61 HPHA Tree ... . .... .. .. . . .. H-62 H.I.62 IL Tree .. . ... .. . .. ... .. .. H-63 II.1-63 ILP Tree . . . . . . . . .. .. .... . ..... . . .. H-64 H.1-64 ILX Tree .......... .. ... ..... . H-65 H.1-65 L Tree. . . . . . .. .. .. .... . ... .... H-66 H.1-66 LA Tree . . . . ... . .. .. ... ......... .... H-67 11.1-67 LAP Tree . . .. .. ....... .. ... .... . .. H-68 H.1-68 LAX Tree . . . . . . . .. ... .. . ... ... H-69 H.1-69 LP Tree . . .. . . .. ...... ..... ....... ... H-70 H.1-70 LX Tree . . . . .. ......... ................ .... H-71 H.1-71 OF Tree . . . . . . . . . . . . . ............... . . .... . H-72 H.1-72 OFP Tree ..... .. . . . ..... . .. . ... . H-73 11.1-73 OFX Tree . . . . . . . . . . ........ ........ ....... .. H-74 < H.1-74 OVPR Tree ........ ... ......... ..... . ..... . H-75 H.1-75 OVPRP Tree . . . .. ..... . .. . . . ........... H-76 H.1-76 OVPRX Tree . . . . . . . . . . ...... ........ ... . .... H-77 H.1 77 P Tree . . . . . . .......................... ........ H-78 ! 11.1-78 PISLP Tree. . . . . . . . . . ...... ............ . ..... H-79 H.1-79 PISLX Tree .... . ........... ........... ... ... H-80 H.1-80 PISOL Tree .............................. ........ H-81 H.1-81 PP Tree . . . . . . . . . . . . . . . . . ......... ... .... . . H-82 ; H.1-82 PX Tree . . . . . . . . . . . . . . ......... ......... .. .. H-83 H.1-83 R Tree. . . . . . . .. . ........ ........... .... .. H.84 1 H.1-84 RA Tree . . . . . . .. .... .. ........ . ... H-85 ! H.1-85 RAP Tree ......... .... .. . . . ... . H-86 H.1-86 RAX Tree . . .... .... .... ..... ...... . .. H-87 18 1-87 RP Tree . . . . . .. . . . . ... . . ... . 11-8 8 H . .-8 8 RX Tree . . . . . . . . . . . . ... .. . .... ........ H-89 H.1-8 9 S Tree . . . . . . . . . . . . . . ......... .... .......... H-90 NUREG/CR-6143 x Vol. 2, Part 2
LIST of Figures (Continued) H.1-90 SDC Tree ................................... .... H-91 H.1-91 SNP Tree ........................................ H-92 H.1 -92 SP Tree . . . . . . . . . . . . . . . . . . . . .................... H-93 H.1-93 SX Tree . . . . . . . . . . . ..... . .. . . . .. .... H-94 H.2-1 ASIN Tree . . . . . . . . . . . . . . ..... ... .. .. ........ H-95 H.2-2 ASINH Tree . . . . . . ......... ......... .......... H-96 H.2-3 ASINM Tree . . . . . . . ........ .. .... ............. H-97 H.2-4 ASISH Tree ....... ..... . .... .. . ........ H-98 H.2-5 A51SJ Tree . . . . . , .. .. . . ... . ... ..... ..... H-99 H.2 6 A50UH Tree . . . . . . . . . . . . ..... .. .. ......... .. 11-100 H.2-7 A500T Tree . . . . . . . . . ............... ...... ..... H-101 H.2-8 ADEPS Tree . . . . . . . .... . .. .. .. . ..... . ..... H-102 H.2-9 ADESP Tree . . . . . . . .. ....... .. . ... . H-103 H.2-10 ADESX Tree . . . . .. . ... .. . . . H-104 H.2-11 ADRif Tree .. ..... . .. . . . ... H-105 H.2-12 ADRHP Tree . . . . .. . . .. . H-106 H.2-13 ADRHX Tree. .. .. ... .... .... ... .. ..... H-107 H.2-14 AINMN Tree . . . ...... . . .. . . .. . . H-108 H.2-15 DEPS Tree . . . .. ... .... ...... . . . . . H-109 H.2-16 EAM Tree . . . . . . . . . . .. .. .. . . .. ... H-1 t o H.2-17 EAMH Tree . ... .. .... ....... .. . .. .. . H-Ill H.2-18 EAMHP Tree. . . . . . . . . .. .. .. . .. . . H-112 H.2-19 EAMHX Tree .......... . .... .. ..... . ...... H-113 H.2-20 EAMN Tree . ...... ..... . . .. .. ... . H-114 H.2-21 EAMP Tree . ...... ... . .. .. ... .. . H-115 H.2-22 EAMX Tree .. ... . . . . . H-116 11.2-23 ECAC Tree ...... . .. . .. .. .. . .. .. . H-117 H.2 24 ECACH Tree . ........ ........ . ... . . . . H-118 H.2-25 ECACN Tree . . . . . . . . ... .. .. .... . . . H-il9 l H-120 H.2-26 ECACP Tree . . .. ... . ... .. . . ... ... H.2-27 ECACX Tree . . . . . ... .. . . .. . .. .. H-121 H.2-28 ECAO Tree ... .... ..... ... .. . .. .... .... H-122 11.2-29 ECAOH Tree. ......... ...... ........ . ......... H-123 H.2-30 ECAON Tree . . . . . . ...... ...... .. .... .... H-124 H.2-31 ECAOP Tree . . . . ..... .. . .. . ... . . .. .... H-125 H.2-32 ECAOX Tree . . . .. . . .. . ..... .... ...... H-126 H.2-33 ECCHP Tree . . . . . . ... ... . .. .. . ... H-127 H.2-34 ECCIIX Tree . . . . . . . ... .... . ... ... . .. . .. H-128 H.2-35 ECNPL Tree . .. .. ......... .. ...... ..... . ... H-129 H.2-36 ECOHP Tree . . . . . . . . . . . . . ... . ... ... . H-130 H.2-37 ECOHX Tree . . . . . ... . . .. .. . ..... H-131 H.2-38 ES Tree . . . .. ...... .................. .... H-132 H.2-39 ESP Tree ........ ..... ..... ........ .......... H-133 H.2-40 ESX Tree ........ . . .... ...... .. . .. .... . H-134 H.2-41 FAM Tree . . . . . . . . ..... . . . .... .... . .. .. H-135 H.2-42 FAMN Tree . . . . ...... .. .. .. ... ....... .. H-136 9.2-43 FAMP Trec . .............. ......... ....... . H-137 h.2-44 FAMX Tree .. ..... ........ .... . ...... .... H-138 H.2-45 FCAC Tree ....... . .... .. . .. . . . . . .. ... H-139 H.2-46 FCACN Tree . . . . . . . . . . . . ..... .... . . . .... H-140 H.2-47 FCACP Tree . . . . ... ...... . . ..... . .. ... . H-141 H.2-48 FCACX Tree . . . . . . ... . . .... .. H-142 Vol. 2, Part 2 xi NUREG/CR-6143
List of Figures (Continued) H.2-49 FCAO Tree ....................................... H-143 H.2-50 FCAON Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H 144 H.2-51 FCAOP Tree . . . . . . . . . . . . . . . . . . . . .................. H-145 H.2-52 FCAOX Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-146 H.2-5 3 FCN Tree . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . .. ...... H-147 H.2-54 FS Tree . . ...... ............................... H-148 H.2-55 FSP Tree ........................................ H-149 H.2-56 FSX Tree ............................. .......... H 150 H .2-57 H PCSW Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-151 H.2-58 LH Tree . . . . . . . . . . . . . . . . . . . . .................... H-152 H.2-5 9 LH A Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-153 H.240 LHAP Tree ....................................... H-154 H.241 LHAX Tree ............................. ......... H-155 H.242 LHP Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-156 H.243 LHX Tree, . . . . . . . . . . . . . . . . . ..... ................ H 157 H.244 OFS Tree ................ . . ... . . ....... H-158 H.2-65 OFSP Tree . . . . . . . . . .... ................ ....... H-159 H.246 OFSX Tree . . . . . . . . . . . . . ......... ................ H 160 H.247 OVPRS Tree . . . . . . . . .......i. .. ................. H-161 H .2-6 8 OVPS P Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-162 H.249 OVPSX Tree . . . . . . . . . . . . . . . . ... ....... ......... H-163 H.2-70 RAH 1 Tree. . . . . . . . . . ................... ......... H.164 i H.2-71 RAH 2 Tree . . . . . . . . . . . . . . . . . . . . ................. H-165 H.2-72 RH1 Tree ............. .......................... H-166 l H.2-73 RH2 Tree ................ ...................... H-167 H.2-74 S151N Tree ............ ..... ... ...... ........ H-168 H.2-75 S15NF Tree ....................................... H-169 H.2-76 S 15 00 Tree . . . . . . . . . . . . . . . . . . . . .......... ....... H-170 H.2-77 S1HIN Tree .............. ....... . ............. H-171 H.2-78 SlHNF Tree . . . . . . . . .............................. H-172 H.2-79 S l HOU Tree . . . . . . . . . . . . . . . . . . . . . . . . . . ............ H 173 H.2-80 S IXFH Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . ........... H-174 H.2-81 S I X FR Tree . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H-175 H.2-82 SDCH Tree ....................................... H-176 H.2-83 SDCHP Tree . . . . . . . . ......................... .. . H-177 H.2-84 SDCHX Tree . . .......... ............ .... ....... H-178 i l i 1 1 NUREG/CR-6143 xii Vol. 2, Part 2 l
List of Tables A.2-1 Plant Configuration in Various OC's Based on Procedures . . . . . . . . . . . . , ....... A-2 A.2-2 System Limitations . . . . . . . . . . . . . . . . ....... ........ .. A-5 A.2.3 Summary of Major Systems Available for Each OC ................... .... A-6 B.I.1 Precautions, Limitations, and Actions Associated with Procedure 03-1-01-2. . . . . . . . . . ... B-6 B.I.2 Summariation of Procedure Steps Necessary for Low Power to Full Power increase . . . . . .... B-7 2 B.I.3 Summarization of Procedure Steps Necessary for Full Power to lew Power Decrease ... . . . . B-10 B.I.4 Summariation of Procedure Steps Necessary for Rapid Power Reduction ........... .. B-12 B.2.1 Precautions, Limitations, and Actions Associated with Procedure 03 01 -3 . , . . . . . . . . . . . . B-13 B.2.2 Summarization of Procedure Steps Necessary for Cool down with the MSIVs Open .......... B-14 B.2.3 Sammarization of Procedure Steps Necessary for Cool down with the MSIVs Closed . . . . . . . . . B-18 B.3.1 P<ecautions and Limitations Associated with Procedure 03-1-01-5 . . . ............. B-21 B.3.2 4ummarization of Procedure Steps Necessary for Plant Cool down and Entry into OC 5 . . . . . . . B-22 B.3.3 Summarization of Procedure Steps Necessary for Reactor Pressure Vessel Reassembly and Entry into OC 4 B-25 B.4 1 Precautions, Limitations, and Actions Associated with Procedure 03-1-01-1. . . . . . . . . . . . . B-26 i B.4.2 Summarization of the Procedure Steps Necessary for Reactor Startup ............ B-27 B.4.3 Summarization of the Procedure Steps Necessary for Unit Heatup . . ........ . .... B-29 B.4.4 Summarization of the Procedure Steps Necessary for Turbine Startup and Generator Synchronization . . . B-32 B.5.1 Symptoms Which Require Use of Procedure 05-1-02-111-1 ........... ........ B-34 , B.S.2 Immediate Operator Actions .......... ....... ... ........ B-34 ! B.5.3 Summarization of Steps Necessary to Restore Decay Heat Removal When Fuel is in the Vessel and the Unit is in OC 4 . . . . . . . . . . . . . . .... ... ...... .... B-35 B.5.4 Summarization of Steps Necessary to Restore Decay Heat Removal When Fuel is in the Vessel and the RPV Head is Off ............... ....... ......... B-37 B.S.5 Summarization of Steps Necessary to Restore Decay Heat Removal When Fuel is in the Containment or Spent Fuel Pools . . . ............. .... ...... B-38 D.I.1 Grand Gulf lew Power and Shutdown Initiating Events and Frequencies .. .. .. . D-2 D.2.1 Transients . . . ...................... . . . ..... D-4 D.2.1 Comments. . . . . . .... . . . . . .. . ..... D-5 D.3.1 less of Coolant Accidents . . . . . . . ... . ............. D-7 D.3.1 Comments. . . . ...... ....... ........ ....... ... D9 D.4.1 Decay Heat Removal (DHR) Challenge Initiators . . . . . . . . . . . . . . . . ... ... D-15 ; D.4.1 Comments . . . . . . . . . . . . . . . . . . . . . . . . . . ...... ... . D-17 D.5.1 Special Initiating Events . . . . . . . . . . . . . . . . . . . . . ...... ..... D-19 D.5.1 Comments . . . . . . . . . . . . . ............. ........... D-22 E.1.1 Success Criteria for Plant Operational State (POS ) 4 . . . . ... ...... ..... E-9 E.1.1 Notes. . . . . . . . . . . ........... ....... . ... . E-11 E.1.2 Success Criteria for Plant Operational State (POS) 5 . ....... . . .. ..... E-12 E.1.2 Notes . . . . . . . . . . . . . . . . . . ........ ....... ... .. E-16 E.1.3 Success Criteria for Plant Operational State (POS) 6 .. . .. .. . .. . E-17 E.1.3 Notes . . . . . . . . . . . .......... .. .... .. ........ E-21 E.1.4 Success Criteria for Plant Operational State (POS) 7 .............. . ..... E-22 E.1.4 Notes . . . . . . . . . . . . . . . . . . . . .. .. ...... . E 26 i F.1.1 Calculations Performed . . . . . . . . . . . ... ................... F-2 . F.2.1 Results ofInitial Thermal Hydraulic Calculations for Screening Study ....... ...... F-4 F.3.1 MULINIT. PAS Source Code . . . . . . . . .. . . . ... .. .. F-8 F.3.2 Multiple Initiating Events for POS 5 . . . . .. ........ ........ .... F-12 F.4.1 GGENER. PAS Source Code . . . . . . . . .... . .. . ..... . F-22 F.5.1 Times Available for Operator Actions: POS 5 .. . .. . . . F-39 Vol. 2, Part 2 xiii NUREG/CR-6143
List of Tables (Continued) 0.1.1 less of Offsite Power Events Used to Estimate Frequency During POS I .............. G-5 G.I.2 Additional Loss of Off-Site Power Events Used to Estimate Frequency During FOS 2-7 ........ G-8 G.1.3 Informational Worksheet for LOSP Calculation ...... ... ..... ........ G-9 G. I .4 Non-category IV Event Data . . . . . . . . . . . . . . . . .. . . . . . . . ....... G-15 G. I.5 Category IV Event Data . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... G-16 G.2.1 Time to Recover from LOSP Through 1988 . . . . . . . . . . . . . ... . ... G-19 G.2.2 Mean Probability of Recovery from LOSP at Different Times ... . . .. . .. G-21 G.3.1 Correction / Recovery Factors for DG Fails to Start (LOSP as Initiating Event) . ........ . G-24 G.4.1 Correction / Recovery Factors for DG Fails to Run (LOSP as Initiating Event) . . . . . .. G-27 l G.5.1 Correction / Recovery Factors for LOSP (not an IE) with DG Fails to Run ..... ...... G-30 l G.7.1 DG Fail to Start Non Recovery Distributions . ........... ..... .... G-35 i G.7.2 DG Fail to Start Common Mode Non Recovery Distributions . ...... .... .... G-35 l l l l l i f r I i i r NUREG/CR-6143 xiv Vol. 2, Part 2
Acronyms ADHR Auxiliary Decay Heat Removal ADS Automatic Depressurization System ATWS Anticipated Transient Without Scram BNL Brookhaven National 1.aboratory BWR Boiling Water Reactor CCW Component Cooling Water CDS Condensate CI Containment Isolation CRD Control Rod Drive CRWST Condensate and Refueling Water Storage Transfer System CS Containment Spray CST Condensate Storage Tank CV Check Valves CVS Containment Venting System DBA Design Basis Accident DG Diesel Generator ECCS Emergency Core Cooling Systems EHC Electro-Hydraulic Controller EHV Emergency Ventilation System ENSDC Enhanced Shutdown Cooling EPS Emergency Power System FCV Flow Control Valve FDW Feed Water System FW Fire Water HCU liydraulic Control Unit , HPCS High Pressure Core Spray IAS Instrument Air System IRRAS Integrated Reliability and Risk Analysis System ; LCO Limiting Condition of Operation LOCA loss of Coolant Accident LPCI law Pressure Coolant Injection I LPCS Low Pressure Core Spray i MSIV Main Steam Isolation Valve l MSL Mean Sea Level MSR Moisture Separator Reheater NPSHA Net Positive Suction Head Available NPSHR Net Positive Suction Head Required NRC Nuclear Regulatory Commission OC Operating Condition POS Plant Operating State PRA Probabilistic Risk Assessment PSW Plant Service Water PWR Pressurized Water Reactor RCIC Reactor Core Isolation Cooling RES Research (Office of NRC) RFPT Reactor Feedwater Pump Turbine RHR Residual Heat removal RPV Reactor Pressure Vessel RRS Reactor Recirculation System RWCU Reactor Water Cleanup System SDC Shutdown Cooling System (s) SGTS Standby Gas Treatment System Vol. 2, Part 2 xv N U REGICR-6143
Acronyms (Continued) SL Safety Limit SLC Standby Liquid Control SP Suppression Pool SPC Suppression Pool Cooling SPMU Suppression Pool Makeup SPMU Suppression Pool Makeup SR Surveillance Requirement SRV Safety Relief Valve SSWXT Standby Service Water Crosstic TBCW Turbine Building Cooling Water TBV Turbine Bypass Valve (s) UPSAR Updated Final Safety Analysis Report 5 L T i l NUREGICR-6143 xvi Vol. 2 Part 2 l \ - - - - -
Foreword (NUREG/CR-6143 and 6144) Low Power and Shutdown Probabilistic Risk Assessment Program Traditionally, probabilistic risk assessme nts (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during ;'ull power operation Some previous screening analyses that were performed for other modes of operation suggested that ilsks during those m xles were small relative to full power operation. However, more recent studies and operational experience hve implied that a.:cidents during low power arul shutdown could be significant contributors to risk. During 1989, the Nuclear Regulatoiy Com nission (NRC) ini:iated an extensive program to carefully examine the potential risks during low power and snutdown open tions. The progn m includes two parallel projects performed by Brooklaven National Laboratory (BNL) and Sandia Nati >nal Laboratories (SNL), with the seismic analysis perfonned by Future Resources Associates. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the prograrn are to assess th i risks of severe accidents due to internal events, intemal fires, internal flomis, and seismic events initiated during plant operational states other than full power operstion and to compane the estimated core damage frequencies, important accident sequen es and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. The results of the program are documented in two reports, NUREG/CR 6143 arxl 6144. The reports are organized as follows: For Grand Gulf: NUREG/CR-6143 - Evaluation of Pdential Severe Accidents During Low Power aral Shutdown Operations at Grand Gulf, Umr 1 Volume 1: Summar/ of Results Volume 2: Analysis if Core Damage Frequency from Internal Events for Plant Operational State 5 During a Refueling Outage ! l Part 1: Main Report Put l A: Sections 1 - 9 Put IB: Section 10 Part IC: Sections 11 - 14 Part 2: bremrJ Events Apperrlices A to H Part 3: Internal Events Appendices I and J Part 4: Intemal Events Appendices K to M Volume 3: Analysis of Core Damage Frequency from Intemal Fire Events for Plant , Operational State 5 During a Refueling Outage Volume 4: Analysis of Core Damage Frequency from Intemal Flomling Events for Plant Operational State 5 During a Refueling Outcge Volume 5: Analysis of Core Damage Frequency from Seismic Events for Plant Operational State 5 During a Refueling Outage Volurne 6: Evaluation of Severe Accident Risks for Plant Operational State 5 During a Refueling Outage Part 1: Main Report Part 2: Supporting MELCOR Calculations Vol. 2, Part 2 xvii NUREG/CR-6143
Foreword (Continued) For Surry: NUREG/CR-6144 - Evaluation of Potential Severe Accidents During lew Power and Shutdown Operations at Surry Unit-1 Volume 1: Summary of Results Volume 2: Analysis of Core Damage Frequency from Internal Events During Mid-loop Operations Part 1: Main Report Part IA: Chapters 1 - 6 Part IB: Chapters 7 - 12 Part 2: Internal Events Appendices A to D Part 3: Internal Events Apperxlix E Part 3A: Sections E.1 - E.8 Part 3B: Sections E.9 - E.16 Part 4: Internal Events Appendices F to 11 Part 5: Internal Events Apperrlix I Volume 3: Armlysis of Core Damage Frequency from Intemal Fires During Mid-loop Operations Part 1: Main Report Part 2: Appermlices Volume 4: Analysis of Core Damage Frequency from Internal Floods Durir.g Mid loop Operations Volume 5: Analysis of Core Damage Frequency from Seismic Events During Mid loop Operations Volume 6: Evaluation of Severe Accident Risks During Mid-loop Operations Part 1: Main Report Part 2: Apperxlices l l NUREG/CR-6143 xviii Vol. 2, Part 2
1 Acknowledgements The authors wish to acknowledge the following for their contributions to this study. The numerous individuals at the Grand Gulf site for their help in obtaining information that made this analysis possible. Richard C. Robinson, Jr. of the NRC for his support in obtaining timely support from the IRRAS computer code developers. Kenneth Russell of Idaho Nuclear Engineering Laboratory for his help in using IRRAS and for providing excellent code support durir.g the use of IRRAS. Members of the Senior Consulting Group and the BWROG PRA Review Committee for their review and suggested improvements to the project. Finally, to Ellen Walroth and Emily Preston for their secretarial support during the project. 1 1 Vol. 2 Part 2 xix NUREG/CR4143
Appendix A. Definition and Characterization of Plant Operational States (POSs) and POS Change Initiators : A.1 Introduction Conditions (OCs) as follows [USNRC 1984]: This section of the report is taken from the earlier coarse (1) OC 1, Power Operation: Mode Switch in screening study report [ Whitehead et al,1991]. It is Run, Any Temperature included in this report so that the definition of Plant Operating State (POS) is clearly explained, and so that (2) OC 2, Startup: Mode Switch in Startup/ Hot , the concept of a known, pre-existing unavailability prior Standby, Any Temperature to an accident initiating event is clearly explained. (3) OC 3, Hot Shutdown: Mode Switch in in order to analyze accidents initiated from conditions Shutdown, Temperature Greater than 200 F other than full power, a clear understanding of how the plant changes its operational status was needed. In (4) OC 4, Cold Shutdown: Mode Switch in addition, it was necessary to gain an understanding of Shutdown, Temperature 200 F or Imwer why the plant changes its mode of operation. To evaluate how the plant transitions from full power to (5) OC 5. Refueling: Fuel in Vessel with Head other conditions, a detailed review of several of the Detensioned or Removed, Mode Switch in Shutdown or Refuel, temperature 140 F or operational procedures for Grand Gulf was performed. To evaluate reasons for transitioning to conditions other IA**T - r than full power, the Technical Specifications were reviewed [USNRC,1984], the Safety Analysis Report The normal configuration of the plant in each of the five i was reviewed [SER1,1992], and discussions were held OCs is summarized in Table A.2-1
- Plant Configuration in Various OCs based on Procedures".
with Grand Gulf staff. Also, the experience of the (The entries in this table correspond to normal conditions authors of this report was brought to bear on evaluating the reasons for transitioning the plant. as the plant is cooled down from full power. The situation for startup is subsequently discussed.) This table delineates when certain systems are placed into This appendix uses information from various procedures service, removed from service, or operated in a different i at Grand Gulf. These procedures are discussed more mode as the plant transitions among OCs. (Note, this completely in Appendix B. Appendix C is a sununary table was developed in the initial screening study, and of general information about BWRs with an emphasis on does not consider the Hydro condition during cold Grand Gulf, that is pertinent to understanding plant shutdown, in the detailed analysis of POS 5, the Hydro characteristics. condition during cold shutdown was considered, as discussed in Section 3 of this report.) The systems A.2 Definition and Characterization aspects of Table A.2-1 are influenced by the design of POSS characteristics of the systems. For example, the Reactor Core Isolation Cooling (RCIC) system is auto isolated at As originally envisioned, the study would have identified 60 psig since it requires adequate steam for the turbine and quantified potential accidents for the five modes of driven pump. Also, the steam condensing mode of the operation as defined by the Technical Specifications RCIC system can only be used below 500 psig since this [USNRC 1984]. However, as the review of the plant's is th design rating of the RHR heat exchangers. (The operating characteristics progressed, it became apparent steam condensing mode of RCIC is not currently used at that another means of classifying the status of the plant Grand Gulf.) Design limitations are summarized in would be necessary. This new classification scheme Table A.2-2 ' System Limitations". To facilitate event needed to account for the various changes in system tree development and review, Table A.2-3, ' Summary , configurations, decay heat, pressure and temperature, of Major Systems Available for each OC", was prepared. I and water level that occur during transitions from power This table summarizes the availability of systems to ( operation to refueling and back to power operation, or provide the l some subset of these transitions. This need resulted in the development of Plant Operational States (POSs). , i The technical specifications define Modes or Operating Vol. 2, Part 2 A-1 NUREG/CR-6143
-e w - -e -w - -
_______e+ - -
Characterization of POS: Table A.2-1 Plant Configuration in Various OC's Based on Procedures OC P P P (psis)T *F llest Reunoval levd Control Rods Recirculation (Sat. Unless Noted) 1 100 % 100 % - 1000 psig TG FDW Ota High Speed
- 550*F FCVs open Gradually close FCVs 50 % 50 % At - 50 % Above 45%
power secure core flow, one RFPT innen rods and continue to insert to reduce power Above 30% core flow, switch to low speed, open FCVs fully 20 % 20 % - 950 psig TG, TBVs open below FDW on
- 540*F 20% at 950 psig stanup setpoint
- 12 % 150 MWe
- 12 % 0 Manually trip turbine, generator trips on reverse pow er, TBVs open
-12% 0 - 950 psig TBVs FDW Partly in, low speed,
- 540*F insert as FCVs full required to open ,
nduce power ' 2 (rnode -8% 0 TBVs close as FDW switch in presnure goes below STARTUP) 950 psig, no heat renoval - 3 (mode 0 0 Take TBVs in Manual FDW A!! Rods in switch in to continue cooldown SHUTDOWN) i
~ 500 psig Secure running i RFFT, contro! l level with condensate and booster
- 135 psig Place RHR in SDC.
TBVs still open (Manual) f f NUREG/CR-6143 A-2 Vol. 2, Part 2 1 1
l i I 1 Characterization of POSs l Table A.2-1 Plant Configuration in Various OC's Based on Procedures > i OC P P P (psis)T *F IIeat Reinoval Level Control Rods Recirculation (Sat. Unles Noted) l t
- 100 psig Shut TBVs, set pressure RWCU demand 100 poig > blowdown, reactor pressure. R}IR break on SDC condenser vacuum if desired Close MSIVs if desired to go to OC 5. Cool down to below 20&F !
with R}{R on SDC 4 (when T < 19&F, vent to Cooldown to -120 to RWCU All in b>w speed, 20&F) atmosphere 130*F and maintain with blowdown, FCVs full O psig, subcooled RHR on SDC maintain open condensate if desired to go toOC5 4 0 0 0 peig RHR on SDC Raise level
- 120*F subcooled wie.
condensate to above head I flange l l to go to refuel OC, cooldown to 80 to 100*F with RIIR on SDC
- 80*F subcooled Open fuel transfer tube closure hatch, close gate connecting upper pool and reactor cavity, drain upper Rx uvity in RWST Remove i
drywell head, lower vessel j level to I A. I or more below head flange, remove RPV i lead j ( connections j l 5 (as soon as Detension Throttle FCVs ; detension RPV head, to reduce head) remove RPV water ripple l head, remove steam dryer e l l ' 1 Vol. 2, Part 2 A-3 t' it'RF:3/CR-4 03 l l l
( l l i l i , Characterization of POSs ] Table A.21 Plant Configuration in Various OC's Based on Procedures OC P P P (psig)T *F I! eat Reinoval level Control Rods Recirculation (Sat. Unless Noted) , Drain level to l below steam lines (RWCU l blowdown). ! install steam l line plugs l RcDood upper l reactor cavity from RWST, lift steam l separator as cavity fills Open gate connecting upper pool and l reactor cavity 5 0 0 0 psig RHR on SDC RWCU
-80'F subcooled blowdown, condensate I
available as needed 5, commence i nquired in-vessel ; activities I L l i i i k 9 NUREG/CR-6143 A-4 Vol. 2, Pa t 2 . r
1 Chzrzcterization of POSs : Table A.2-2 System Limitations RHR on SDC l
- RPV pressure < 135 psig (pressure interlock FSAR 5.4.7.1.3.1) i
- Requires manual alignment I
ECIC
- HPCS can perform same function
- Auto isolates at 60 psig
- Once through mode can operate at rated pressure ,
- RHR steam condensing mode only if < 500 psig (HX pressure rating)*
- Once through mode auto initiated on Level 2, low low water level (-42") {
- Steam condensing mode requires manual actuation
- l l
11P.CE i e injects over all pressure, rated to O prig, evidentally no concern about runout (NPSH or power) ;
- Auto on at high drywell pressure (1.4 psig) glow low vessel water level (Level 2, -42")
AD.S
- 8 SRVs open auto if either: l
- Low water (level 3, + 11") a_n.ui. Low low low water (level 1, -150') a.n.id .high drywell pressure (1.4 psig) annd one low pressure pump running a.nd.105 see timer times out
- Lew water (level 3, + 11") a_nd_ Low low low water (level 1, -150") an. stone low l pressure pump running an.d 10 min. timer times out :
LPCS l
- Iew pressure permissive 500 psig and decreasing
- Given low pressure permissive, auto on if low low low level (Level 1, -150") qthigh drywell pressure (1.4 psig) l LPCI Train A RHR
- Low pressure permissive 500 psig and decreasing f l
- Given low pressure permissive, auto on if low low lov lent (Level 1 -150") qr_high drywell pressure (1.4 psig)
LPCI Train B RHR. or Train C
- low pressure permissive 500 psig and decreasing ,
- Given low pressure permissive, auto on if low low low level olhigh drywell pressure ADHRS
- Section piping rated at 80 psig
- Only allowed in operation in OC 4 or DC 5 4
*Not used at Grand Gulf Vol. 2, Part 2 A-5 NUREG/CR-6143
y Table A.2.3 Summary of Major Systems Available for Each OC x t'1 _ O i 3 I y OC W 3. W pdg level Centrol Reactivity Availability of Ilent Renneval Systeams 6 Centrol h' Injection IAdows g { 3 CRD IDWI Steam RWCU Reds SLC' Recirc TBVs SDC ADIIRS RCIC SRVs IIPCS LPCS LPCI Feel Other CDS CoeEng X'
~1000 1. 2. and 3 Y Y Y N" Y / N' N' Y Not needed Y Y Y' f N To be if reactor developed' tripped *"
~ 500 3 Y Y Y N" IN Not Y' N' N' Y Y Y Y' Y' N See above needed'"
- 100 3 Y N" N Y IN NM N" Y" N' Y Y Y Y' Y' " N See above tn
,gg
- 60 io 3 and 4 Y N" N Y IN Not N" Y" Y - OC 4 N' Y" Y Y' Y'" N See above
-0 needed*" only" I
O 5 Y Y" N Y IN Not N" Y" Y" N' N" N"" N*" N"'" Y See above l > heed needed" l 6 rerrmwed i upper cavity filled pm>ls I connected l 9 5 Y Y" N Y IN Na N" Y" Y" N' N" N*" N*" N"'" N Le above heed needed" i removed upper cavny nnt filled but level raiwd Y is Yes N is No E a w
Characterization of POSs Table A.2-3 Summary of Mdor Systems Available for Each OC (Concluded) Notes
- 1. SLC needed only if rods unavailable. i
- 2. Natural circulation with raised level OK with reactor tripped. I
- 3. TBVs auto control to 950 psig. Below 950 psig use of TBVs requires manual operation.
- 4. RHR SDC auto isolated above 135 psig ;
- 5. ADHRS can only be used in OC 4; suction piping rated at 80 psig. 1
- 6. RCIC auto mode (once through) available from full pressure down to 60 psig (auto isolate). RCIC manual mode (steam condensing) available below 500 psig (auto isolate) down to 60 psig (auto isolate). RHR HX 1 limits steam condensing mode to below 500 psig.
- 7. Consider CRD, fire water, RWCU, condensate, etc. Some of these will only work at low decay heat levels (e.g., RWCU letdown, CRD/ condensate makeup).
- 8. FDW secured but injection with condensate and booster pumps.
- 9. LPCI/LPCS requires p < 500 psig permissive for injection.
- 10. Condensate kept available to raise level if going to OC 5, refueling.
- 11. Below 135 psig, initiate RHR SDC, close TBVs. Assume condenser not available when TBVs are closed (stop cire, water, bredc vacuum, etc.).
- 12. When RHR on SDC, manual re-alignment of RHR A and B required for use as LPCI A and B.
- 13. Witl'out recire. on low, speed natural circulation can be established with level raised.
- 14. ADHRS can only be operated in OC 4 or 5 (< 200'T); suction piping rated at 80 psig.
- 15. In OC 5 with upper cavity filled and pools connected. TS 3.5.2 allows ECCS to be inoperable. In OC 4, or 5 without cavity filled and pools connected,2 of 5 ECCS must be operable according to TS 3.5.2.
In OC 1,2, and 3 all ECCS must be operable according to TS 3.5.1
- 16. Inadequate Decay Heat Removal procedure does not discuss use of ECCS when head is off.
- 17. RWCU is not the primary means of letdown level control since steaming to the condenser is used.
- 18. 2 SRVs required per procedure. i
- 19. Steam Line Plugs in place, vessel head removed.
l 1 l l I i Vol. 2, Part 2 A-7 NUREG/CR-6143 l
Characterization of POS: following functions: level control, reactivity control, and RHR/SDC procedure (# 04-1-01-E12-1, rev 44, step heat removal. All of these functions must be provided to 3.6.1). l cool fuel in the vessel. Since OCs are not one-to-one with system availabilities, During startup, the plant configuration in certain OCs is the initial conditions of the plant prior to the occurrence different than during shutdown. As indicated in the of an accident initiating event cannot be easily specified summary of the startup procedure (see Appendix B, based purely on OCs. For this reason, we developed a Procedure # 03-1-01-1), Grand Gulf uses nuclear heat, as set of Plant Operationa' States (POSs), to segregate the opposed to pump heat, to heatup (decay heat is typically various off power situations into a set of states for which too low to be used for startup). For example, if the the normal configuration of systems (prior to an accident plant is in OC 4, and startup is requested, the follcwing initiating event) can be specified. Thus, a POS is steps are taken: defined as: a plant condition for which the status of plant systems (operating, standby, unavailable) can be (1) RilR/SDC is taken out of service and RHR is specified with sufficient accuracy to model subsequent ' lined up for LPCI. accident events. A POS is not identical to an OC, but POSs are defined based on OCs. In general, an OC , (2) Mode switch placed in Startup (this places unit cannot in itself meet the requirement for a POS. For in OC 2), example, in OC 3, above 135 psig RHR on SDC cannot be used and the Turbine Bypass Valves (TBV) or RCIC (3) Rods are pulled to critical. are used; while in OC 3, below 60 psig RCIC cannot be (4) Turbine bypass is made operable. There are some OCs that are essentially the same in (5) Rods are pulled and primary heats to terms of system availabilities and primary thermal temperature (pressure) where moderator hydraulic conditions, and these were treated as one POS. feedback re-establishes criticality. For example, OC 1 and OC 2 differ only in the power l level, rods positions, and recirculation pumps speed - all (6) Step 5 continues with heatup rate limited to s f which are minor in terms of accident sequence 80 degrees F per hour. pr gressi n, since reactor shutdown / trip with the rods is essentially the same regardless of power level, and recirc (7) At rated pressure (temperature), Turbine Bypass is not required post trip. The pressure / temperature of Valves (TBVs) control pressure. Rods pulled to the primary is almost identical in OC 1 and 2 (during position for 4% power, and power goes to 4% shutdown): about 1000 psig and about 550 degrees F. In (fuel Doppler re-establishes criticality at 4 % OC 3 from 1000 psig down to 500 psig, the systems power). configurations important to the accident analysis are identical to the configurations in OC 1. The main (8) Mode switch placed in Run, and power differences are: in this upper pressure range of OC 3 increased. Recire flow controlled, turbine the rods are all in, and the turbine / generator is tripped. rolled, and generator loaded per Als , the pressure / temperature conditions that affect procedure. Full Power established. accident sequence progression are not drastically . different at 500 psig from those at 1000 psig. la contrast to the situation during shutdown, during I normal startup the unit goes from OC 4 directly to OC 2 Using the OCs as a starting point, the following seven , without passing through OC 3. This is because the mode POSs were defined: j switch is placed in Startup to allow rods to be pulled t (1) POS 1 consisting of: OC 1 and OC 2 with heat up the unit. When the unit initially enters OC 2 pressure at rated conditions (about 1000 psig) i durmg startup, it is at low pressure and temperature. and thermal power no greater than 15 %. However, the system lineups are basically the same as when the unit is in OC 2 during shutdown (i.e., (2) POS 2 consisting of: OC 3 from rated pressure - RHR/SDC is isolated, ECCS is operable, and turbine ' to 500 psig. bypass is operable). During the startup process, should it be required to initiate RHR/SDC, the rods will be fully (3) POS 3 consisting of: OC 3 from 500 psig to I inserted prior to establishing RHR/SDC, per the where RHR/SDC is initiated (about 100 psig). NUREG/CR-6143 A-8 Vol. 2. Part 2 l _ _ _]
Characterization of POSs (4) POS 4 consisting of: OC 3 with the unit on upper and spent fuel pools connected: spent fuel RHR/SDC. pool cooling can be used to cool fuel in vessel, ECCS allowed inoperable per Tech Spec 3.5.2. (5) POS 5 consisting of: OC 4 (Ts 200 degrees F) and OC 5 until the vessel head is off and level is This selection of POSs was based on the factors indicated raised to the steam lines. in Table A.2 3. Because the information in this table is based on system configurations during shutdown, it must (6) POS 6 consisting of: OC 5 with the head off and be shown that these POSs handle system configurations level raised to the steam lines. during startup as well. For POSs 6 and 7, there is no distinction between system configurations for shutdowri (7) POS 7 consisting of: OC 5 with the head off, and startup. As discussed previously, during normal the upper pool filled, and the refueling transfer startup the unit passes from POS 5 directly to POS 1. tube open. However, should the heatup process be stopped (for example, to institute RHR/SDC), the rods are inserted Control rods are fully inserted in POSs 2, 3,4,5,6, and and the mode sw;tch placed in Shutdown. Therefore,
- 7. should the unit enter POS 4,3, or 2 during startup, it will do so with the same system configurations as during The reasons for this segregation of the five OC into these shutdown, and POS 4, 3, and 2 apply equally well to ,
seven POSs are indicated in Table A.2-3, and the most both situations. POS 1 is characterized as bei,g at rated salient ones am as follows: pressure, the situation during shutdown. During startup, the unit enters POS I at low pressure, but with the same (1) OC 1, OC 2, and OC 3, down to 500 psig: lineups as for rated pressure since the idea is to heat up steam dump to be condenser is used, feedwater to rated pressure in this configuration. A rise to rated is available, and omer similar characteristics pressure is therefore of no concern in POS 1 during exist. startup, and POS 1, as defimed for shutdown, applies equally well for startup. (2) OC 3, between 500 and 100 psig: have the potential to use RCIC in the steam condensing It is interesting to note that for Grand Gulf ECCS mode (not used currently at Grand Gulf), the injection is not required to be manually blocked during pressure is below the LPCI/LPCS permissive cooldown as the unit depressurizes, because ECCS setpoint, and feedwater is secured but actuates on level, not purely on pressure, and water is condensate / booster makeup is still available, maintained at normal level during cooldown. This is in contrast to PWR's where ECCS actuates on pressure and (3) OC 3, between 100 and 0 psig: RHR on SDC, must be blocked during cooldown and reset during level control with RWCU, RCIC unavailable heatup. (conservative assumption since it is available above 60 psig), LPCI trains A and B require A.3 Definition and Characterization manual re-alignment of RHR from SDC. of POS Change Initiators (4) OC 4: vent can be opened, ADHRS can be After an understanding of how the plant operates and/or used RCIC cannot be used, RHR on SDC and transitions among the identified POSs was obtained, it LPCI trains A or B requires manual re- became necessary to identify the reasons why the plant alignment, LPCI/LPCS flooding through tw would be required to change its POS and the implications open SRV s to the SP can be used. . of such a change (i.e., known pre-existing system and/or mp nent unavailabilities). Since the major concern of (5) OC 5 with head off, level raised but upper . this study was with accidents occurring in non full power cavity not flooded: spent fuel pool cooling POSs its focus was on controlled shutdown imtiating cannot be used for fuel in vessel, ECCS events. Also meluded are reactor trip events which required operable per Tech Spec 3.5.2 (r.ee allow orderly transition among POSs, hereafter called Appendix B for discussion of procedure for ,
, , nuisance' trips are included Inadequate Decay Heat Removal). because they affect the amount of time that the plant is in POSs asso:iated with conditions other . n full power.
(6) OC 5 with head off, upper cavity flooded, and Vol. 2, Part 2 A-9 NUREG/CR-6143
Characterization of POSs Note, that by definition such nuisance trips do not trip are not accident initiating events, since they do not prevent the plant from transitioning among POSs in an prevent controlled transitions among POS. However, orderly manner, they can impose known, pre-existing unavailabilities if a subsequent accident initiating event occurs. Reactor trip For accident sequences initiated from full power as initiating events are, in gennal, accident initiating events modeled in full power PRA's, this study addresses only since they require mitigative actions to handle the event those sequences defined in the top success path of the without regard to orderly transitions ainong POSs. For full power accident sequence event trees, for which the example, following a LOCA at full power, the plant does plant can transition among POSs in an orderly manner. not undergo an orderly transition to cold shutdown - ECCS systems respond as necessary to mitigate the ne coarse screening study did not address the long term break. Only certain types of events requiring reactor trip issues following a non-nuisance reactor trip from full allow subsequent transitions among POSs. These include power. Consideration of such events is an extension of those that do not affect the ability to transition, or those traditional full power PRA analyses of accident that can be easily fixed to allow transition (e.g., the sequences. Full power PRAs model the response of the nuisance trips described above). Events requiring plant out to the time at which conditions are stabilized controlled shutdown, such as refue'ing or inoperable (e.g., hot shutdown for transient initiated accident equipment, lead to orderly transitions *down* among sequences). However, the long term response of the POS. Transitions *up* among POS occur following plant is not considered. outages or equipment repair . He methodology employed in this study is not directly In this study a POS Initiator has the following definition: i suitable for analyzing such concerns, since the An event which initiates controlled shutdown of the plant methodology assumes that the plant is initially in a stable from full power, a nuisance trip from full power, or an condition in a POS, and not initially transitioning into a event which requires the plant to transition up or down POS from an accident at full power. He concept of among POS in response to outage requirements or POS is not always meaningful for accidents initiated at equipment conditions. ' full power anyway, since the plant responds to the accident rather than transitioning among POS. For For the purposes of describing how the POS change example, jollowing a large LOCA the plant systems initiators were identified and the implications of euch citempt to mitigate the LOCA rather than transition in a initiators, the initial state of the plant is assumed to be controlled manner to cold shutdown. full power; and before the first initiating event occurs it is assumed that no significant known system he fact that the screening study did address these unavailabilities exist. The analysis starts when an event t nuisance trips and not the more stressful, but less likely, occurs that requires transitioning the plant through a set trips which progress along an event tree path (other than of POSs. the top success path) should not be iaken to imply that a transition to a POS following a nuisance trip is believed In general a given POS can be entered in one of four to be of higher risk than long term considerations ways: following the more stressful trips. Rather it is a reflection of two facts: (1) nuisance trips occur relatively (1) coming down from full power for a scheduled frequently (on the order of one to ten times a year refueling outage, depending on the particular plant), and (2) the ' methodology developed for quantifying accidents (2) coming down from full power not for a < occurring following transitions among POSs can easily scheduled refueling outage, handle the nuisance trips as defined above. Also, the ' full power PRAs dg analyze the accident sequences (3) going up to full power following a refueling ' associated with non-nuisance trips, although 1.gng_tum. octage, er accident management issues are not addressed. (4) going up to full power not follov6g a refueling A distinction must be made between what is meant by outage. accident initiating events and initiating events which require a transition among POS. For example, initiating events requiring controlled shutdown but not a reactor NUREG/CR-6143 A-10 Vol. 2. Part 2 l
Characterization of POSs
'Ibe following seven categories or classes of POS Based on our understanding of the plant characteristics Initiators were identified: and operating practices, we developed seven rules of .
analysis for evaluating each POS. l Class Description l Rule (1): When an accident initiating event occurs in a l
- 1. Refueling. The plant is scheduled for its next given POS, the event tree for that accident initiator in refueling outege. that POS totally describes the subsequent behavior of the plant. Once an accident occurs, the plant systems focus
- 2. Controlled shutdown required by Technical on mitigating that particular accident rather than on l Specifications (Tech Specs) due to violation of a transitioning among the POS.
Safety Limit (SL) or Limiting Condition of Operation (LCO). Rule (2): The Etnicture of the accident event trees and constituent fault trees in a given POS for a given
- 3. Controlled shutdown required by Tech Specs accident initiating event, are independent of how the due to missed Surveillance Requirement (SR). plant transitioned to that POS; (except that consideration of additional methods of core cooling are considered at
- 4. Controlled shutdown due to failures in non-Tech low decay heat levels that exist going up following a Spec equipment. refueling outage). This rule follows from rule (1), ir.
that any accident within a POS renders transitioning to a
- 5. Preventive maintenance. subsequent POS invalid. Thus, entry into a given POS is without an accident having previously occurred. Of ,
- 6. Change necessitated by a reactor trip from full course, the availability of systems and components is ;
power (nuisance trip only). aff.cMd by known, pre-existing unavailabilities.
- 7. First time startup or final shutdown. Rule (3): For any POS 6, 5, 4, 3,2, or 1 that is entered following a refueling outage, there are no known, pre-After these seven classes were developed, they were existing unavailabilities. This rule is based on the examined to determine if a change in the plant's POS assumption that the plant will not be restarted following a necessitated by one of these events would impose known, refueling outage if known, major equipment pre-existing unavailabilities. For Class 1, the following unavailabilities are present.
assumption was made: the plant would not enter refueling (i.e., POSs 6 and 7) knowing that a system Rule (4): For POS 6, no known, pre-existing required during the refueling outage was unavailable. unavailabilities exist. This rule is based on the Class 2 events can impose pre-existing unt.vailabilities, assumption that a refueling outage is a scheduled event if an inoperable system is requiied during shutdown, and does not occur simultaneously with any other POS then entry into an action statement will impose known, initiator. Conversely, if a POS initiator occurs which pre-existing unavailabilites. If the system is not renders equipment inoperable, it is assumed that the required, then no known, pre-existing unavailability problem will be fixed in POS 4 or 5. POS 6 or 7, which exists. Events in Class 3 do not impose known, pre- involve vessel head removal, are not entered. existing unavailabilities. Class 4 events may impose pre-existing unavailabilities. If the equipment is taken credit Rule (5): For any POS entered in returning to power l for in a PRA (i.e., used to mitigate an accident initiatmg following a non-refueling outage, there are no known, event), then its failure does impose a pre-existing pre-existing unavailabilities from any time prior to entry unavailability. If not, then no pre-existing unavailability into the first POS. This rule is based on the assumption ) cxists. Class 5 events do not impore pre-existing that the reason for coming down in power is fixed prior j unavailabilities, because if the equipment were non- to going back up in power. functional, then it would be in Class 2 or 4. Class 6 events do not impose pre-existing unavailabilities, since Rule (6): Failures occurring in a POS following the POS only reactor trips associated with nuisance trips are initiator which required entry into the POS, are accident analyzed. No exact determination of Class 7 events was initiating events, and by rule (1), do not affect 1 made, as these events were outside the scope of this subsequent POS. Failures in one POS can affect tic ! project. availability of equipment in a subsequent POSs. Rules (3), (4), and (5) limit those earlier POS to which Vol. 2 Part 2 A-11 NUREG/CR-6143 i
i Characterization of POSs 4 consideration should be given. We have made the transitioned to; thus, accidents due to random additional assumption that any failure subsequent to the failures are less likely. POS initiator initiates an accident. The rationale for this assumption is that in most cases in the POS, even if b) For Grand Gulf, and many other plants, this redundant trains exist, only one train is in operation assumption is further supported by the practice ; (Shutdown Cooling with RHR, for example), and a to not disable one functional system (such as failure in the running train and starting the backup train core cooling with turbine bypass) until the is modeled in the accident sequence event trees. replacement system (such as shutdown cooling) is shown to be operable. Rule (7): For any POS entered except as part of a planned refueling outage, the fault exposure time for c) Finally, the historical record of events occurring standby components is T,/2, where T, is the average time at shutdown shows that they do not occur during ; between testing of component i. For any POS entered as transition states. part of a scheduled refueling outage, the fault exposure + time is T* +T /2, where T is the time interval from the We believe that &e most probable situations for which , last test of coEponent i, andentry in to the POS, and unique initiating events can occur during a transition l T is the duration of the POS. This rule is brsed on the state, are those associated with rod withdrawal during i fEt that refueling is a scheduled (non-random) event. startup. Errors in rod movements during such situations can challenge the reactor trip system. Such situations do These seven rules taken together, enable the accident not occur in cold situation. sequences for a given POS to be evaluated without rigorously considering all the details of how the plant transiticaed to that POS. V However, this methodology cannot in eeneral handle time dependent changes in system configurations. For example, the methodology cannot easily model all the possible changes in system availabilies during a refueling outage as extensive maintenance is performed on different systems. For cold shutdown at Grand Gulf, (the subject of this report), this is not a serious limitation since train A is frequently taken out for maintenance in i cold shutdown. This was the conservative assumption used in our model. To assess risk during actual refueling operations involving extensive testing and maintenance, the methodology may have to be improved to consider ' rolling' unavailabilities of equipment. Similarly, the methodology cannot easily consider accidents that occur as the plant transitions among modes during shutdown. For example, in hot shutdown the plant operators switch fmm cooling with turbine bypass I to cooling with shutdown cooling at about 100 psig. , Plant conditions are changing during this transition, and cre different than those present while either on turbine bypass ecoling or on shutdown cooling. We have assumed that accidents occurring during such transition ; operations are adequately considered by our models for the initial and final states of the transition, for the following reasons: a) The time spent in transition is less than the time spent in the states transitioned from and NUREG/CR-6143 A-12 Vol. 2, Pan 2
1 Characterization of POSs References for Appendix A [ Whitehead et al,1991] D. W. Whitehead, .I. L. [USNRC 1984] USNRC, " Technical Specifications, Darby, B. D. Staple, B. Grand Gulf Nuclear Station Unit No. Walsh, T. M. Hake, and 1*, Docket No. 50-416, Appendix *A* T. D. Brown, "BWR Pow to License No. NPF-29, NUREG-0934, Power and Shutdown October,1984. Accident Frequencies Project, Phase 1 - Coarse [SERI,1992] System Energy Resources, Inc.,
- Grand Screening Analysis", Vol. Gulf Updated Final Safety Analysis 1, Draft Letter Report, Report," Revision 7,1992 Sandia National Laboratories and Science and Engineering Associates, Inc.,
November 23,1991 update. (Available in USNRC Public Document Room) l i l Vol. 2 Part 2 A-13 NUREG/CR-6143
. - . - - - = _ l l 1 Appendix B Summary of the Detailed Review of l Selected Grand Gulf Procedures
- This appendix summarizes the information obtained (off startup). Power is increased by withdrawing rods, dud a detailed reviews of selected Grand Gulf Power is held at 20% for about 1.5 hours to allow heat Proc Aures. He reviewed procedures include: rate data to be gathered. As soon as the low power setpoint (20%) is exceeded, the operability of the Rod (1) Power Operations #03-1-01-2, Withdrawal Limiter (RWL) is verified per Tech Spec 4.1.4.2.b.l. Power is held at 40% for about 1.5 hours (2) Plant Shutdown - #03-1-01-3, to allow heat rate data to be obtained. When the reactor is stable above 34% power and below the 80% rod line, 3 (3) Refueling - #03-1-01-5, the flow control valves are closed to minimum position, and the recirculation pumps are switched from low to (4) Cold Shutdown to Generator Carrying high speed. At about 40% power, feedwater is placed m Minimum Load - #03-1-01-1, and three element control where pump speed is a function of !
steam flow, vessel water level, and feedwater flow. At (5) Inadequate Decay Heat Removal - #051-02-111- about 45 % power, the second RFPT is placed in service i
- 1. on master level control, and the second circulating water !
pump is placed in service. Rods are positioned at the For each procedure the most important steps (tasks) are desired flow control line, and power is increased by ; identified and summarized both in text and tabular opening the recirculation flow control valves and thereby [ format. In addition, the important precautions, increasing recirculation, with the rods fixed. Power is limitations, actions, and prerequisites are presented. held at 60% for about 1.5 hours to allow for gathering of heat rate data. As soon as the high power setpoint is ! B.1 Power Operations - #03-1-01-2 reached (70 %), RWL operability is demonstrated. At about 80% power and 90% core flow, all ECCS line his procedure covers three situations: (A) low to full break alarms should be cleared, but any applicable LCOs power increase, (B) full to low power decrease, and (C) are entered for alarm not cleared. (Evidently the rapid power reduction. *ECCS line break alarms
- are readouts from the i
" injection permissive" low pressure sensors of Tech Spec i The prerequisites (initial conditions) for this procedure table 3.3.31 which, upon low pressure, permit LPCI and LPCS injection given either low vessel level or high .
are as follows: For situation (A) recirculation is on low speed, the flow control valves are fully open, one reactor drywell pressure.) Power is held steady at both 80% and feed pump is maintaining vessel level, and the main 100% for about 1.5 hours to allow heat rate data to be ; generator is synchronized to the grid carrying about 15 % gathered. (196 MWe) load. Heat removal is through the loaded turbme with Turbm, e Bypass Valves (TBVs) open. For h abm idwim is a -him oW information presented in Table B.I.2. situations (B) and (C), the prerequisite conditions are those established in this procedure for a defined power B.I.2 Full Power to Low Power Decrease level. See Table B.I.! for a list of the most important , precautions, limitations, and actions. Full power to low power decrease, situation (B), is I accomplished essentially by reversing the steps just B.1.1 Low Power to Full Power Increase described for (A). Ifit is desired to trip the turbine, this is accc mplished by manual action once power is 100 to Situation (A), low to full power increase, is 150 MWe. He generator then automatically trips on accomplished as follows: The loading instructions are reverse power since with no driving torque it acts like a obtained from the system dispatcher. The load demand motor and draws power from the grid. The TBVs are ; is increased in increments until the TBVs are fully verified to be maintaining vessel pressure. See Table l closed. (As more steam flows to the turbine, the turbine B.I.3 for the appropriate steps for this portion of the , header pressure dro9s, and once it is below the TBVs procedure. setpoint they close!/ The TBVs are verified to be fully closed before raising power above 20% to satisfy Tech B.I.3 Rapid Power Reduction Spec 4.1.4.1; and the reactor feedwater pump turbine I (RFFT) is verified to be on the master level controller Rapid power reduction, situation (C), is achieved by Vol. 2, Part 2 B-1 NUREG/CR+143
Review Procedures using the fast mode of recirculation flow reduction. If psig, the running RFPT is secured, and it is verified that further reduction in power is required, the rods are only one booster / condensate pump combination is inserted, ne appropriate steps in (A) of this procedure running. Cooldown with the TBVs is continued as long are then followed. If reactor scram occurs, the Reactor as possible. When necessary, SDC with RIIR is placed Scram procedure #05-1-02-1 is followed, into operation. At 200 psig, one RWCU pump is secured if both pumps are running. At 100 psig, the , Table B.I.4 lists the steps necessary for performance of running RWCU pump is transferred to the pre-pump this section of the procedure. mode. The TBVs are closed (manual operation is stopped), and the pressure setpoint is set at 100 psig B.2 Plant Shutdown - #03-1-01-3 above reactor pressure. Heat removal is via RHR on SDC. If desired, the condenser vacuum is broken, and cire water is shutdown. When vessel temperature is his procedure takes the plant from Operating Condition (OC) I at about 12 % power down to zero power in below 190 degrees F (unit enters OC 4 at 200 degrees either OC 3 or 4. The prerequisites (initial conditions) F), the primary is vented to the atmosphere by opening are as follows. Reactor power is about 12%, and the F001 and F002 and closing F005. This establishes 0 turbine is offline. Recirculation pump (s) on low speed psig and renders the primary subcooled. To prevent with flow control valves (FCVs) full open in loop manual thermal stratification, recirculation on low speed is c ntinued. If either recirculation or SDC is lost, control. Heat removal is via TBVs to the main i condenser. procedure #0NEP 05-1-02-111-1 " Inadequate Decay heat i removal" is followed. Coo.Jown is continued to 120 to l Re proceduce nas two perts. One deals with cooldown 130 degrees F. I.evel is controlled via RWCU j keeping the main steam isolation valves MSIVs open, blowdown to either the condenser or radwaste. To maintain cold shutdown conditions as desired, RHR is and the other deals with cooldown when the MSIVs are closed during the cooldown. See Table B.2.1 for a list perated in the SDC mode per procedure #SOI 04-1 i of the most important precautions, limitations, and E12-1. actions. The above information is a summarization of the inf rmati n presented in Table B.2.2. B.2.1 Cooldown with the MSIVs Open B,2,2 Cooldown with the MSIVs Closed Cooldown with the MSIVs open is accomplished as follows. If rapid and complete shutdown is desired, the reactor is manually tripped and the Reactor Scram Cooldown with the MSIVs closed during the cooldown procedure #0NEP 05-1-02-1-1 is followed. Otherwise, process is similar to the case with the MSIVs open. The the following steps are taken. Rods are inserted to main difference is that just before the MSIVs are closed, reduce power to about 8 %. ne IRMs are inserted. All RCIC is placed in operation in the open cycle mode surveillance requiremeris (SRs), per the Tech Specs, are (injection from the CST or SP) per procedure #50! 04 completed before entry into OC 2. The mode switch is 01.E51-1. Unless decay heat is so low that the steam ) placed in STARTUP, and hence the unit enters OC 2. discharged to the RCIC turbine provides adequate heat l Rods are inserted, the SRMs are inserted, and the TBVs removal, the SRVs will cycle and relieve to the SP. SP l are verified to close at the 950 psig turbine header cooling is instituted if necessary. RHR on SDC is placed j pressure control setpoint. All conditions for entry into in operation below 135 psig, and RCIC is isolated above i OC 3 are met, and the unit enters OC 3 as the mode 75 psig (RCIC auto isolates at 60 psig). It is important switch is placed in SHUTDOWN position when all rods to note that if RCIC is inoperable, then HPCS with SRVs cre fully inserted. Reactor power is zero (except for (relief mode) can be used. See Table B.2.3 for the steps decay heat). Cooldown is continued at less than 80 necessary for performing this portion of the procedure. degrees F per hour by manually opening / closing the TBVs. (Operation of the TBVs reduces reactor pressure. B.3 Refueling - #03-1-01-5 l Temperature also decreases along the saturation line due l to controlled fin.hing as pressure decreases.) Level This procedure takes the plant from OC 3 down to OC control n mamtamed with feedwater. The steamjet air 5, and from OC 5 up to OC 4. The prerequisites going ejectors (SJAEs) are secured and hoggers are placed in down are that the plant is in OC 3 per procedure #03 l operation to maintain condenser vacuum. At about 500 01-3
- Plant Shutdown." The prerequisites going up are NUREG/CR-6143 B-2 Vol. 2, Part 2
I Review Procedures that the plant is in OC 5 as specified in this procedure. information presented in Table B.3.2. See Table A.3.1 for a list of the most important precautions and limitations. B.3.2 Reactor Pressure Vessel Reassembly B.3.1 Plant Cooldown and Entry into OC 5 The steps for bringing the unit from OC 5 with the upper ne steps for going from OC 3 down to OC 5 are as reactor cavity flooded, to OC 4 are essentially the follows. Per procedure #03-101-3 the unit is being reverse of the appropriate preceding steps. See Table cooled down with the TBVs. Once pressure is below B.3.3 for a list of the appropriate steps. 135 psig, SDC via RHR is instituted, and the TBVs are removed from service. The MSIVs are closed. RWCU is placed in the blowdown mode, but the condensate B.4 Cold Shutdown to Generator system is retained for vessel flooding. With condensate Carrying M. .inimum Load - #03 . and using the startup level controller, the. level is raised 01-1 above the RPV head flange. Cooldown with SDC is continued (OC 4 is entered at 200 degrees F) to about 80 This procedure controls the activities necessary for degrees F. (It is venfied that RCIC suto isolated at 60 reactor startup, unit heatup, and turbine startup and psig.) The fuel transfer tube closure hatch is opened, generator synchronization. The prerequisites (initial thus enabling fuel to be moved from the upper conditions) for this procedure are as follows: The containment pool to the spent fuel storage transfer pool reactor vessel head must be in place with the studs m the auxiliary buildmg, once isolation valves in the transfer tube are opened. The gate and seal between the tensioned. He mode switch must be in the SHUTDOWN or REFUEL position. Recirculation is in upper containment pool and the reactor upper cavity is operation on low speed, with the flow control valves full mstalled, thus isolating the upper reactor cavity. The open and in loop manual control. The control rod upper reactor cavity is dramed to the Refuehng Water hydraulic system is in operation, and the RWCU system Storage Tank (RWST). The drywell head is removed. is blowing down to the condenser or radwaste system to Vessel level is lowered (with RWCU blowdown) to one foe or more below the flange. All external connections maintain level at normal level. RHR is in LPCI standby, or another mode as required, and ADHRS is in the to the vessel head are removed. The head studs are isolate mode per procedure # sol-04-1-01-E12-1. (It detensioned. This places the unit in OC 5, Refuelmg. should be noted that Section 3.1 of the procedure defines The vessel head is removed. Recirculation is throttled with the FCVs to reduce water npple. The steam dryer .., standby" as able to respond upon automatic or manual
'* * " A " P"
is removed. The vessel is drained to below the main steam lines, and steam line plugs are installed. The egnty of primary cmtainment, seemdary l upper reactor cavity is reflooded from the RWST and the # "'"* **"I' "" I** " **" E D*# steam separator is removed as the upper cavity fills. turn ng gear. ' Circulating water is m operation. Usually, Once the upper cavity is filled, the gate / seal between the
. . the MSIVs are closed, atmoephenc vents F001 and F002 upper reactor cavity and the upper contamment pool is are open, and temperature is below 190 degrees F. The removed. (Later, m preparation for fuel transfer, the primary coolant is subcooled, and the unit is in OC 4.
transfer tube isolation valves wdl be opened. At this time, the vessel w See Table B.4.1 for a list of the most important the upper reactor cavity, the water the m;ater, the water upper containment pool, m, and the precautions, limitations, and actions associated with this water in the spent fuel storage pool are interconnected E** " since the vessel head is off, the upper reactor cavity is flooded, the gate between the upper cavity and the upper B.4.1 Reactor Startup containment pool is open, and the refuel 4 tube connecting the upper containment pool to the spent fuel Reactor startup is completed as follows. RHR is aligned storage pool is open.) Most of the requbed in-vessel s that LPCI can be initiated with no manual work is performed with the unit in these conditions. (In realignment; thus, shutdown cooling is not provided service inspection of the vessel is performed with a since alignment of RHR for shutdown cooling is not lower water level.) allowed. The only active core cooling present is that due to injection from the control rod hydraulic system and The above information is a summarization of the blowdown with the RWCU system, and that is Vol. 2 Part 2 B-3 NUREG/CR-6143
- - - ' - - ' " - - - . -..n_ . .
Review Procedures insufficient to prevent heatup. It is acceptable to have no service per procedure #SOI-04-1-01-N21-1. At about active core cooling during heatup because: 500 to 800 psig, the steamjet air ejectors are placed in service to provide condenser vacuum. At about 950 (1) It is desired to heatup the unit anyway, psig, the TBVs operate at their setpoint, and open as thermal power increases. The mode switch is transferred (2) ne time to heat to saturation in this condition to RUN and the unit is in OC 1, with thermal power at is long since the unit has been shutdown for an about 4 %, electrical power zero, pressure about 950 psig appreciable time and decay heat is low saturated, and steam being dumped to the condenser via (procedure #05-1-02-3-1 provides curves giving the TBVs. As power increases, the rods are withdrawn , time to boil), and to overcome the Doppler effect in the fuel and maintain l criticality. See Table B.4.3 for the important steps (3) LPCI is available if needed. associated with this portion of the procedure.
?
De mode switch is placed in STARTUP and this places B.4.3 Turbine Startup and Generator the unit in OC 2 (not that OC 3 is skipped during Synchronization
- abnormal startup). The rods are withdrawn per the specified pattern until the unit is critical, nis plant uses Turbine startup and generator synchronization are nuclear heat to heat up as opposed to pump heat as ,
accomplished as follows. The turbine stop valves are utilized in many PWRs. (The BWR can maintain opened. The second stage moisture separator reheater is shutdown margin with rods alone at near ambient placed in service. The EHC is set for 400 rpm and the temperatures while the PWR cannot. Thus, criticality on turbine is rolled to 400 rpm as the turbine control valves rods in the BWR at low temperatures is acceptable.) open in response to the EHC signal. The turbine speed is increased to 1800 rpm. ne turbine bypass valves are ne above information is a summarization of the verified to be at least 20% open to accommodate ! information presented ir, Table B.4.2. generator synchronization and loading. The generator is ! to be operated with constant output voltage using the B.4.2 Unit Heatup voltage regulator in auto control (the emf of the generator is varied with load to maintain constant i Unit heatup is accomplished as follows: The vent to terminal voltage). The load dispatcher is notified that the ; ctmosphere is isolated by closing F001 and F002. F005 generator is ready to come on the grid. The EHC is set is opened to provide controlled venting of to 1805 rpm, and at the 12 o' clock position on the ! noncondensibles to the main condenser. As the unit is synchroscope, the generator is connected to the grid. ; heated up, the water will follow the saturation curve and The 12 o' clock position corresponds to the generator temperature will be the saturated value at the existing voltage being equal and opposite to the grid voltage and pressure. The vacuum in the main condenser is hence the generator is not loaded (no current to the grid). established with hoggers (mechanical s acuum pumps). The grid provides synchronizing power to lock the speed i Heatup is initiated by withdrawing rods, and the rate is in at 1800 rpm. (A speed settine of slightly greater than kept below 80 degrees F per hour. He rods must be 1800 rpm does not change the turbine speed once the i withdrawn to maintain criticality as the primary heats up generator is on the grid. It moves the TCVs to a ' to counter the negative temperature coefficient of the position corresponding to the speed setting and thereby moderator, ne turbine bypass stop valves are opened. establishes the generator output power. Speed control The chemical conditions of the primary are verified to be can only be used up to about 175 MWe, thereafter load : acceptable. It is verified that one condensate pump is in control is used.) Power output is increased with speed operation. Feedwater level control is instituted using the control to between 75 and 150 MWe. He first stage ; startup level controller. At about 60 psig, RCIC is moisture separator reheater is placed in service. Power l placed in standby. Letdown with RWCU is stopped output is raised to about 17S MWe by setting speed ! when automatic control on level with feedwater is { demand at about 1812 rpm. Control is transferred from , l established. At about 100 psig, one RWCU pump / filter speed to load demand. Electrical power is not to exceed j is placed in cleanup mode. At about 200 psig, the 24 % during use of this procedure. The second second RWCU pump / filter is placed in cleanup mode. condensate and booster pumps are started. The high At about 400 psig, the TBVs are verified to be about pressure feedwater heaters are placed in service. (The 10% open and one feed pump turbine is rolled into low pressure feedwater heaters were placed in service service; evidently, the second feed pump is placed in NUREG/CR-6143 B-4 Vol. 2, Part 2 l
Review Procedures when steam was admitted to the low pressure turbines, and the unit is taken to cold shutdown per procedure since no valves need to be opened to extract steam to the #03-1-01-3. See Table B.S.3 for the important steps low pressure heaters, as indicated on Figure 10.3-4 in corresponding to this portion of the procedure. the FSAR.) See Table B.4.4 for a list of the steps described above. B.S.2 Fuel in the Vessel and the RPV Head B.5 Inadequate Decay IIcat Removal
- #05-1-02-III-1 If inadequate decay heat removal is encountered with the vessel head removed, the mitigative actions depend on The inadequate Decay IIcat Removal Procedure whether or not the upper reactor cavity pool is filled with addresses two situations with respect to loss of decay water. If the upper cavity is filled with water, then fuel heat removal. These are inadequate decay heat removal p of cooling is maximized if necessary until SDC with when fuel is in the vessel and the unit is in OC 4 and RilR or AD11RS can be re-established. (As discussed in Section B.3, the vessel water, the upper reactor cavity when fuel is in the vessel and the vessel head is off.
Table B.5.1 lists the symptoms which indicate a loss of p 1, the upper containment pool, and the spent fuel heat removal capability, and Table B.5.2 provides a list storage pool are interconnected when the head is off and the gates and valves isolating the pools are open. In this of the immediate operator actions which should be situation, the pool cooling system can cool vessel water performed given entry into the procedure, as well as pool water.) B.S.1 Fuel in the Vessel and the Unit in . Ifm. adequate heat removal is encountered with the vessel OC4 head off and the upper reactor cavity pool not filled, then the following steps are taken. Recovery of SDC with If inviequate decay heat removal is encountered while RIIR or AD11RS is attempted as soon as possible, and the un't is in OC 4, the following steps are taken. Note vessellevelis raised. If SDC with RIIR and ADilRS ehat if decay heat removal is not restored prior t are totally lost, letdown and makeup are increased to the entering OC 3, the ADilRS must be isolated (its suction maximum (RWCU and CRD/ condensate). Ifincreased design pressure is only 80 psig). If the in-service loop letdown is not adequate, the fire water system is aligned of RiiR on SDC is lost, the other RilR loop or the to flood the vessel, and appropriate vessel drain lines are ADHRS is placed in operation for SDC. If forced opened. t recirculation (Iow speed) i , lost, level is raised to about 82 inches to promote natural circulation and attempts are Tables B.S.4 and B.5.5 list the important steps associated made to restore recirculation. If RilR SDC is also lost, with this section of the procedure. the head spray is operated, if available. If SDC with , Rl"t and cooling with ADilRS are completely lost, With the vessel head off, if ECCS injection is used, the [ RWCU letdow and makeup (CRD hydraulic and water injected into the vessel will exit the open top and condensate) are increased to the maximum to maximize fill the upper containment if the SRV's are unavailable their effect on cooling. (This alone will only work for due to installation of steam line plugs. In this situation, low decay heat levels, but it does increase the time the operator will throttle ECCS injection to avoid available to institute other measures. The maximum overfilling upper containment. I letdown rate with RWCU is about 360 gpm, which can match decay heat only if the unit has been shutdown for obout 17 days or longer.) Also, Attachment #1 of the procedure is used to estimate the time to boil. If SDC or ADliRS cannot le restored within this time, the following steps are taken: SP cooling is initiated, all vents are closed (F001 F002, and F005), the MSIVs are closed, the RCIC steam line isolation valves are closed, SRVs are manually operated so that two of them are open, the vessel level is increased with any available means to 101 inches to 129 inches to allow water discharge to the SP, LPCS and/or LPCI are actuated to supply coolant to the vessel from the suppression pool, Vol. 2. Part 2 B5 NUREG/CR-6143
Review Pro edures i Table B.I.1 Precautions, Limitations, and Actions Associated with Procedure 03-1-01-2 11rg Descrintion 2.2 Adhere to power distribution limits specified in Tech Spec 3/4.2. 2.4 Generator loading must be within limits of the curves given in Figures I and 2. 2.5 Maintain thermal power less than or equal to that allowed as a function of core flow as specified by
- Power to Flow Operating Map".
2.7 Balance recirculation loop flows per Tech Spec 3.4.1.3. 2.10 Decrease load as specified when feedwater heaters / reheaters are out of service. 2.16 Do not pull rods if thermal power > 20% unless TBVs are closed (Tech Spec 3.4.1). , 2.21 At turbine loads < 50% condensor vacuum should be maintained 2 3.63 psia as steam cooling on last stage blades is minimal. n NUREG/CR-6143 B4 Vol. 2, Part 2 l l
P- Table B.I.2 Summarization of Procedure Steps Necessary for Low Power to Full Power Increase m E OC w Reactor Power, P Step Elecinc hwer, - Reactivity Heat Ranoval Comments P P (p*ig) T CF) 5.0 low power to full power increase OCI Critical on rods with loaded turbine and P, - 15 % recirculation low speed, turbine bypass P, - 15 % FCVs full open P rated T_(p) 5.1 Obtain loading instructions from system dispatcher 5.2 Increase load demand in Reactor power fixed; As flow to turbine increases, turbine increments until TBVs are closed send more steam to header pressure draps below TBVs set
$ turbine and less via point and bypass valves close.
TBVs 5.3 Before increasing thermal power Cha. age reactor power Loaded turbine lead demand increase opens TCVs,
> 20%, verify TBVs closed per with rods only until generator voltage automatically shifts Tech Spec 4.1.4.1 switch recirculation to in phase to provide more electrical high speed and establish power. Don't pull rods if < 20%
rod pattern (5.1I and power unless TBVs closed. 5.16) 5.4 Check that RFPT is on FW Off startup, on master level controller master level controller before exceeding 20% power 5.5 l'old for 1.5 hrs. at ~20% Allow for gathering of beat rate data power Z 5.7 As soon as low power setpoint LPSP = 20% P (LPSP) exceeded, verify RWL f RWL is Rod Withdrawal g' a operability per Tech Spec Limiter (for power pealang) , 3
- c 4.1.4.2.6.1 3
6 p' c E
. E 1
1B __d
g Tsbie B.I.2 Summarization of Procedure Steps Necessary for Iow Pbwer to Full Power Increase ,. m 5 O 8 OC Reactor Power, f 8. Step P Electric I%wer, Reactivity Heat Remont Comments l P P (psig) , T(*F) f t 5.10 At ~40% power hold for 1.5 Allow for gathenng of heat rate data n' rS. f
, While changing reactor power, stay out of Region IV, Tech Spec figure 3.4.1.1-1. Ifin Region IV, reduce power to be in
' Regions 11 or til within 2 hours 5.1I When reactor power stable > Critical on rods, don't Switch to hi speert when clear low FW 34% and below 80% rod line, increase recirculation flow limit (~ 30%), set FCVs on min. l [ shifttecirculation pumps to high until Step 5.16 open before speed change (30% FW is speed control valve cavitation interlock) i 5.13 At ~40 to 45% reactor power, 3 element mode is where RFP speed ( verify level, steam, and feed flow is a function of vessel water level, are stable. Place FW control in steam flow, and FW flow ; 3<lement mode 5.14 At ~45 to 55% reactor power, place 2nd RFFT in service on master level control, place 2nd cire. water pump in service 5.16 When desired flow control line Increase power with Rod pattern fixed, increase power by reached, increase power by recirculation after opening FCVs , increasing recirculation flow with desired rod pattern ! loop controllers in manual reached 5.17 At ~60% power, hold ~ 1.5 hrs. Allow for gathering of heat rate data 4 E ! n to _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . . _ _ , _ _ - . . . _ . . . , . . _ . _ __m, , . . . _ , . . . , . . _ _ . . ._. . , . , _ _ . _ _ _ _ , _ , _ _ _ _ _ _ _ _ . . _ . - , . . , _ _ . . . _ . _ , . .
- 2. Table B.I.2 Summarization of Procedure Steps Necessary for Low Ibwer to Full Power increase
.N N
w Reactor Power, P Step Electric hower, Reactivity Heat Ranoval Comments P P (p ig) T (T) 5.20 As swa as high power set point (HPSP) reached (~70%) demorstrate RWL operability. ,
)
At -80% power 90% core flow Assumed: "ECCS line break alarm;" ali ECCS line break alarms is associated with the " low pressure
- should be cleared; enter sensors in the ECCS actuating I&C, applicable LCOs for any like per TS 3/4.3.3. Table 3.3.3-1.
break alarms not cleared of these These sensors provide " injection conditions permissive" signals to allow LPCI and
?
LPCS to actuate on either low vessel level or on high drywell pressure if pressure is also low. 5.21 At -80% power maintain steady Allow for gathering of heat rate data state for 1.5 hrs. 5.24 At - 100% power hold for ~ 1.5 Allow for gathering of heat rate data hrs. 2 ifs. c b Q 1 b
" a. & c E
E g __;
Z 18 g Table B.I.3 E- --0. tion of Procedure Steps Necessary for Full Power to Imr Power Decrease M. m k e , 9 N 1
& Reactor Power, P 1 3
Step Electric Power, P' P (psig) Reactivity Heat Renoval Comunents l T (F) 6.0 Full power to low power OC1 Rods positions and Loaded turbine decrease P ~ 100% recirculation flow P[ ~ 100% P. T,(p) 6.I Notify system dispatcher before decreasing generator load 6.3 Decrease power by closing FCVs Decrease with recirculation flow _ to h 6.4 Below ~ 14 x 10'lbm/hr FW flow secure I condensate booster, then I condensate pump 6.7 Before reducing core flow < Decrease with recire. Insert rods per SOI 04-1-01-Cl1-2 45% begin inserting rods flow; and rods when
~ 45 %
6.10 At ~45% to S5% reactor power, secure one RFPT 6.12 Before FW decreases to 30% and Decrease with rods after below 80% rod line, switch once switch to low recirculation to low speed and speed open FCVs to maximum. 6.17 At ~20 to 25% rated FW flow, verify stable level, transfer to o_ single element control _
.N T
R m
P- Table B.I.3 S- --htien of Procedure Steps Necessary for Full Ibwer to Low Pbwer Decrease m E 6.19 At 15 to 20% power, remove N steam side of HP FW hesters ' from service 6.20 At ~15 to 20% power transfer FW to startup level contmiler 6.21 At -15 to 20% ga..hn load - (196-261 MWe) shutdown MSRs 6.22 At generatorload ~157 MWe 1.oed demand contml only > 157 verify offload demand MWe; speed demand control below 175 MWe 6.23 Insert IRMs 6.24 Notify system dispatcher generator is ready to be disconnected fmm grid C
~
6.25 Insert rods until 100 to 150 MWe 6.26 Manually trip turbine 6.28 Generator auto trips on reverse Turbine bypass to With no driving power, generator acts power (bypass valves maintain condenser like a motor (reverse power) reactor pressure) I z E i C -- 0 N - % 3 w l
@ Table B.1.4 E - - -i, tion of Procedure Steps Necessary for Rapid Pbwer Reductson f E f C
{ ~ 25 y Reactor Pbwer, P OC {1 g Electric Power, P[ g w Step P (psig) Reactivity Heat Ranoval Connnents T CF) 7.0 Rapid power reduction OC1 P, ~ 100 % P. ~ 100% i ! (P(D) 7.1 Reduce recirculation flow using Take appropnate action ifin fast detent, then insert rods if unallowed power / flow regums further power reduction necessary or if scram occurred then follow 6,0; enter ONEP-05-1-02-I-I in " Reactor Scram" U a ' N _ . . . . _ . ~ . _ _ _ _ . - . _ ...... _ ,. ... ., -. - - _ _ . , _ _ _ - . . . . , - _ , . , , . , - . . , , . . _ . _ . _ . . _ ~ . _ . - . _ . . _ . . _ _ . _ _ - - . . _ - . _ . . . .
1 l Review Procedures Table B.2.1 Precautions, Limitations, and Actions Associated with Procedure 031013 l
$1 ggt Description 2.1 With mode switch in STARTUP, an APRM block occurs at 12% power, scram at 15 % power.
2.2 With mode switch in RUN, APRM rod block if power < 5 % (Procedure #03-1-01 1 Step 2.1.10 says 4 %). I 2.4 Maintain vessel level normal + 32 to 40 inches. 2.5 Cooldown rate S.,80'F/hr. 2.6 Follow Tech Spec Figure 3.4.6-1-1 for vessel materials integrity. 2.8 If desired to remain in hot shutdown, reduce Rx pressure to approximately 400 psig to minimize feedwater (feedwater temperature approximately 100 'F with no feedwater heaters; T, (400 psig) is approximately 450'F). 2.10 If cold shutdown is required, refer to SOI #04-1-01-E12-1 and have shutdown cooling flushed
& ready for service as soon as pres,sure permits.
2.12 Do not run two RWCU pumps in post pump mode at < 200 psig RPV pressure as loss of NPSH may occur. B-13 NUREG/CR-6143 G
1
$ Table B.2.2 Summariantion of Procedure Steps Nc, for Cool down with the MSIVs Open (
E 5_ O < 8 OC y Remeter Power, P, r Electric Power, P Step p (psig) Reactivity Hest Rarmal Comments T (*F) 5.0 Shuklown and Cooldown OC1 Rods and recirculation on low Turbine bypass to MSIVs open P, ~ 12% speed condenser P, = 0 (P) 5.5 If rapid and complete shutdown desired manually scram and refer to ONEP 05-1-02-I-1, Reactor Scram I 5.8 Insert rods in specified order P* ~8% [ to reduce power to 8%, insert
- IRMs 5.10 Ensure SRs met to change mode 5.12 Place mode switch in OC2 STARTUP 5.15 Continue to insert rods OC2 P, ~ 0 5.15 Insert SRMs, verify turbine None (until 5.20) With 0 power, turbine header bypass valves close at 950 pressure decreases psig (pressure setpoint),
continue to ireert rals until all rmis in 5.16 Verify all signoffs for entry l
< into Mode 3, verify SRs met .~
n 9
- - - . _ . _ - . . _ _ _ - - . _ - _ . _ _ - _ _ _ - - - _ _ - _ . _ - - _ . _ _ - _ _ - _ _ _ _ _ _ _ _ _ _ - - _ - - - - -_ _ _ . - ~ - - , -,,--- ~
f Table B.2.2 Summarization of Procedure Steps Necessary for Cool down with the MSIVs Open
? OC
$ Reactor Power, P Electric Power, P' Step p (psig) Reactivity IIcat Removal Comments
. T (*F) 5.17 Place nnie switch in OC3 All rods in None (until 5.20) Decay heat orJy SHUTDOWN when all P=0 control rods fully irtserted P[ = 0 P<Pu T_(p) .
5.20 Initiate and maintain cooldown TBVs on manual Cooldown by lowering
< 80 *F/hr by manually to condenser pressure T p) decreases via opening / closing TBVs controlled E(ashing 5.21 Control level with ITV to '4 Secure SJAEs and use y mechanical pump for condenser vacuum 5.24.1 At a 500 psig secure the FW pumps offline running RFPT 5.24.2 Check that only I Level control still with FW condensate booster and I injection condensate pump running Note: If no recirculation per TS RHR SDC only if p < 135 3.4.9.1, one loop of SDC psig must be in service within 2 hrs. of p < 135 psig Caution: Do not secure one mode of heat removal before y
y establishing another 3,
$ 5.25 Maintain TBVs in operation From TVBs to RHR SDC per pmcedure 501- I h
- c for cooldown as long as possible; when necessary RHR SDC 04-1-01-E12-1
{g, b place RHR SDC in operation E O Pa = - _ _ -
2 I c Table B.2.2 Sessmarization of Premdure Steps Nw_-y for Cool down with the MSIVs Open . E 0 l,
$ OC y Reactor Power, P, g Electric Power, P g " Step p (psig) Reactivity Heat Renovel Comuments R TM 5.26 At 200 psig secure i RWCU pump if both are running l
5.27 At 100 psig transfer RWCU to RWCU blowdown to pre-pump rnode condenser or radweste, can take over level control from FW 5.29 Shut the TBVs, set steam OC3 RHRSDC demand setpoint 100 psig > P, = 0 , reactor pressure P, = 0 p < 135 psig ' " T ,(p) ' 4 e 5.30 Break condenser vacuum if desired 4 - Shut down mech vacuum pump
- Open condenser vacuum breakers
- Shut down gland seal steam
- Shut down cire. water, if desired ;
5.3I When T < 190*F, open OC4 Vent primary to atum,Jee F001, open F002, and close P, = 0 F006 P=0 p = 0 psig T < 190*F g
~
subcooled i 9 To prevent thermal stratification. c maintain recirculation on low speed E w t
._m______ _ _ _ _ _ _ _ . _ . _ _ _ . . _ . _. . . _ _ . . . __. , ,
f Table B.2.2 Sumsnarization of Procedure Steps Necessary for Cool down with the MSIVs Open P 7 OC [ Reactor Power, P, Electric Power, P Step p (psig) Reactivity Heat Reneral Conuments T(D - If recirculation gishutdown cooling Inadequate decay heat removal lost, go to procedere ONEP 05 proceduse (ONEP 05-1-02-111-0 2-111-1 ' 1) (off normal event pi4 ) - 5.32 Cool down to and maintain OC4 120-130*F P, = 0 P=0 P'= 0 psig 5.33 Secure condensate /FW system Level control with RWCU txt 6 5.34 Reject water with RWCU to Reject to counter CRD maintain normal level hydraulic injection 5.35 While maintaining COLD SHUTDOWN and as necessary to maintain desired reactor coolant temperature operate RHR in SDC per SOI 04-1-01-E12-1 Z M m a e m 9 1 i } e a
2 2e C
$ Table B.2.3 Summarization of Procedure Steps Necessary for Cool down with the MSIVs Closed 3{
rZ x Reactor Power, P l li Electric Power, P' 2 Step p (psig) Reactivity IIeat Renoval Comments 4 TCO 6.0 Shutdown and Cooldown with OC1 Rods and recirculation on low Turbine bypass to This section assumes MSIVs MSIVs cleed P, - 12% speed condenser (if initially open. If MSIVs are P, = 0 MSIVs open) closed perform only applicable P=P m steps 4 T_(p) 6.5 Check for availability of operation (with MSIVs chud) of:
~ - RCIC
=
- RWCU (tsvel control)
-SRVs
-SP
- SSW 6.6 If rapid and complete shutdown desird, scram reactor and follow ONEP 05-I-02-1-1 " Reactor Scram
- i 6.9 Insert rats and reduce power OC2 to ~ 8 %, insert IRMs, nule P,-8%
switch to STARTUP 6.15.9 Insert all nxis, verify OC2 signoffs for entry to OC 3 P,~ 0% 6.17 Place anale switen in OC3
< SHUTDOWN when ali nxis P* ~0%
inserted O
?
2 N
,I Table B.2.3 Summarization of Procedure Steps Necessary for Cool down with the MSIVs Closed
[ OC w Reactor Power, P, Electric Power, P* Step p (psig) Reactivity IIeat Renoval , Comments T (T) In following it is assumed RCIC MSIVs still open (close in operable; if not, use HPCS for 6.25/26) makeup and cycle reliefs (SRVs) 6.23 Start up RCIC per 50104 Turbine bypass if 01-E51-1 p > 950 psig and RCIC 6.24 When level and pressure stable and being maintained with RCIC, shut down tp running RFPT and secure FW G and condensate. 6.25 Close Inboard MSIVs RCIC only Close in board MSIVs 6.26 When pressure downstream of RCIC All MSIVs closed Inboard MSIVs - 0, close outboard MSIVs 6.29 As necessary use RWCU to assist in level control 6.32 When p < 135 psig place OC3 RCIC and RHR RHR in SDC mode per SOI p < 135 psig 04-1-01-E12-1 T ,(p) 6.34 Before 75 psig shutdown RHR RCIC g8 j z 1 l c g 6.35 At 60 psig check RCIC auto Q Q isolation 7 s n l I w
"2
N Table B.2.3 Summarization of Pmceduit Steps Necessary for Cool down with the MSIVs Cleoed f O a oc F
$ Reactor Power, P, [
Electric Power, P
- g Step p (psig) Reactivity Heat Resnoval Canunents T (*F) 6.36 When T < 190* vent t.y OC4 RHR Vent the primary I opening F001 and F002 and closing P, = 0 F005 P=0 p = 0 psig T < 190*F subcooled Maintain recirculation low speed. If Inadequate decay heet removal forced circulation o_r_SDC lost, Go procedure to ONEP 05-1-02-111-1 .
tic 6.37 Cooldown to and maintain OC4 RHR 8 120-130"F P, = 0 P=0 p = 0 psig T ~ 120*F subcooled 6.39 Maintain level with RWCU 1 1 r a N
i l Review Procedures Table B.3.1 Precautions and Limitations Associated with Procedure 031-015 Sita Description 2.19 Recirculation on low speed. Go to ONEP 05-1-02-111-1 (* Inadequate Decay Heat Removal *) if recirculation or SDC lost. 2.20 Limit cooldown s; 100* AF/hr. 2.21 Adhere to pressure and temperatur; limits per Tech Spec Figure 3.4.6.1-1. , 2.22 Vessel temperature > 70*F when studs tensioned. i i i I B-21 NUREG/CR-6143
i i Z se g Table B.3.2 Summarization of Procedure Steps Necessary for Plant Cool down and Entry into OC 5 4, o I Q oc
& Reactor Power, P ylll l,
[ Electric Power, P[ Step p (psig) Reactivity Heat Removal Comments T (M i 5.0 Cooldown & entry to mode 5 OC3 P, - O P, = 0 l T > 200*F P,.,(T) 5.1 Cooldown with TBVs until pressure TBVs to s 135 psig for SDC interlock for SDC clears condenser i 5.2 Place SDC A or B in operation (refer to TS 3.5.1 and 3.6.3.2) to r j $ 5.3 Remove TBVs from service RHR in SDC 5.4 Fast close inboard MSIVs Fast closure required to support local leak rate test (LLRT) ' i 5.5 Let pressure downstream ofinboard Head spray to cooldown head for ! MSIVs drop to 0, then fast close outboard detensioning _ MSIVs, initiate head spray i.f. desired but don't exceed 100*F/hr cooldown 5.7 At 200 psig transfer RWCU to blowslown , mode i 5.8 With condensate and startup level ~230 on shutdown range controller raise level > flange 5.9 Continue cooldown to 80 to 100*F RHR on SDC , B- 5.10 At 60 psig verify RCIC auto isolates OC4 9 4 5.12 Open HFTS transfer tube closure hatch Connect spent fuel poolin aux building to upper pool in containment I E N 1 . . _ . .. _ . . , . . - _ _ . - . . _ . _ _ _ - . - - , . - - . . - . _ _ _ . - _ , . . . _ . _ . _ . . _ _ . _ , _ . . . . - _ _ . . _ _ ~ . _ . _ , _ _ _ _ .-_. ~ _ .- - .. ~ -
,SL Table 0.3.2 Sinnmarization of Pmcedure Steps Necessary for Plant Cool down and Entry into OC 5 ?
a OC N Reactor Power, P, Electric Power, P Step p (psig) Reactivity Heat Removal Comments T (D 5.14 Open containmerit air lods 5.17 Containment and drywell equipment hatches removed 5.20 Install upper pool to reactor upper cavity Isolate upper cavity from upper pool gate and inflate gate seal to allow draining upper cavity 5.21 Drain upper cavity to RWST Refueling water storage tank (RWST) 5.23 Drain RWST to Hotwell for cleanup in prepration for reflooding upper pool if g, required w 5.24 Remove drywell head 5.25 Lower vessel level to I ft or move below flange and verify head spray not in service 5.26 Remove connections to RPV head a y 5.29 Detension RPV head OC5 5.30 Remove RPV head 5.31 Throttle recirculation to reduce water ripple 5.32 Establish containment cleanup mode ventilation. May renave airlock doors and y c equipment hatches 5.
- I h 5.33 Remove RPV steara dryer y n 9 N 5.34 Drain level to below steam lines ~90* on shutdown range p'
& c Ew 3
_ _ _ _ _ _ _ _ - - _ - _ . _ _ - - - _ _ ._. . .- -- .- ~ , - -
t
- s 7 Table B.3.2 Suramarization of Procedure Steps Necessary for Plant Cool down and Entry into OC 5 3, b I O
6 Reactor Power, P, 1 { Electrk. P1wer, P, g Step 9 4 tig) Reactivity Heat Rernoval Comments T O F) 5.35 Install steam line plugs Can't use SRVs with plugs installed 5.37 Reflood reactor cavity from RWST. Lift 5.23 Dramed RWST! steam separator as reactor cavity fills 5.39 Deflate gate seals and remove upper pool to reactor upper cavity gate 5.42 Commence required in-vessel work (e.g., SDC with RHR fuel movement) 1 l I
~
1 y 2 tJ
k Tr.ble D.3.3 Summariation of nw;i . Steps PLi or Reactor f Pressure Venet Renssembly and Entry ines OC 4
;P i 3
OC l
" Reactor Pbwer, P Electric Pbwer, P'
- i Step p (psig) Reactivity Heat Removal Comments ,
T (*F) L 6.0 Pressure vessel reassembly OC5 RHR or SDC ' l 6.5 Upper pool to reactor cavity gate installed and seal inflated t 6.7 Drain upper reactor cavity to RWST. Iower level to 1 It. below flange 6.8 Install steam separator 6.9 Lower vessel level below main steam lines
, 6.10 Deflate and remove main steam line plugs ~
b 6.12 Install steam dryer 6.13 Install RPV head l 6.15 Tension RPV head studs . 6.17 Place mode switch in SHUTDOWN OC4 6.21 Commence RPV heatup in preparation for SDC " throttle SDC to heat up 03-1-01-6 6.24 Install drywell head 6.26 Reflood upper reactor cavity 6.27 Deflate gate seals and remove upper pool to reactor upper cavity gate C ~- W
- ]
8 .
, 1 e 3 i,
I m .__.__.________m . _ _ . ___m_m. _ _ _ . _ _ _ . _ _ _ . _ . _ _. _ _ _ _ _ _ , . - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . . - _ _
r Review Procedures l Table B.4.1 Precautions, Limitations, and Actions Associated with Procedure 03-1-01 1 Sigg Description 2.1.4 Period 2.50 Sec 2.1.9 In STARTUP an APRM Rod Block occurs at 12 % Power and an APRM Scram at 15 % Power. . 2.1.10 In RUN RPRM Rod Block it < 4% Power. 2.1.11 No Rod withdrawal unless TBVs fully closed and power > low setpoint of RCIIs (rod control and information system). 2.2.3 Maintain heatup to 5.80* F to prevent exceeding Tech Spec 3.4.6.1 limits 2.10.1 &2 No gland seal steam to turbine if shaft not turning. Turbine on turning gear for 24 hour if performing a cold startup and 1.5 hrs for a hot startup if turbine not off turning gear during shutdown. 2.10.11 At turbine loads < 50%, condenser vacuum > 3.63 psia since little steam cooling occurs on the last stage of the turbine under < 50% load. t r k e l NUREG/CR-6143 B-26
Table B.4.2 Summarization of the Proceduit Steps Necessary for Rescior Startup w Remetor I%wer, P Electric Power, P * , Step P (psig) Remetivity liest Removal Comments T (*F) 5.0 Reactor Startup OC4 or 3 P, = decay Only in OC3 if T>2000 per Step 5.4 heat P = 0 p and T per 5*4 . 5.1 Verify recirculation in operation on low Rods positions per mode Per prerequisite If unit has been shutdown 120 days, speed Switch in Shutdown on 3.3.3. RHR can be decay heat in low, and in preparation REFUEL out of shutdown for startup RHR SDC mey be stopped cooling mode, thus & RHR lined up for LP I. This is no heat removal OK since (exces for CRD 1. heatup is slow (cunn m injection RWCU 05-1-02-III-1). tn letdown) 2. Rx will be heated up anyny.
@ 3. RHR lined up for LPCI See Steo 5.15.
5.2 Verify CRD hydrauhe system in operation 54-66 gpm 53 Verify level 32 -> 40 being main-tained by RWCU letdown to main cond or radwaste (letdown to match CRD injection) 5.4 Ifinboard MSIVs ope, or T 11907 T 1190*F If T <200*F in OC3 venfy: cicse F001 & F002 open P = P,(T) F005 Ifinboard N51Vs closed and T < T < 190* in OC 4 190*F verify: open F001 & F002 p=0 Z closed F005 a C 5-N E 9 5 6 Verify SFMs IRMs fullin IRMs full N Q in IRMs range I
& 6 g 5.8 Verify all OP8:RABLE rods in g w
I __ _ _ . _ ._. . _ _ , _ - . _. . . _ ~.__ _ - . . . . - , ._ __. _. _ _
Z c Table B.4.2 Sumnuwization of the Prar=e-e Steps Nar====ry for R.=cear % E - O N OC
$ Reacter Power, P g Electric Power, P ,
- Step P(psin) Reactnity Heat Reesevel Ceauseets T G) 5.15 Verify RHR A,B,C in Standby (or No shutdown cooling; see commers in mode not requiring manual re- associated with Step 5.1.
alignment for LPCI) 5.20 Verify chemistry 5.23 Place mode switch in STARTUP OC2 P = decay 13 Table 1.2 allows 'any temp
- for heat OC2. Normal cold startup posses P, = 0 p and T per from OC4 to OC2 wahout any time in 5.4 OC3 Heatup on nuclear heat; not pump heat
, as for PWR 5.29 Pull I rod or I barg 4
i SM3 Withdraw rods until Rx crtical 5.38 Fully withdraw SRMs when IRMs on 1 range 3 1 i e i b 5 a tJ l i
. , - , , , - - , - - - . . , , - - _ , . - , . . - - , - , , , . _ . - , . . . ~ . _ ~ _ _ _ _ - __ . . _ - , . - . _ _ - , -, --- - _- -
2. u Table B.4.3 Summarization of the Procedure Steps pry for Unit Hestup E a . N N [ l Renctor Pbwer, P ! l Electnc Power, P' Step P (psig) Reactivity Heat Removal CW T O) 1 T 6.0 Unit Heatup 6.1 Establish Main Cond Vacuum , - If MSIVs closed, at - 190'F: open F005, close F001 & F002 P = P"'(T) once
- verify main turbine & RFPTs on F001 & F002
- turning gear closed
, - lineup seal steam condensate to main turbine & RElrrs 2
- draw vacuum in main cond using y mech vacuum pumps to maintain c 20 to 26* lig
- place cond demin's in service i
y 2 a C S. M $ , S m n k L h 0 $
._m. _____ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . . , _ , . _ _ . - . _ . ,m _ - . , ., m.- __ - . .. - __.,, -. . _ - - _ _ _ . _ , . . - . . , . ..,_m. . . , , , . . . . . - . - . , . . -
Z > c: Table B.4.3 Summarization of the I%cedure Steps Necessary for Unit Hestup p .a.. a x Reactor Power, P [g Electric Power, P, Step P (psig) Reactivity Heat Removal Comments 5 T C F) 6.2 Rx lieatup and Pressurization
- If bypass s_t_og valves closed, open them
- verify chemistry
- verify I cond pump in oper if ,
pump in oper & if p> 400 psi one RFIT should elso be in oper.
- ensure at least 2 CCW & TBCW HYs in service , - establish FW level contml with & startup ievel controller
- rnanually adjust then place in auto at 36" e increase to 40* before opening MSIVs to compensate for level decrease
-if MSIVs closed:
- equalize steam p across MSIVs
= open MSIVs at desired RX pressure
- at ~ 60 psig
- place RCIC in standby
* <iop letdown when no lon ger needed for level control b
a N
, ._ =__
- 2. Table B.4.3 Sununarization of the Procedure Steps Necessary for Unit Heatup
..N u E OC w Reactor Power, P Electric lbwer, P,
- Step P(psig) Reactivity lleat Removal Comments T(*F) 6.2 Rx Heatup and Pressurization (Contim:ed)
- At ~ 100 psig transfer RWCU to post pump made with I pump &
filter m service
- At ~200 psig place 2nd RWCU fi er in service
- At ~400 psig pull rods as necessary to obtain at least 10%
bypass valve opening (for FW pump start)
- Place 1 RFP in se:vice and W insuie 2nd RFP is ready for w service -
- At ~500 to 800 psig a place SJAE in service e depress 11PCS hi level text hurt -: b level 8 (+55*) H1 annunciator ciered i
- At -950 psig when, turb stm press demand has been raised to 950 peig, stop
- Raise P setpoint and allow bypass valves to open as P, merease
- Transfer to RUN as follows: Rx pressure higher (~950 psig)
= verify all mode change conds met OC2 P ~ 4% Turbine bypass to Ts Table 1.2 says OCl can have
- Withdraw rods until APRM downs- P = 0' P > 950 main cond. 'any temperature
- indicator lights off(~4% power) T = T*(P) t
- Verify main stm pressure > 850 psig OCl P* = 0 p > Rods positions to hold Turbine bypass to x
$- - Transfer mode switch to RUN 950 critical at desired P main cond. Q x - withdraw IRMs & place on range 3 T=T "(P) (overcome dopplerf W m 8
- continue rods withdrawal for p' 9 to give 5-10% total steam flow *?
n 8 5 E-zw a
=
_ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _____ _ _ _ _ _ _ _ _ . . - . , . . , . . , - . ._....,,..m. . . , - . . _ . , _ , - - - .--,.._,..--.-m _-,_m.
, Z Table B.4.4 Summariaation of the Procedure Steps ply for Turbine Startup and Generator S,A *
- C E OC o
8 Reactor Pbwer, P
$ Electric Power, P,'
g Step P(psig) Reactivity Heat Removal Commsents g TCO E j 7.0 Turbme Startup + Generator OCl P 5-> 10% Cntical at desired power Turbine bypass to on FW level control Synchronization P, = 0' P ~ 950 with rods main cond. T = T,(P) 7.1 Turbine startup ICVs still closed , l - Reset turbine trip solenoids & begin TSV warming, open HP and LP TSVs
- Place 2nd stage heating steam for MSR into service j - Roll turbine to 400 rpm as follows: ;
- verify on turbine gear Limitation 2.10.2 t
! ip sufficiently long l M
- verify sufficient Rx steam to
! roll to 180 rpm l
- set ETTC sp demand to 400 rpm Turbine bypass + Roll the turbine (opens TCVs) unloaded turbine ;
- verify vibration OK st 400 rpm j
. -increase turbine to 180 rpm as Turbine totaled speed follows:
- set ETTC sp demand to 1800 Ensure adequate steam for (TCVs open) + generator sync & rnin loading
- verify 1800 rpm
- verify TBVs at least 20% open i
I n i 9
-._...~,....m . . - . . - -._-- -, , - . . ~ - - . . . - . ~ . , . , . _ - . , - - , - - . - - - . . _ . . - . . . , , . . _ . . , , . . - .- . . . . - - . - - - - - - - , . - - - - - -
I p Table B.4.4 Summarization of the Procedure Steps Necessary for Turbine Startup and Generator Synchronization l { Reactor Power, P w Electric Power, P, Step P (psig) Reactivity Heat Rarnoval Comments T (*F) 7.2 Generator Synchromzation Voltage regulator m AUTO
- ensure motor disconnect 15230 whenever generator Il turgid, ready to be closed except if regulator fails (regulates
- For breakers J5228 + J5231: ternunal voltage by varying exiter a verify switchyard lineup is hence emf) J5230 ties gen to such that 228 + 232 can be switchyard (FSAR Fig. 8.1-1) opened without losing loads; 15228 + 232 tie gen to switchyard open 228 + 232 (FSAR Fig 8.1-1)
- close disconnect 35230
- place isophase bus cooling in oper.
- notify load dispatcher ready to sync to grid
- verify generator > 1710 rpm +
close generator field breaker tn - adjust generator output to 22Kv 6
* - close breaker J5228 or 35232
- depress ETTC sp deriind to 1805 rpm
- watch syr.chroscope + decrease Generator freq slightly above grid; speed slowly until synchroscope ready to sync is slowly rotatmg in clockwise (fast) direction Generator sync'd to grid; at any
- At 12 o' clock on synchroscope, Turbine bypass & fixed synchroscope position, gen.
close J5232 (or J5228) unloaded turbine & grid frecuency are equal; at 12 [ depending on which closed o' clock positum, in addition to earlier) f uencies being equal, in each of
- Increase gen load immediately 1 P - 10% 3p induced emf is equal and (by increasing spced demand of P L 75 to 150 opposite (180* out of phase) with EHC) to >75 h1w but i150 htw htw line voltages and hence generator
- Establish 1st stage htSR heating P > 950 T = is n__ot_ loaded.
stea m T"(P)
- Raise gen output to 175 htw with Ensure - 175 h1we at least EHC demand (~ l812 rpm regardless of load demand demand) x Z - Transfer from sneed demand HP FW Htr steam extraction lines y C control to load demand control have isolation valves that are --
E - Do not exceed 34% power in the opened to place HPFW Htrs in I
@ procedure P* 124% rated service O - Start 2nd cond & Booster pump 5' $ - hiaintain 1812 rpm 175 Afwe LP FW Htr steam extraction lines 8.
g - Place HP FW Ltrs in service probably have only check valves g w
?
Review Procedures Table B.5.1 ! Symptoms Which Require Use of Procedure 05-1-02-111-1 , Sigg Description l 2.2 Malfunction of RHR or SSW component associated with SDC mode of RHR. ! 2.3 12ss than adequate RHR SDC flow. 2.4 - Uncontrollable increase in reactor coolant temperature. 2.5 Steaming from head vents even though reactor coolant temperature indicates < 212 'F. ! 2.6 RPV pressurization in OC4, Cold shutdown. 2.7 Loss of ADHRS flow or loss of PSW to ADHRS. l t I Table B.5.2 r Immediate Operator Actions ; Sit 2 Descriotion 4.1 Check reactor pressure and temperature. v 4.2 Check spent fuel pool temperature. ; 4.3 Ensure redundant loop available. 4.4 Increase frequency of monitoring temperature and reactor pressure. i i e t l l i h' NUREG/CR-6143 B-34 f
5 { 9 Table B.5.3 Summarization of Steps Necessary to Restore Decay Heat Removal When Fuel is in the Vessel and the Unit is in OC 4
'g OC E Reactor Power. P tJ Electric Power, P' Step p (pdg) Reactivity IIcat Removal Comments T (*F) 5.0 Subsequent Operator Actions if unabic to restore decay heat removal prior to reaching ADilRS suction design pressure is 80 psig OC 3, isolate ADliRS (close F066A F410, and F424) 5.1 Fuel in vessel OC4 5.1.I If in-service RilR loop in SDC lost, place redundant OC4 RIIR in SDC (backup lonp)
- Time to boilofr curves attached to this loop in operation per Sol 04-1-01-E12-1 or place or ADilRS. recirculation on pracedure; also minimum core flows ADiiRS in operation per same procedure low speed provided in attachment 5.12 If forced recirculation lost. raise level to 82* to RHR in SDC, natural Core water hotter than downcomer water promote natural circulation, estempt to regain circulation due to loss of circulation.
recirculation. If RIIR SDC also lost, operate head spray 5.1.3 If RilR SDC and ADHRS completely lost to h - Increase RWCU reject to max and use CRD all RWCU provides some heat removal. and condensate for makeup only enough if unit has been sh.stdown for a long time, RWCU max -360 gpm-
. Use Attachment I to estimate time to boil With vent to atmosphere. boil at 212T
- If adequate cooling cannot be maintained or restarted in acceptable amount of time: None
+ Initiate SP cooling SOI O4-1-01-E12-1
*Close FOOI, F002, and F005 Isolate all vent paths z i?
c 5.
- n a m 4 9
o *?
- = F>
& b 5 $
y is Tcbie D.5.3 Summarization of Steps Necessary b Restore Decay IIeat RemorJ M1xn Fuel is in the Vessel and the Unit is in OC 4 { e oc a 0 Reactor Power, P i [ Electric Power, P[ { g Step p (Psa) Reactivity liest Removal Comunants g w T (F) E 5.1.3 (Continued)
*Oose MSIVs
*Close RCIC steam line isolation valves
*Open/ shut SRVs so that 2 SRVs are Use relief / manual mode to open 2 SRVs UPen Steam lines rated for full water lesd up to
+1ncrease RPV water level MSIVs (using any available injection system) to 101 to 129' to flow through open SRVs to SP SOI 04-141-E12-1 tc
- Start the LPCS or LPCI with l
y suction from SP l l +1ncrease LPCSILPCI to maximum. LPC1/LPCS injection, water j If RPV pressure does not stabilize > out SRVs (MSIVs closext) 55 psig, then start additional LPCS/LPCI pumps until p > 55 psig. If RPV > 202 psig open another SRV. Maintain cool down < 100
*F/hr by tnrottling flow of LPCS/LPCI ifnecessary
- Control SP temp to maintain RPV Don't go below 70 *F with head bolts temp >70 *F tensioned
*Go to cold shutdown per procedure 10103-1-01-3
- Plant Shutdown
- t b
a N
t l g Toble B.5.4 Summarization of Steps Necessary to Restore Decoy liest Removal When Fuel is in the Vessel and the RPV Head is Off , V
}J m OC
! E Reactor Power, P N Electric Power, P' Step P (psig) Reactivity Heat Removal C- A T CF) 5.2 Fuel in vessel, RPV head removed 5.2.1 With upper pools fil:ed if upper reactor cavity filial and
- Notify refueling crew gate to upper containment pool and
- Maximize fuel pool cooling if fuel transfer tube open to spent necessary fuel pool, then fuel pool cooling
- Re-establish SDC or ADHRS ASAP cools pools and vessel 5.2.2 With upper pools n_ot filled Cannot use fuel pool cooling to
- Contact personnel if any on refueling cool vessel floor
- Raise level i - Re-establish SDC or ADHRS ASAP 5.2.3 If SDC & ADHRS totally lost, increase RWCU maximum ~360 gpm RWCU blowdown to maximum and increase makeup with CRD hydraulic and condenste; if inadequate to go 5.3 o
a C 1 y m I 9 ? 9 l
- n 5
e
g Tchte B.5.5 Summarization of Steps Necessary to Restore Decay IIcat Removal When Fuel is in the Containment or Spent Fuel Pools E 9 OC { m h Reactor Power, P 6 Dectric Power, P' 8. 2 step p (psig) T ( F) Reactivity IIcat Removal Comments l 5.3 Decay heat removal for fuel in containment See comment for 5.2.1. 2 or spent fuel pools 5.3.1 If in-service loop of fuel pool cooling lost, place redundant equipment in operation 5.3.2 If fuel pool cooling completely lost align pool cooling to RilR 5.3.3 If fuel pool cooling and R11R lost. inject with fire water to 2
.N a
N
,, - - - - .., . - ,_ _ - .-_ __ _~ - - _ . . -. - -
Appendix C. Overview of Grand Gulf Power Plant This section is a brief summary of the technical aspects 3. Hot Shutdown Shutdown of the Grand Gulf power plant noted in our initial revi'e w > 200 Degrees F of the referenced literature which are of special interest for the off-power risk study. 4. Cold Shutdown Shutdown s 200 Degrees F The following literature was reviewed:
- 5. Refueling Shutdown or Refuel (1) The NUREG 1150 PRA dealing with Grand s 140 degrees F Gulf at full power [USNRC,1989]
Five conditions are specified: Power Operation, Startup, (2) The Grand Gulf Updated Final Safety Hot Shutdown, Cold Shutdown, and Refueling. No Analysis Report (FSAR) [SERI,1992] condition on K,is specified for these conditions in contrast to the case for typical PWR tech specs. This is (3) The Grand Gulf Technical Specifications because BWRs use rodded cores with no cherrical shim, [USNRC 1984] and the 1 % shutdown margin can be maintained by rods alone with the highest single worth rod withdrawn (4) Numerous Grand Gulf Procedures, as [Section 4.3.2.4.1 of Grand gulf, UFSAR]. Below Hot presented in Appendix B Zero Power, PWRs must borate to maintain shutdown margin and their tech specs limit K in each mode (5) Class notebooks from the BWR/6 (operational condition). The table [oes specify the mode Fundamentals Course m Tulsa [ General switch position which places limitations on rod positions Electric,1981} in each condition as the mode switch activates various rod blocks in its various positions. Section 7 of the (6) The textbook Nuclear Enercy Conversion [El- UFSAR discusses the limitations imposed by the Mode Wakil,1971) Switch Position. In the Refueling position, only one control rod can be withdrawn (without special bypass). (7) The NRC's BWR Fundamentals Manual in the Shutdown position, all rods are in. The control [USNRC,1983] rod circuitry is in a scram state for ten seconds. In the Startup position, a rod block is set at 12% power, and a (8) The GE General Description of the BWR/6 scram is set at 15 % power. In the run position, power [ General Electne,1980) can be up to 100% , but the full power protective scrams, and rod position / pattern limits, are present. The tech (9) Various sources ofinformation on nuclear specs specify reactor coolant temperature limits in each , power plant components. OC, but do not specify pressure. The system is saturated (until it is vented at very low temperatures-typically 190 degrees F) and thus there is a unique The Operational Conditions (OCs) for Grand Gulf are pressure at each temperature. Other portions of the tech defined in Table 1.2 of the Technical Specifications. At specs limit pressure to the ASME code allowable some plants, these are called operational modes. The (design + 10 %) and specify temperature / pressure limits OCs as defined in the technical specifications are as for thermal stress and NDTT considerations in the I U *" vessel. The refueling OC does not cover refueling , operations. The refueling condition applies for fuel ir, the vessel with the head studs less than fully tensioned. Condition Mode Switch Position and Refueling operations involving fuel transfer to and from , Aserace Reactor Coolant TemE- the vessel are subject to tech spec section 3/4.9
' Refueling Operations".
Any Temperature Grand Gulf, like all latter-day BWR designs, is a recirculation controlled plant with turbine following (turbine leading is unstable). At steady state the
- 2. Startup Startup/ Hot Standby turbine / generator rotor rotates at 1800 rpm. Load Any temperature changes within the response capability of the plant are Vol. 2, Part 2 C-1 NUREG/CR-6143
Overview of Plant accommodated as follows. If it is desired to increase setpoint. The previous increase (decrease) in recire (decrease) the electrical load on the generator, the torque results in lowering (raising) the vessel downcomer water on the turbine shaft must be increased (decreased) to level. The level is restored to its normal range by increase the in**antaneous speed of the rotor and move it increasing (decreasing) feedwater flow, at the new steady to a new position with respect to the stator windings state the feedwater flow equals the steam flow, where the torque from the magnetic field equals the driving torque. In a synchronous electromagnetic ne following discussion focuses on those systems machine (altemator) such as an AC generator, with a normally involved in changing operational conditions, change in driving torque the rotor changes its such as: turbine and bypass, recire, and shutdown instantaneous speed and establishes a new position with cooling. These are the systems which the operations respect to the str. tor so as to produce an equal opposing personnel will be manipulating during changes in torque. Once this equality is established, the rotor operational condition, and they are those which will first j regains its initial rotational speed. The stability of the drive the course of any accident acenario. The additional speed control is enhanced by the grid ' flywheel' effect systems - such as LPCI, HPCS, SP Cooling - are already which provides synchronizing power to hold the well understood as a result of the NUREG 4550 study. I generator output frequency at the grid value. Thus, a The primary effects on these systems are out-of-service change in electrical load does not change shaft speed, so conditions resulting from operational constraints (e.g., long as the control range of the generator (90 electrical switching RHR trains A or B from LPCI to Shutdown degree shift between rotor position and stator field) is not Cooling) or resulting from down-for-maintenance as exceeded. The turbine drives the rotor so as to change allowed by tech specs. the phase angle between grid voltage and generator terminal voltage which changes the power delivered to Since the BWR is operated at saturated conditions, : the grid from the generator. The turbine demand is in special attention is paid to providing enough Net Positive l response to the load desired on the grid, not in response Suction Head Available (NPSHA) to meet the Net to speed changes. Speed controllers on the turbine are Positive Suction Head Required (NPSHR) for the recirc used in startup (no load), for protection against and RHR pumps to prevent cavitation. When the recirc overspeed if the control range of the generator is pumps are at rated speed (1800 rpm) adequate NPSHA is exceeded (e.g., loss of load), and for contributing to grid provided by the amount of subcooling due to subcooled frequency stability by being set at 1800 rpm for 60 feedwater (420 degrees F) mixing with saturated cycle. [This discussion on speed stability is specific to a recirculating water from the core exit (549 degrees F) synchronous machine. For a DC generator or an with a recire ratio -core exit recire flow to feedwater (or induction motor, speed changes with load.] The change steam) flow - of 7:1. The recirc suction water is 20 in driving torque is provided by a change in recirculation Btu /lbm subcooled (about 16 degrees F subcooled) at flow with the turbine following. The load demand signal rated conditions. The recirc pumps are tripped to low is sensed by the turbine Electro-Hydraulic Controller speed if the subcooling margin (TgT ) is less than (EHC) which interacts with recirculation flow control 8 degrees F. On low speed, the recirc pumps are at system to increase (decrease) recirculation flow. 25 % speed and adequate NPSHA is provided by the (Currently, at Grand Gulf, this automatic load following static head of water in the downcomer. This information is not used and recirculation is manually controlled.) on recire NPSHA was taken from Section 5 of the his increase (decrease) in recire flow decreases UFSAR. Figure 5.4-4 of the FSAR indicates the (increases) the void fraction of the water exiting the core NPSHR for the recire pumps on high speed is about 100 and via negative void fraction feedback the reactor ft. Since head is proportional to pump speed squared, thermal power increases (decreases). The steam header the NPSHR on low speed should be about 1/16 of 100, i pressure increases (decreases) in response to the or about 6 ft (rough estimate neglecting actual system increased (decreased) steaming from the core and the resistance and pump suction details). Since the vessel turbine pressure controller opens (closes) the turbine contains 570 in. of water in normal operation [ Figure control valves to restore header pressure as much as 5.3-2 of Grand Gulf, UFSAR], it is seen that the static gmssible (the turbine follows the boiler). The increased head alone prevents cavitation. , (decreased) steam flow to the turbine increases (decreases) the driving torque on the rotor thereby The RHR pumps have a NPSHR of 2 feet, and they are
'instan'.aneously' (response time determined by rotational located at an elevation of 96 ft Mean Sea Level (MSL).
inenia of the shaft) shifting the rotor to provide the With saturated water in the suppression pool at its desired power output. Turbine header pressure is at its minimum level of 107.5 ft, the NPSHA to the RHR l NUREG/CR-6143 C-2 Vol. 2, Part 2 I l
3 i Overview of Plant pumps is 5.8 ft coder worst case flow loss conditions. procedure which instructs operators to ensure natural his information is from Section 5 of the UFSAR. Since recirculation by controlling the water level, the vessel is at an elevation above the suppression pool, there is ample NPSHA to the RHR pumps in the The following information is from the UFSAR and the shutdown cooling mode due to static head alone. BWR/6 Fundamentals Manual. The recire system in BWR/5 and 6 designs is flow valve controlled rather than Certain options for energy removal which cool liquid in variable pump speed controlled as in earlier designs, the downcomer region (such as RHR/SDC) require that The induction motors for the recirc pumps have two the measured level, measured in the downcomer, be speeds: 1800 rpm via a 60 hz line source and 450 rpm sufficiently high for adequate recirculation between the via a 15 hz low frequency motor-generator source. The core and downcomer regions. This required measured low speed is used during off-power conditions. The levelis significantly higher than the top of the core. pumps are not canned, they use a dual mechanical shaft The recirculation system is normally kept in operation in seal design with controlled leakage, and cooling with the the off power conditions to reduce thermal stratification Component Cooling Water (CCW) system. The CCW (from the Plant Shutdown Procedure. See Appendix B also cools the lube oil and the air to the motor stator of this report). However, it is not required to be in windings. The pump / motors have sufficient inertia to operation at shutdown, as long as level in the core region provide slow coastdown to preserve thermal margin until is adequate, natural recirculation due to the difference in the reactor can be tripped. A seized recire pump density between downcomer and core fluid is sufficient. accident is a design basis accident [Section 15 of Grand The actual level of concern is the level in the core region Gulf, UFSAR]. The high speed power circuit breakers which must be above the steam separator tumaround incorporate an Anticipated Transient Without Scram point to allow core water to flow back hato the (ATWS) trip coil to reduce power given an ATWS. The downcomer. recire flow control valves (FCV) are ball valves, hydraulically operated, with a linear flow control The actual core level is different from the measured level response (C, versus position). The recire pumps are in the downcomer due to the following reasons: The always started on high speed with the FCVs at mininum core fluid is a two phase mixture (at power). If the position in order to lift thejournals off the bearing faces, recirculation pumps are on, they raise the core level with Evidently the bearing oil pump is gear driven off the respect to the downcomer level. The level measurements recire pump shaft and requires high speed to develop cre based on a standard delta p sensor which measures enough head to inject oil into the bearing and ' lift' the the pressure difference between the head of water in the shaft. Once the pump has started and attained 95 % high vessel and the head of water in a reference leg filled with speed, the 60 hz source is auto-tripped and the recire condensate. In the safety grade level instrumentation pump coasts down to 25 % speed where the 15 hz power (narrow and wide range), this pressure differential is source is engaged. The major recirc pump trips are as converted to an equivalent level without compensating follows: for changes in water density with temperature, which causes the measured level to be higher than the actual (1) At any power, trip to low speed ifinadequate downcomer level at low temperature conditions. subcooling for NPSH (T_-T, suction < 8 degrees F) A design basis accident at power is loss of both recire pumps [Section 15 of Grand Gulf, UFSAR]. Tech Specs (2) At feedwater flow < 23.3% and FCV < 24% require operator action to scram the reactor via placing open, trip to low speed to prevent FCV the mode switch in the Shutdown position [TS 3/4.4,1 of cavitation Grand Gulf. Tech Specs). This is to reduce the time (prior to trip) during which the thermal margin (critical (3) With either discharge or suction isolation valves best flux ratio)is below normal. The reactor will trip on < 90% open, pumps are tripped and cannot be high water level if the operater fails to manually tnp. started. Note that a decrease in recinulation increases measured water level. He level is measured in the downcomer, During startup, the plant follows the power flow and following a decrease in recirculation flow with operating map [ Figure 4.4-5 of Grand Gulf, UFSAR]. feedwater flow constant, the level in the downcomer will The recire pumps are started with the FCVs at minimum increase. Without forced recirculation, cooldown is open position. Once the pumps trip to low speed, the governed by the inadequate Decay Heat Removal FCVs are opened to maximum open position. When Vol. 2. Part 2 C-3 NUREG/CR-6143 e
_ , . - - . _. - _ - ~ f l 1 i : Overview of Plant power is > 30% the low feedwater interlock is cleared, line break. Downstream of the MSIVs, the steam lines , and the recirc pumps are switched to high speed after the provide steam to the high pressure turbine through the , FCVs are closed to minimum (to avoid reactivity turbine stop and control valves. Between the outboard insertion). The rod pattem is established and the FCVs MSIV and the stop/ control valves in each steam line, a are throttled open to achieve the desired operating branch feed is provided to the Reactor Feedwater Pump power. Turbine (RFPT) supply header. All four main steam i lines feed this header. This header also is piped to the The RilR system has seven modes of operation, five of three parallel turbine bypass lines each of which contains which are emphasized: LPCI, Containment Spray, SP a turbine bypass valve and discharges to one of the three Cooling, RCIC steam condensing (not used at Grand parallel condensers. { Gulf), and shutdown cooling [Section 5 of Grand Gulf, i UFSAR][USNRC, !983]. ne other two modes Between the inboard MSIV and the vessel, each mam i (containment flooding and spent fuel pool cooling) are steam line contains Safety Relief Valves (SRVs) which less likely to be used. At power, RH R is imed up for discharge to the SP. As in most BWRs, these valves LPCI and is subject to auto mitiation in either that mode serve both a safety function and a relief function and are 1 or the containment spray mode. Two of the RHR trains, different from the case at most PWRs which use separate i A and B, contain RHR heat exchangers and can be safety and relief valves. The safety function is to manually realigned for shutdown cooling when in OC 3 prevent the primary system from exceeding the ACME if the vessel pressure is below the cut-ia permissive [TS code allowable pressure of 1375 psig (design + 10%). 3/4.4.9 of Grand Gulf. Tech Specs]. The cut-in permissive is 135 psig vessel pressure [Section 5 of The system cannot be depressurized with the SRVs Grand Gulf UFSAR]. purely performing their safety function. The SRVs pop open at their safety pressure setting and require no power , ne Reactor Core Isolation Cooling System (RCIC) to do so. The SRVs automatically open at their lower ( serves the BWR as does the auxiliary feedwater system relief setting, require air to do so, and fail closed on loss ; at a PWR. RCIC is used to remove decay heat if the of air. Accumulators are provided. To operate an SRV main condenser /feedwater heat sink / makeup capability is in its relief mode, DC powered solenoid control valves in ! unavailable [Section 15 of Grand Gulf, UFSAR] the air supply line must be energized. To depressurize . [USNRC,1983]. RCIC has two modes of operation. the system, the SRVs can be manually opened, and of The auto mode is one in which steam is relieved by the the 20 total SRVs eight can be actuated by the Automatic j Safety Relief Valves to the SP, and makeup is from Depressurization System (ADS). ! either the condensate storage tank or the SP via the steam-driven RCIC pump. His lineup can operate at Main steam line A provides steam to the RCIC drive rated pressure and temperature. The manual mode uses turbine. This steam is provided off the mam line [' the RHR heat exchangers in a steam condensing mode upstream of the inboard MSIV. Also, a continuous vent with their condensate retumed to the vessel by the RCIC to vent noncondensibles is provided off main steam line , pump. This mode is only allowed at less than 500 psig A upstream of its inboard MSIV. His vent path is I reactor pressure due to the limiting design pressure of provided with an isolation valve (F005) and two pressure ; the RilR heat exchangers. This steam condensing mode reducing orifices, and it discharges to the main ' can match decay heat 1.5 hr after shutdown. (Grand condenser where deaeration occurs. At power F005 is j Gulf does not utilize the RCIC steam condensing lineup.) open. This line also connects to the reactor head vent ! Since the HPCS is a fully diverse backup for RCIC, tech line which vents the vessel to atmoepheric pressure when l specs allow RCIC to be unavailable for up to 14 days if two isolation valves (F001 and F002) are opened. At l HPCS is operable [TS 3/4/7/3 of Grand Gulf, Tech power F001 and F002 are closed. The Plant Shutdown t Specs]. ne RCIC pump turbine is driven off main procedure specifies that when reactor temperature is less j steam line A. than 190 degrees F, F005 is closed and both F001 and , F002 are opened. His establishes atmospheric pressure i he main steam system consists of four main steam in the vessel and renders the fluid slightly subcooled. { lines: A, B, C, and D, details of which are provided in Sections 5 and 10 of the FSAR. Each line contains two The turbine system is described in Section 10 of the i Main Steam Isolation Valves (MSIV), one inboard and FSAR. The following discussion is based on that one outboard of containment, which fait closed and information supplemented with information on the design ; isolate the vessel given such accidents as a main steam and operational characteristics of power plant , NUREG/CR-6143 C-4 Vol. 2, Part 2 I l
I I Overview of Plant components. The turbine pressure control setpoint is 950 rolled off turning gear at about 400 psig. Check valves psig. ne turbine bypass capacity is 35 % of rated isolate the vessel following a feedwater line break. steam. With bypass, the turbine generator system can eccommodate a 100% to 40% load rejection at up to 1 % The Reactor Water Cleanup (RWCU) system is used to per second, and it can accommodate a step load purify the reactor water. Also, during startup and ( reduction of 35%. A turbine trip with power greater shutdown when level is not controlled with feedwater, I than 35% causes a reactor trip. The high pressure the RWCU system is used to blowdown to either the turbine exhausts to two parallel Moisture Separator main condenser or the liquid radwaste system to control Reheaters (MSR) which reheat the exhaust to remove level which tends to increase due to fill from the control moisture before feeding the three parallel low pressure rod drive cooling system, and due to swell during turbines. Gland seal steam is supplied by a seal steam heatup. This system is indirectly in the tech specs generator. Gland seal steam is required to provide through chemistry control [TS 3/4.4.4, of Grand Gulf, controlled bleeding of steam across the turbine seals to Tech Specs]. prevent air in leaka;c into the main condenser when it is at vacuum. He seal steam generator is heated by either main steam or turbine extraction, and it supplies nonradioactive steam. The turbine shaft is provided with a hydraulic-driven turning gear to rotate the drum whenever the turbine is heating up or cooling off to minimize thermal stresses which could kink the shaft. He turbine must be on turning gear rotation before any steam is admitted. The Cold Shutdown to Generator Carrying Minimum lead procedure requires that seal steam never be applied to the main turbine shaft seals if the turbine is not on tuming gear. When gland seal steam is admitted, it rises to the top of the turbine casing and heats the top of the rotor, while the bottom of the rotor is kept cool due to condenser circulating water. Thus, if the rotor is not tuming, it is stressed due to a thermal gradient and can how and become unbalanced. To prevent thermal stresses, the turbine is kept on turning gear whenever it is heated up or cooled down. He major turbine trips are low condenser vacuum and overspeed. He turbine uses the EHC system for control. The condenser vacuum is maintained by steam jet air ejectors when steam is available and by mechanical vacuum pumps when it is not available. He feedwater and condensate systems provide feedwater to the vessel. Three 50% capacity motor driven condensate pumps pull from the intermediate pressure condenser hotwell and supply three 50% capacity motor driven condensate booster pumps. The now from the booster pumps is heated by a series oflow pressure feedwater heaters, then the water is supplied to two variable speed turbine driven feedwater pumps. The output of the feedwater pumps passes through a series of high pressure feedwater heaters then enters the vessel downcomer at 420 degrees F. Regenerative feedwater heating is used to increase the thermal efficiency of the rankine cycle. During startup, How to the vessel is supplied by the condensate and booster pumps up to about $50 psig, with the first feedwater pump turbine Vol. 2, Part 2 C-5 NUREG/CR-6143
Overview of Plant
. References for Appendix C
[USNRC,1989] USNRC, " Severe Accident Risks: [ General Electire,1981] General Electric Co., BWR/6 An Assessment for Five U.S. Fundamentals, Operator Nuclear Power Plants," NUREG- Training Services, Tulsa, 1150, June,1989. Oklahoma,1981. [SERI,1992] System Energy Resources, [El-Wakil,1971] Nuclear Enercy Conversion. Inc.," Grand Gulf Updated Final Intext Educational Publishers, Safety Analysis Report",1992. 1971. [USNRC 1984] USNRC, " Technical Specifications, [USNRC,1983] USNRC, Course Material for Grand Gulf Nuclear Station Unit R-104B, " Technology No.1,* Docket No. 50-416, Manual for BWR/4 Design". Appendix "A" to License No. NPF-29, NUREG-0934, October, [ General Electric,1980] General Electric Co. 1984. *BWR/6 General Description of a Boiling Water Reactor", Revised September 1980. I NUREG/CR-6143 C-6 Vol. 2, Part 2 f
Appendix D. Initiating Event Analysis from Screening Report His Appendix describes the initiating events that were 4. Special Events. identified and used for each POS during the coarse screemng analysis [ Whitehead et al.,1991]. This In each of these subsections, the scope of events Appendix is from that earlier analysis. It correlates each considered, as well as the methods employed to obtain initiating event to the appropriate plant operational state the frequencies and distributions for each of the events, (POS). in addition, the information sources used to are described. A table summarizing the frequencies and quantify the initiating event frequencies and the screening distributions for the events is included in each values assigned to each initiating event are presented, subsection, along with comments that provide detailed descriptions of the methods for obtaining the frequencies. D.1 Approach and Summary D.2 Transient Initiating Events The initiating event analysis task for this project was performed in much the same manner as for any full D.2.1 Background power PRA. First, a definition of what is meant by an initiating event was developed, and then a search for . . In rder to obtam the transient categories considered m. events which fit the definition was made. Finally, NUREG/CR-4550 volume 6 [ Drouin et al. 1989], EPRI information was analyzed to produce estimates of the , , frequency for each initiating event. I'""' "I '"*"I" ** 8 " "P* ""' *8 * "" "' P !*"I response. The reader is referred to Table 4.3 3 of Reference 1, which desenbes in detail the individual For this study there are two definitions used for an EPRI events and their groupmg mto the categories initiating event depending upon the initial POS of the
. .. presented in Table 4.3-1 of Reference 1. From Table plant. For power operation, an imtiating event is dermed 4.3-1, the following transient categories are considered:
as an event which requires a sapid shutdown or trip of the plant, so as to challenge the safety systems to remove TMM Qe Deh the decay heat still being generated in the reactor core. For non-power operations, an initiating event is defined Tl Loss of Offsite Power as an event which would require an automatic or manual i response to prevent core damage in the vessel. T2 Transients with Loss of the l Power Conversion System (PCS) Five major groups ofinitiating events were identified m. this project: Transients, Loss of Coolant Accidents Transients with the PCS initially T3A (LOCAs), Decay Heat Removal Challenges, Special ava lable ! Events, and Hazards Events. The Intemal Fire and l Flood Hazards Events will be considered in a subsequent Transients involving Loss of T3B stage of this project. The effects of seismic events will Feedwater but with the be analyzed by another organization, and all other . steamside of PCS initially , externally imtiated events are beyond the scope of this g l project. Table D.1 1 sununarizes the initiators included 1 in this study along with the screening values assigned to Transient caused by Inadvertent T3C each mitiator for each POS. The event nomenclature Open Relief Valve defines the shorthand notation used for each initiator in the subsequent tasks of this project. ne remainder of the section is divided into four D.2.2 Introduction subsections: The individual EPRI events comprising the transient categories discussed in section D.2.1 were reviewed for
- 1. Transient Initiating Events, their applicability to the various POSs. Each of these transient categories is listed in Table D.2-1, and the
- 2. LOCA Initiating Events, comments included with the table describe in detail the applicability of the various events in each POS. less of
- 3. Decay Heat Removal Challenge Initiators, and Of fsite Power (TI) is applicable to all POSs. See Vol. 2, Part 2 D-1 NUREG/CR-6143
IE Screening I Table D.1.1 Grand Gulf Low Power and Shutdown Initiating Events and Frequencies Initiating Event Mean Frequency Nomenclature (per year) { Description for Each POS 2 3 4 5 1 6 7
)
Tl Loss of Offsito Power 0.07 0.13 0.13 0.13 0.13 0.13 0.13 ! (LOSP) transient T2 Transient with loss of the 1.62 1.62 1,62 - - - - Power Conversion System (PCS) T3A Transient with PCS 4.54 4.54 4.54 - - - - initially available , I T3B Transients involving loss 0.88 0.88 0.88 - - - - of Feedwater i T3C Transient caused by 0.14 0.14 0.14 - - - - Inadvertent Open Relief Valve A Large LOCA I E-4 IE-4 IE-4 IE-4 IE-5 IES lE-5 Si latermediate LOCA 3 E-4 3 E-4 3 E-4 3L4 3L5 3E5 3 E-5
$2 Small LOCA 3L3 3E3 3E3 3E 3 3 E-4 364 3E-4 53 Small Sma!! LOCA 3 E-2 3 E-2 3 E-2 3E2 3E-3 3 E-3 3D3 V interfacing System LOCA - - - - - -
R Vessel Rupture - - - - - - - lil Diversion to Supprrssion - - - BE-2 BE-2 862 852 Pool via RiiR H2 Diversion to Condenser - - - - - - - via RWCU J1 LOCA in Connected BE4 8E-4 BE-4 - - - - System (RCIC) J2 LOCA in Connected - - - SE-2 SE-2 SE2 5L2 System (R}iR) K Test /Mainterunce-Induced - . - - . . - LOCA ! ElB Isolation of SDC loop B - - - 0.1 0.1 0.1 0.1 only j ElC lsolation of RWCU as - - - - - - 0.1 DilR EID isolation of ADilRS only - - - - 0.1 0.1 0.1 EIT Isolation of SDC Comnwn - - - 0.1 01 0.1 0.1 Svetion Line 1 l NUREG/CR-6143 D-2 Vol. 2, Part 2 i 1 l l
IE Screening l l Table D.1.1 Grand Gulf Low Power and Shutdown Initiating Events and Frequencies l 1 1 Initiating Event Mean Frequency i Nomenclature (per year) l Description for Each POS EIV !sr>lation of Comrnon - - - - 0.1 0.1 0.1 Suction Line for ADHR$ 1 E2B less of SDC bop B only - - - 0.37 0.37 0.37 0.37 E2C less of RWCU as DHR - - - - - - 0.1 E2D Loss of ADHRS only - - - - 0.37 0.37 0.37 E2T tess of SDC Common - - - 0,37 0.37 0.37 0.37 Suction Line E2V Loss of Common Suction - - - 0.37 0.37 0.37 Line for ADHRS T4A Rod Withdrawal Error - - - - - - - T4B Refueling Accidera (Rod - - - - - - - or Fuel Misposition) T4C Instability Event - - - - - - - T5A less of all SSW - - - 1.802 1.8L2 1.802 1.8D2 T5B less of all TBN 1.8E-2 1.8L2 1.8 D2 1.8E2 1.852 1.P E.2 - T5C less of all PSW (includes 1.8L2 1.8 E-2 1.8D2 1.8D2 1.8E2 1.8E2 - Radial WeII) T5D less of all CCW - - I .8D2 1.862 1.862 - TAB less of IE 4160 V AC - - - 9E4 9 E-4 964 9E4 Bus B
?
TDB less of IE 125 V DC Bus - - - 663 6D3 6E-3 6D3 l B l TIA Loss ofinstrument Air 0.5 0.5 , 0.5 0.5 0.5 0.5 - 8 TORY Inadvenent Open Relief - - 0.1 - - - Valve at Shutdown 3 TIOP Inadvertent - - - 0.16 0.16 - - Overpressurization (makeup greater than letdown) T!HP Inadvenent - - - IL2 162 - - Overpressurization via Spurious llPCS Actuation TIOF Inadvertent Overfill vis - - - 402 402 - - LPCS or LPCI TLhl less of Makeup - - - 0.49 0.40 0.49 .- Vol. 2, Part 2 D-3 NUREG/CR-6143
IE Scaening Table D.2.I Transients Plant State: Mean Frequency Description [per Calendar Year] Distribution Comments Tl LOSS OF OFFSITE POWER FULL POWER: 0 078 - 1 1: 0.07 - 1 2: 0.13 - ,1 3: 0.13 - 1 4: 0.13 - 1 5: 0.13 - 1 6: 0.13 - 1 7: 0.13 - 1 T2 TRANSIENTS WITH LOSS OF FULL POWER: 1.62 LOGNORMAL; EF= 3 2 Tile POWER CONVERSION 1: 1.62 2 SYSTEM (PCS) 2: 1.62 2 ! 3: 1.62 2 4: N/A N/A 3 , 5: N/A
- 3 6: N/A
- 3 ;
7: N/A
- 3 T3A TRANSIENTS WITH PCS FULL POWER: 4.51 LOGNORMAL; EF= 3 4 INITIALLY AVAILABLE 1: 4.54 (4.50 to 4.54) 4 and 5 2: 4.54 (4.50 to 4.54) 4 and 5 3: 4.54 (4.50 to 4.54) 4 and 5 ,
4: N/A N/A 6 5: N/A
- 6 6: N/A
- 6 7: N/A
- 6 T3B TRANSIENTS INVOLVING FULL POWER: 0.76 LOGNORM AL; EF= 3 7 LOSS OF FEEDWATER (LOFW) 1: 0.88 (0.76 to 0.88) 8 2: 0.88 (0.76 to 0.88) 8 3: 0.88 (0.76 to 0.88) 8 4: N/A N/A 9 5: N/A
- 9 6: N/A
- 9 7: N/A
- 9 T3C INADVERTENT OPEN RELIEF FULL POWER: 0.14 LOGNORM AL; EF-3 10 VALVE (IORV) 1: 0.14 10 2: 0.14 "
11 l 3: 0.14 " 11 4: N/A N/A 12 ! 5: N/A " 12 6: N/A " 12 7: N/A
- 12 NUREG/CR-6143 D-4 Vol. 2, Part 2 ;
I l
IE Screenmg Table D.2.1 Comments (1) The calculation of LOSP frequency and distribution is described in Appendix G. {2} De frequency and distribution for T2 were taken from Table 4.9-26 of [Drouin et al.,1989). Table 4.3-1 of [Drouin et al.,1989] describes the individual EPRI transient events comprising event T2. He values in Table 4.9-26 were calculated from the EPRI transient category frequency data in Table 33 of[Mackowiak et al.,1985]. He frequency used for full power is taken to apply to POS 1, based on a review of the individual EPRI events included in T2. For POSs 2 and 3 where the turbine / generator is tripped, but the turbine bypass and condensate are still used, the frequency is conservatively taken to be that which was used for the full conservative since not all events that make up T2 are valid during theseit POSs; however, is expected that this power analy conservatism will not be important because of the small amount of time spent in these two POSs. {3} De events which make up T2 are not valid during these POSs. {4) The frequency repor*ed ni Table 4.9-26 of[Drouin et al.,1989] includes the EPRI transient events listed in Table 4.31 of [Drouin et al.,1989] for the event T3A. For PCS 1, all of these events are included in the T3A frequency. It should be noted that several of the events included in T3A may not be applicable for POS I when the mode switch is in RUN. EPRI events 14,18, and 21 are all postulated to cause reactor SCRAM on high neutron flux. It is unclear whether, during POS I operations with the mode switch in the RUN position, the reactivity insertion from these events would be sufficient to cause SCRAM on high neutron flux. In this case, these events would have to be removed from T3A for POS 1. For this analysis we conservatively assume that these events will cause a SCRAM and therefore are included in the initiating event frequency. For POS I with the mode switch in STARTUP, the EPRI event 26, "High Feedwater Flow During Startup or Shutdown", has been added to T3A. The frequency for this event in Table 33 of[Mackowiak et al.,1985] is 0.04/ year. {5} Note that the events 14,18, and 21 as described above in {4} are postulated to cause a reactor SCRAM on high neutron flux. With the mode switch in STARTUP a reactor trip will occur at a flux-indicated power level of 15 %, according to Grand Gulf Technical Specifications. It is assumed that these reactivity insertions are sufficient to cause an increase in power level which exceeds the 15 % setpoint. 1 {6} None of the EPRI transient events under T3A apply in POSs 4 through 7, based on a review of the individual ) EPRI transient events comprising T3A. Although several might be postulated to cause an interruption in decay heat removal operations via the RHR, these are assumed to be included in the frequency determined for the DHR challenge initiators involving the RHR (see Table 4.2.3-1). {7} The frequency and distribution for T3B are taken from Table 4.9-26 of[Drouin et al.,1989]; Table 4.3-1 of [Drouin et al.,1989] describes the individual EPRI transient events comprising event T3B. The values in Table 4.9-26 were calculated from the EPRI transient category frequency data m Table 33 of [Mackowiak et al.,1985]. (8} The frequency used for full power is taken to apply to POS I when the mode switch is in RUN, based on a review of the individual EPRI events included in T3B. The frequency of T3B in POS I when the mode switch is in STARTUP is calculated by addmg the frequency for EPRI event 25, Low Feedwater Flow During Startup or Shutdown, to the full power frequency described in {7}. Table 33 of[NRC, NUREG 3862] reports the event 25 frequency as 0.12/ year. The error factor is assumed to be the same as for full power. To be conservative the frequency for POS 1 is taken to be 0.88 with a lognormal distribution having an error factor of 3. His same frequency was conservatively assumed to apply to POSs 2 and 3. {9) Loss of feedwater events are not applicable in these POSs. {l0} The event T3C, Inadvertent Open Relief Valve, is considered in tenns of its potential to cause a SCRAM (due to high suppression pool temperature) for POS 1, as it was for Full Power [1]. The same frequency reported in Table 4.9-26 of [Drouin et al.,1989] for this event was assigned to POS 1, as it is not expected to be any higher. ; {l1} Although not a concern in terms of causing a SCRAM, the potentially high pressure and temperature conditions existing in these plant states require that this event be considered fer its loss of vessel inventory potential. (12} For POSs 5,6, and 7 this event is not of concern since the reactor is at atmospheric pressure (vented in POS 5; head offin POS 6 and 7). For POS 4 a special initiator was developed. See discussion in Section 4.2.4.3. I l Vol. 2, Part 2 D-5 NUREG/CR-6143 !
IE Screening Appendix 0 of this report for a listing of the data used to Another type of LOCA considered in the NUREG 4550 determine the frequency of T1. analysis is the Interfacing System LOCA, or V, which typically involves the failure of a high-to-low pressure It should be noted that the frequencies listed for the interface such that reactor pressure causes failure within various transient initiators are given in terms of plant a low pressure system. Such failures were found to calendar years. A reference used for many of the most likely involve failure of a testable check valve on frequency calculations [Mackowiak et al.,1985] states ECCS injection lines. The V scenario was eliminated as that " reactor years" (which usually denotes a time an initiating event for Grand Gulf based on plant-specific corrected by a plant's capacity factor) were used to arguments regarding testing practices and plant determine event fmluencies. However, the definition of configuration [Drouin et al.,1989].
- reactor year
- in this report appears to be equivalent to a plant calendar year. A final type of LOCA considered in NUREG 4550 is the Reactor Vessel Rupture event, R. The argument for Because the frequencies are given on a per-calendar-year excluding this initiating event in the Grand Gulf analysis tasis, it is intended that the transient frequencies reported draws upon previous studies involving PWRs, and in Table D.2-1 will be corrected by factors representing concludes a lower vessel rupture frequency for BWRs.
the fraction of the plant calendar year spent in a The argument also states that because Grand Gulf's particular POS. In addition, events which depend on vessel is newer, the rupture event is even less likely operation of a particular system, such as the condenser, (presumably due to material considerations with regard to should be multiplied by the fraction of time the given the pressurized thermal shock concern) [Drouin et al., system operates in a particular POS. For the screening 1989]. analysis this fraction was assumed to be 1.0. D.3.2 Introduction D.3 LOCA Initiating Events The following sections describe the LOCA initiating events considered for this study. Appheability of events D.3.1 Background considered in NUREG 4550 are discussed first. followed by descriptions of LOCA events unique to this wady. The accident initiator termed Loss of Coolant Accident The scope of events considered is presented, as wdl as (LOCA) has traditionally referred to piping ruptures of thejustification for exclusion of certain events. Table various sizes causing a failure of the coolant pressure D.3-1 summarizes the mean frequencies and distnbutions ' boundary, in NUREG-4550, Vol. 6 [Drouin et al.. assigned to the various LOCA events, along with 1989), the possible LOCAs were categorized according comments specifically describing the method for to size of the break, based on similar safety system obtaining the frequencies. requirements within a category. The various LOCA categories used in the NUREG 4550 analysis are It should be noted that the frequencies listed for the described below: various LOCA initiators are given in terms of plant calendar years. It is intended that these frequencies will LOCA SJ11 be corrected by factors representing the fraction of the plant calendar year spent in the POS being examined. In A Steam > 0.4 sq.ft. addition, events which involve operating systems are to Liquid > 0.4 sq.ft. be multiplied by the fraction of time the given system operates in a POS. This fraction was conservatively S1 Steam 0.13 - 0.4 sq.ft. assumed to be 1.0 for this screening study. Liquid 0.007 - 0.4 sq.ft. D.3.3 LOCA Events from NUREG 4550 S2 Steam < 0.13 sq.ft. j Liquid < 0.007 sq.ft. In determining the applicability of events considered in i NUREG 4550 to POSs other than full power. S3 Recirculation pump seal break; consideration of the differing plant configurations and categorized as S2 if operator does conditions for the various POSs is necessary. In most not isolate. NUREG/CR-6143 D-6 Vol. 2, Part 2 i
IE Screening Table D.3.1 Loss of Coolant Accidents Plant State: Mean Frequency Description [per CALENDAR YEAR] Distribution Comments A LARGE LOCA FULL POWER: IE-4 LOGNORM AL; EF = 3 1 1: IE-4 1 2: IE-4 1 3: IE-4 1 4: IE-4 1 5: 1E-5 2 6: IE-5 2 7: 1E-5 2 St INTERMEDIATE FULL POWER: 3E-4 LOGNORM AL; EF= 3 i LOCA 1: 3E-4 1 2: 3E-4 1 3: 3 E-4 l , 4: 3E-4 1 5: 3E-5 2 6: 3E-5 2 7: 3E-5 2 S2 SM ALL LOCA FULL POWER: 3E-3 LOGNORM AL; EF= 3 1 1: 3E-3 1 2: 3E-3 1 3: 3E-3 1 4: 3E-3 1 5: 3E-4 2 6: 3E-4 2 7: 3E-4 2 S3 SMALL-SMALL FULL POWER: 3E-2 LOGNORM AL; EF= 3 i LOCA 1: 3E-2 1
- i 2: 3E-2 1 3: 3 E-2 1 4: 3E-2 1 5: 3E-3 2 6: 3E-3 2 7: 3E-3 2 V INTERFACING FULL POWER: N/A N/A 3 SYSTEM LOCA (failure of high to low 1: N/A 3 pressure interface) 2: N/A 4 l 3: N/A 4 i 4: N/A 4 5: N/A 4 6: N/A 4 7: N/A 4 Vol. 2. Part 2 D-7 NUREG/CR-6143
IE Screening Table D.3.1 Loss of Coolant Accidents Plant State: Mean Frequency Description [per CALENDAR YEAR] Distribution Comments R VESSEL FULL POWER: N/A N/A 5 RUPTURE 1: N/A " 5 2: N/A " 5 3: N/A " 5 4: N/A " 5 5: N/A
- 5 6: N/A "
5 7: N/A " 5 H1 DIVERSION OF FULL POWER: N/A N/A 6 VESSEL 1: N/A " 6 INVENTORY TO 2: N/A " 7 THE SUPPRESSION 3 N/A 7 POOL via RHR 4: 8E-2 LOGNORMAL; EF 5 8, 9 5: 8E-2 " 8, 9 6: SE-2 " 8, 9 7: SE-2 " 8, 9 H2 DIVERSION OF FULL POWER: N/A N/A 10 VESSEL 1: N/A " 10 INVENTORY via 2: " 10 RWCU 3: " 10 4: 10 5: 10 6: 10 7: 10 J1 LOCA IN FULL POWER: N/A N/A 11 OPERATING 1: 8E-4 LOGNORM AL: EF- 10 12 CONNECTED 2: 8E-4 " 12 SYSTEM (RCIC) 3: BE-4 " 12 4: N/A N/A 13 5: 13 6: 13 7:
- 13 J2 LOCA IN FULL POWER: N/A N/A 11 OPERATING 1: N/A "
14 CONNECTED 2: " 14 SYSTEM (RHR) 3: " 14 4: SE-2 LOGNORM AL; EF= 10 15 5: SE-2
- 15 6: SE 2 "
15 7: SE-2 " 15 l l NUREG/CR-6143 D-8 Vol. 2, Part 2
IE Screening Table D.3.1 Loss of Coolant Accidents Plant State: Mean Frequency Description [per CALENDAR YEAR] ' Distribution Commcnts K1 MAINTENANCE 16,17 INDUCED LOCA IN RHRS i K2 MAINTENANCE 16,17 INDUCED LOCA IN RWCU SYSTEM K3 MAINTENANCE 16,17 INDUCED LOCA IN RCIC SYSTEM K4 MA!b NANCE 16, 17 INDUCEI LOCA IN L CS SYSTEM K5 M AINTENANCE 16,17 INDUCED LOCA IN LPCS SYSTEM K6 MAINTENANCE 16,17 INDUCED LOCA IN RECIRC J SYSTEM Table D.3.1 Comments {1} Frequency values for primary system LOCAs at Full Power are from Table 4.9-26 of [Drouin et al.,1989] and the distribution value from [Mackowiak et al.,1985). Values for POSs 1 through 4 were taken to be the same as for Full Power (see {2)). l
'?) The frequencies for POSs 5 through 7 are scaled down by 0.1 from the values listed in Table 4.9-26 of [Drouin et al.,1989], based on the information in Table A-5 of [ Wright et al,1987]. This table presents the expected effect on overall LOCA frequency for various factors such as pipe size or mode of operation. The multipliers in the table are meant to be applied to overall mean frequency. The factor 0.1 reported for " Shutdown
- in this table seems to apply only to Cold Shutdown and Refueling. " Starting Up" and " Shutting Down" as defined in [ Wright l et al,1987] encompass Hot Shutdown and Startup, whereas
- Normal Operation" covers Low and Full Power.
Although the results presented in Appendix A of the report have a large associated uncertainty (because expert clicitation was used to obtain the results), this multiplier is considered to be a valid qualitative adjustment for LOCA frequency during shutdown, versus the overall frequency used in the full power analysis. Factors greater than one are reported in the table for modes other than " Shutdown *, but are not considered applicable to the Full Power values, because the overall mean frequency reported in the table is four orders of magnitude lower than Vol. 2, Part 2 D-9 NHREG/CR-6143
IE Screening l Table D.3.1 Comments (Continued) the smallest Full Power frequency. The distributions from [Mackowiak et al.,1985] have been applied to all l plant states, as they are considered realistic for this analysis. l {3} Section 4.4.15 of[Drouin et al.,1989] justifies the exclusion of Interfacing LOCAs from consideration in the Grand Gulf Full Power study. These arguments are taken to apply to POS 1 since the plant configuration and conditions are nearly the same as for Full Power. {4} For POSs 2 through 7 .he plant conditions are such that a high-to-low pressure interface is not likely to exist. For these modes, new event identifiers have been created to describe LOCAs involving interfacing systems: 11 for mverable diversion of vessel inventory through a system connected to the primary, J for LOCAs in a connected system through which primary water is flowing, and K for maintenance-induced LOCAs in connected systems. I (5} Section 4.4.16 of[Drouin et al.,1989] describes the reason for exclusion of the Vessel Rupm:c event from the Full Power study, This same reasoning should apply to POS 1. In POSs 2 through 7, the exi .a c pressure or potential for overpressure in the vessel is considered to be significantly less than at Full t;ower. The arguments employed in [Drouin et al.,1989] regarding the probability of vessel rupture while at power are considered to bound the prol. ability during POSs 2 through 7. {6} Diversion of Vessel Inventory nrough the R11RS is not considered applicable for Full Power for the reasons explained in the Interfacing LOCA section ofIDrouin et al.,1989), and does not apply to POS 1 according to the same arguments. (7) The ' Diversion of Vessel Inventory Through RIIRS* event is not applicable in POSs 2 and 3 since the RIIR system is not normally used in these POSs. {8} The " Diversion of Vevel Inventory Through RiiRS* event frequency for POSs 4 through 7 has been calculated using tne data collected in [ Vine et al.,1989]. Thirteen events involving loss of vessel inventory through the R11R system were identified over the seven-year (1977-1983) time period covered by the study. Of the thirteen events, five events occurred during pre-commercial operation, and two events involved heat exchanger leakage, which is considered under event 12. One event, counted as a single event in [ Vine et al.,1989], has been considered as two separate events in this frequency calculation. Six of the remaining seven commercial events involved loss of coolant inventory to the suppression pool. The seventh event involved significant coolant shrinkage upon cooldown initiation. Diversion of Vessel Inventory is defined to include events involving diversion to a sizable fluid sink, e.g. the suppression pool. The seven events mentioned above are the basis for the R11R Diversion of Vessel Inventory frequency. In each of these events tha coolant was " recoverable *, i.e. not lost to the system. This type of event appears to be the only credible diversion of inventory event involving the RilR (piping ruptures, component failures, or maintenance / test-induced LOCAs are considered in events J2 and K). The events encompass two possible paths out of the vessel: thmugh the RllR Recirculation Loop connection, and via the RilR/LPCI inlet line. The first path terminates at 2/3 core height while the latter path naturally t~erminates at over 50 inches above the top of the active fuel, but is still included as part of the RilR inventory diversion frequency. It should be noted that the inventory diversion event is potentially significant during shutdown because of possible disabling of isolation signals on vessel level, as has been the case in one precommercial event. The seven years covered by the study represent approximately 152 BWR plant operating years. A mean frequency for RiiR Loss of Vessel Inventory is calculated using seven events over 152 years, by first calculating a median value using a binomial distribution computer [ Binomial Computer] (5E-2). The error factor is estimated by finding the 5 % and 95 % confidence values on the binomial computer (IE-2 and 2.5E-1), and roughly doubling that value. The mean, assuming a lognormal distribution about the median value found above, is then SE 2/yr. NtJREG/CR-6143 D 10 Vol. 2 Part 2
IE Screening l Table D.3.1 Comments (Continued) (9) Diversion of vessel inventory via the 11PCS and LPCS systems is credible, based on the possible paths to the ! suppression pool involving failure on the testable check valve combined with two open isolation valves. Ilowever, according to [ Vine et al.,1986], all previous diversion events have involved only RiiR. In addition, the IIPCS and LPCS events, would terminate with a water level above the top of the active fuel. The dominant contributors to this event are expected to be maintenance / test errors and as such will be included in the K events. {l0} System normally in operation. Not considered as a diversion path. i (11) This initiator applies to systems through ovhich primary water is flowing. The RCIC and RilR (SDC) systems i are not normally operating in Full Power, f {l2} The frequency was estimated by assuming a steam line break down stream of MOV 45. The pipe segment , contains two valves with a failure rate of 4.5E-9/hr. Multiplying by the number of hours in a year yields a value of 7.8894E-5. This value was increased by a factor of 10, producing a fmal result of BE-4/yr. An EF of 10 was j assumed for a lognormal distribution. This should be conservative since the value should be reduced by the i fraction of time RCIC is operating in POS 1,2, or 3. i {l3} RCIC not operated in these POSs. , (14) RilR (SDC) does not normally operate during POS 1. It was operated one time in the Startup phase (" Training ; Startups"), but the utility decided not to operate SDC in this state again. Thus this initiator for POSI was assumed to be not applicable. RiiR (SDC) does not normally operate in POSs 2 and 3 and is assumed to be not applicable for these POSs. (IS} For POSs 4 through 7, the RIIR LOCA frequency due to pipe or component ruptures is derived from the argument of Expert "B' on Component Cooling Water Pipe Rupture in [ Wheeler et al.,1989], p. C-172. This expert used data from Appendix A, Figure A-2 of[ Wright et al.,1987] which has a very high associated uncertainty. This expert's mean value estimate for CCW pipe rupture was one order of magnitude lower than the aggregate mean for the three experts involved. Because no better source ofinformation was located, Figure A 3 of[ Wright et al.,1987] was consulted to obtain a RilR pipe rupture frequency. The pipe rupture frequency for RilR at power was found to be about the same : that for the CCW system (2E-7/ system year). Assuming the j same distribution as expert "B" applied to the CCW frequency, the mean for R11R should be about the same as CCW: IE-5/yr. Increasing this value by one order of magnitude in order to more closely match the aggregate j CCW frequency for the three experts yields IE-4/ system year. l Although the operating conditions of the RilR system may be more harsh than for CCW, the CCW system contains over 2.5 times the length of piping as in RiiR, so this frequency seems reasonable. 1 i In considering piping system component failures, Expert "C" of[ Wheeler et al.,1989] indicated that valves l would probably not fail at low pressure. Ilowever, pump or heat exchanger failures must also be taken into secount. [ Vine et al.,1986] reports two RilR IIeat Exchanger leak events causing about a 4000 gallon loss of l vessel inventory to the RBCCW system. . Assuming two events over 43.9 shutdown years, the frequency estimate ; is 0.05/ year. This value is much larger than the pipe rupture frequency estimated above, and is thus the value used for POSs 4 through 7. (16} Maintenancerrest-Induced LOCAs were not analyzed in the Full Power Study. {17} Maintenancerrest-Induced LOCAs are of concern for POSs 2 through 7, where maintenance or test activities inadvertently open a path whereby coolant inventory is lost (e.g. removal of components for maintenance and improper valve alignments). All systems connected to the primary are considered for their K event potential. The analysis for these events will take place during the detailed phase of the project. Vol. 2, Part 2 D-11 NUREG/CR-6143
V - .
=
IE Screening cases, the less attessful temperature and pressure Overpressurization (see Table 4.51), may have a bearing conditions during shutdown should reduce the frequency on vessel rupture, as discussed in note (15) of Table of the various LOCA events considered at full power, or D.5-1. allow elimination of some events. Table D.3-1 lists the various LOC A events considered, their assigned D.3.4 LOCA Events Unique to Low screening frequencies and distributions, and comments power / Shutdown Operations describing in detail the method for obtaining the heqwnss. Additional loss of coolant events have been postulated for the POSs defined in this study, due to the unusual plant D.3.3.1 LOCA Categories configurations and maintenance practices occurring in these POSs. nree types of events, all involving ne various LOCA categories (A, Si, S2, and S3) sysm c mecte t e pr nian, am en ed fm een assigned for full power are considered applicable for all POSs: 1) 11, involving recoverable diversion of vessel PO3s. Reclassification of the LOCA sizes for the various inventory through a connected system; 2) J, loss of plant states is not considered necessary. He c lant in an operating connected system involving frequencies presented in NUREG 4550 are considered P PNE "' "P ".ent failures; and 3) K, applicable to POSs 1,2,3, and 4. The error factors nsamtename/tes imlue As n muected systems from NUREG/CR-4550 Vol. I are applied because they with potential for draining vessel inventory. These are considered more realistic. Although the transient events, combined with the full-power events described m conditions existing in the Startup Phase of POS 1 could the previous section, are thought to encompass the be construed as more stressful to the plant than at full e I ss of emlant eats pssMe in aH mss. ne power, this is not considered to have a significant effect on the frequencies assigned for POS 1. The frequencies in sesera f the events described in this section, the for POSs 5,6, and 7 have been scaled down from the fr quency has been estimated using a known number of full power values, as described in conunent (2} of Table events o er a certam number of plant calendar years. A D.3-1
- binomi.I distribution computer (see note (8} of Table D.3-1) has been used to provide an estimate for the D.3.3.2 Interfacing System LOCA median frequency (using the 50% confidence value), and _
t give an indication of the error factor (using the 5 % and As described in the Background section above, 95% confidence values). The error factor mdicated by , Interfasing System LOCAs (V) were screened out of the e unual e mptu was appmxinsately doubW. ami a Reference 1 analysis by the use of arguments that apply mean fr quency was calculated from the b, m onual median to POS I as well. The high-to-low pressure interface assum ng a 1 gn rmal distribution. This method has conditions necessary for the V scenario do not exist been applied for 11 and J events. during Plant States 5,6, and 7 except possibly as a result of an accident initiating event. This type of V sequence . A.! mera
. emon ese inventwy is included in the appropriate event trees. Such conditions may exist during Plant States 2, 3, and 4, where maintenance / test conditions may increase the RemnaW Eversn of het Imenwy nent likelihood of a V event, but new LOCA categories have nv Ives the establishment of a path thrcugh a connected been created to take into account these situations (see
'l'I#"' "* D *****I * *" # 7 '
Section D.3.4.3). inventory is recoverable. All of these events involve diversion to the suppression pool. nese events are kept D.3.3.3 Vessel Rupture separate from the J and K events because the possibility I "'##"7 '"#'7 "'* ** *
- P '""' "" Y ""'
As described in the previous section, Vessel Rupture (R) resynw to this type of initiator. was excluded for Full Power. The less harsh conditions experienced in the POSs of this study allow exclusion of . in identifying the possible systems for the 11 event, the R event for these POSs as well. Although PO;,1 ns fmm the s essel to a possible smk. such as eme (i.e., the Startup Phase) may involve increased stresses supprem p am emfie . e padis am to the vessel due to the transient vessel conditions, the R bmught about in most cases by misalignment or failure event is also excluded for POS 1 (see comment {3} of f valves. Only two connected systems have the
] Table D.3-1), A special event, Inadvertent D-12 Vol. 2, Part 2 NUREG/CR-6143
)
E_ _.__ __
IE Screening potential to directly drain the vessel below the Top of the notes that all known diversions have been through RiiR. Active Fuel (TAF): 1) the Resideal liest Removal (For POSs 1,2, and 3, RWCU is in normal alignment (RHR); and 2) Reactor Water Clunup (RWCU) systems (i.e., cleanup mode). Beginning in POS 4, RWCU through the RIIR connection on the B recirculation loop. rejects water to the condenser or Rad-waste as a means Other connections, such as the LPCI/RHR injection line, of level control.) have the potential for draining coolant from the vessel but will naturally terminate above the top of the active D.3.4.1.3 Reactor Core Isolation Cooling ("Ck.) fuel. Rese connections are also considered in this event because of the possibility of non detection during An interfacing LOCA at full power involving the RCIC shutdown and the need for maketp or cooling. was ruled out in NUREG 4550, and the same arguments apply to POSs I through 7 as well. Vessel inventory ne following subsections desenbe the connections diversion through the RCIC system connection (to the considered and justification for exclusion. It should be feedwater line via the RiiRS) is not considered credible noted that instrumentation and leak-detection lines were because two check valves (one feedwater and one RCIC) not considered significant diversion paths and thus were must fail in addition to the testable check valve on the - not ccmsidered. He Alternate Decay IIcat Removal feedwater line. The event is thus ruled out for all plant System (ADilRS) is considered as part of the RIIRS. states. D.3.4.1.1 Residual llent Removal System D.3.4.I 4 liigh Pressure Core Spray (IIPCS) De RHRS is an important system with regard to vessel As with other connected systems, NUREG 4550 screened diversion potential in the shutdown POSs. Several out interfacing LOCAs involving the HPCS system. events have occurred in the past involving vessel Again, this applies to POSs I through 7 as well. Foi all inventory diversion to the suppression pool. These POSs, however, mamtenance or testing activities events formed the basis for the RHR inventory diversion involving the testable check valve or other valves make (III) frequency, as described in comrnent (8) of Table this event a concern and will be considered in the D.31. Diversion is possible through either the Maintenanceri'est-Induced (M/T-1) LOCA initiating recirculation loop Shutdown Cooling (SDC) suction event. (This type of initiating event requires connection, or through the LPCI/RHR injection line to development by the detailed IIRA methodology program the vessel. This event has been excluded for POSs I,2, and will be used if available. NOTE: Development not and 3 since the plant configuration is so similar to Full available.) where it can be used. A path to the Power. suppression pool exists through or.e testable check valve and two isolation valves. Thus, from a hardware D.3.4.1.2 Reactor Water Cleanup System perspective, the Mir-1 LOCA IEs are unlikely to occur. The event has been ruled out for all plant states. Section 4.4.15 (Interfacing LOCA) of NUREG 4550 considered the RWCU system. The contribution to core D.3.4.1.5 Low Prenure Core Spray (LPCS) damage frequency from a RWCU pipe break was assessed to be less than for large LOCA, and was thus The comments for liPCS above apply directly to LPCS. nited out. The arguments for ruhng out the RWCU included isolation potential, the high pressure design of D.3.4.2 LOCA in Operating Connected System the entire system, and the fact that the h> cation of the RWCU precludes any adverse affect of a RWCU pipe The LOCA in an Operating Connected System (J) event break on coolant injection systems. These arguments refers to pipe ruptures and component failures (e.g. , apply to POS 1. heat exchangers) in operating systems connected to the primary. Three systems fit this definition: RHRS. Diversion of vessel inventory through the RWCU is not RCIC, and RWCU. (Note that ADHRS is considered considered as an initiating event because no credible part of Ri!RS.) A J event involving the RWCU system drain path with a sizable fluid sink other than the has been ruled out of all POSs because it should be Condenser or Rad Waste was identified. Since RWCU included in the full power LOCA initiators since RWCU is normally rejecting to either Rad-Waste or the operates at full power. The J event for the RCIC system Condenser (or both), this diversion event was excluded (J1) and the RHR system (12) are possible and the as a potential initiatmg even Furthermore, NSAC 88 methods used to estimate their frequencies are described Vol. 2, Part 2 D-13 NUR EG/CR-6143 r
l l IE Screerung in Table D.3-1, Rese events apply to POSs 1,2, and 3 distribution computer has been used to provide an for J1 and POSs 4,5,6, and 7 for J2. Note that the estimate for the median frequency (using the 50% frequencies abould be reduced by the fraction of time confidence value), and to give an indication of the error these systems are actually operating. For the screening factor (using the 5 % and 95 % confidence values) analysis this factor was assumed to be 1.0. [ Binomial Computer). The error factor indicated by the binomial computer was approximately doubled, and a D.3.4.3 Maintenance / Test Induced LOCAs mean frequency was calculated from the binomial median , assuming a lognormal distribution. Maintecance/ test-induced LOCAs (K) involve systems ; connected to the primary wherein maintenance or test Table D.4-1 describes in detail the various events activities result in a primary coolant loss through the considered as well as the method for obtaining the event connected system. Actions such as removal of system frequencies and distributions. It should be noted that the components for maintenance / test combined with frequencies listed for the various DHR initiators are inadvertent valve misalignment are considered in given in terms of plant calendar years it is intended that the K event. Maintenance / test-induced LOCAs are of these frequencies will be corrected by factors concern for POSs 2 through 7, during which such representing the fraction of the plant calendar year spent maintenance or test activities are postulated to occur. in the POS being analyzed. These events, which depend on operation of a particular system, should be multiplied All systems connected to the primary will be considered by the fraction of time the given system operates in a for their K event potential. Other possible K events, particular POS. For this screening analysis, this factor such as maintenance / test involving the control rod drive was assumed to be 1.0. system, have been identified. The analysis for these events did not occur because the detailed human D.5 Special Events reliability analysis methodology program was completed. D.4 Decay Heat Removal Challenge Initiators Events which did not fit into the previous three categories but which present a challenge to plant safety are included under the Special Initiating Events category. D.4.1 Introduction Events identified for inclusion in this category include A group of initiators that are unique to this project are " "" E ## .""
**""""*"I""" "# I
- 8 * * ** Y "
the Decay Heat Removal (DHR) challenge initiators. study. Various sources were consulted to identify the These events involve an m. terruption or failure t events possible in the differmt plant states, including the establish decay heat removal during POSs 4 through 7. NUREG/CR-4550 volume luclear Safety Analysis They are broadly categorized into two types of events: Center Reports, several y .s of BWR operating isolation from an operating DHR system (EI); and experience described in Nuclear Power Experience, and failure of an operating DHR system (E2). All systems the information contained in the Precursor Reports. normally used for decay heat removal at various times in each POS are considered for these initiators (based on a The tollowing sections describe the various events review of Grand Gulf operating procedures). This considered in this category. Table D.5-1 describes in inclades the use of the condenser for decay heat removal deuil the events eonsidered as well as the method for after a shutdown evolution. However, this event has obtaining the event frequencies and distributions. It been included under the T2 event for POSs 2 and 3. should be noted that the frequencies listed for the various special initiators are riven in terms of plant calendar D.4.2 Identification and Estimation years. It is intended that these frequencies will be cometed by factors representing the fraction of the plant
%e majonty of the events involve the RHR system, with calendar yeai p nt in the POS. The events which much of the ata for RHRS failure taken from NSAC dw d on operation of. particular system, such as a
[ Vine et al.,1986). For several of the events described in se. , ice water system, should be nmitiplied by the this section, the frequocy has been estimated using a fraction of time the given system operates in a particular known number of events found in NSAC 88 over a POS. For this screening analysis the factor was acumed certain number of plant calendar years. A binomial to be 1.0. l NUREG/CR-6143 0-14 Vol. 2, Part 2 1
IE Screening Table D.4.1 Decay IIeat Removal (Dil.R) Challenge Initiators Plant State: Mean Frequency Description [per Calendar Year) Distribution Comments ElB ISOLATION FROM FULL POWER: N/A N/A 1 OPERATING RHR-SHUTDOWN COOLING 1: N/A 2 LOOP B 2: 2 3: 2 4: 0.1 LOGNORMAL; EF =5 3 5: 0.I 3 6: 0.1 3 7: 0.I 3 E1C ISOLATION FROM FULL POWER: N/A N/A 1 OPERATING 1: N/A 4 RWCU SYSTEM (DilR) " 2:
" 4 3:
- 4 4:
" 4 5:
4 6:
" 4 7: 0.1 LOGNORM AL; EF =5 4 EID ISOLATION FROM FULL POWER: N/A N/A 1 OPERATIN'] " ]
ADilRS 1: N/A 5 2: N/A 5 3: N/A 5 4: N/A 5 5: 0.1 LOGNORM AL; EF=5 5 6: 0.1 5 7: 0.1 5 EIT ISOLATION OF SDC FULL POWER: N/A N/A 1 COMMON SUCTION 1.INE 1: N/A 6 2: N/A 6 3: N/A 6 4: 0.1 LOGNORM AL; EF= 5 7 5: 0.I 7 6: 0.1 7 7: 0.I 7 I l EIV ISOLATION OF FULL POWER: N/A N/A 1 1: N/A 6 COMMON SUCTION 2: 6 LINE FOR ADHRS 3: 6 4:
" 6 5: 0.1 LOGNORM AL; EF=5 8 6: 0,I 8 7: 0.1 8 Vol. 2, Part 2 D-15 NUREG/CR-6143
IE Screening Table D.4.1 Decay Heat Removal (DHR) Challenge Initiators Plant State: Mean Frequency Description [per Calendar Year) Distribution Comments E2B LOSS OF OPERATING FULL POWER: N/A N/A 9 RHR SHUTDOWN SYSTEM 1: N/A 9 2: 9 3: 9 4: 0.37 LOGNORMAL; EF =5 10 5: 0.37 10 6: 0.37 10 7: 0.37 10 E2C LOSS OF OPERATING FULL POWER: N/A N/A 11 RWCU SYSTEM (DHR) 1: N/A 4 2: 4 3: 4 4: 4 5: 4 6: 4 7: 0.1 4 E2D LOSS OF OPERATING FULL POWER: N/A N/A 12 ADHRS 1: N/A 12 2: N/A
- 12 3: N/A
- 12 4: N/A
- 12 5: 0.37 LOGNORMAL; EF=5 13 6: 0.37 13 7: 0.37 13 E2T LOSS OF SDC FULL POWER: N/A N/A 1 COMMON SUCTION LINE 1: N/A 6 2: 6 3: 6 4: 0.37 LOGNORMAL; EF=5 7 5: 0.37 7 6: 0.37 7 7: 0.37 7 E2V LOSS OF COMMON FULL POWER: N/A N/A 1 SUCTION LINE FOR ADHRS 1: N/A
- 6 2: 6 3: 6 4: 6 5: 0.37 LOGNORM AL; EF=5 8 6: 0.37 8 7: 0.37 8 j NUREG/CR-6143 D-16 Vol. 2, Part 2
) - m . ..
IE Screening Table D.4.1 Comments (1) A decay heat removal (DHR) system is not normally operating in Full Power, so that events ElB (RHRS), ElC (RWCU as DHR system), and EID GDHRS) do not apply. {2) RHR Shutdown Cooling (SDC) is not normally operated in POSs 2 and 3. This event is assumed to be not applicable for these POSs. l {3} Re frequency for ElB is found using nine events identified in [ Vine et al.,1986). NSAC-88 identifies 25 events involving isolation of the RllRS, but 16 of these were pre-commercial. He study covered l g proximately 152 years of BWR plant operating years (1977-83). A mean frequency for ElB was calculated using nine events over 152 years, by first calculating a median ! value using a binomial distribution computer [ Binomial Computer] (0.065). The error factor was estimated by finding the 5 % and 95 % confidence values on the binomial computer (0.036 and 0.099), and roughly doubling that value. The mean, assuming a lognormal distribution about the median value found above, is then 0.1/yr. (4) RWCU used only in POS 7. The same numerical value for ElB is used for ElC and E2C, i {5) ADHRS is only allowed to operate in POSs 5,6, and 7 per Grand Gulf Technical Specifications [USNRC 1984). He frequency calculated for event ElB, {3), was applied to eld, since the ADHRS operates through the RHRS, and isolation of RHR would also isolate ADHRS. (6) Not normally operated in these POSs. I i (7) Assume same numerical value for EIT (E2T) as for ElB (E2B). {8) Assume same numerical value for ElV (E2V) as for ElB (E2B). l l {9) SDC is not normally operated at Full Power or in these POSs. l 1 i {l0) The calculational method for the E2B frequency is as described in [ Wright et al.,1987], using 13 events for foss of RHR due to valve problems, four events for loss or degradation of RHR due to loss of a running RHR pump, five events involving RHR her.t exchanger problems, three events for loss of RHR due to overfill or overpressurization of the RPV, (These events are considered here only for their potential to cause l an interruption in decay heat removal operations. Overpressurization is considered as a special event, see Table 4.5-1.), and seven of the nine events for loss of RHR due to planned mainten.nce. The remaining two events were pre-commercial. All events are from [ Vine et al.,1986). , {11) RWCU used in a decay heat removal capacity does not apply to Full Power. (12) Grand Gulf Technical Specifications mandate that ADHRS only be used in Modes 4 and 5 (i.e., POSs 5,6, and 7). {l3) A screening frequency for loss of ADHRS has been estimated using the E2B events, since ADHRS operates through the RHRS and has similar components. l l Vol. 2, Part 2 D-17 NUREG/CR4143
IE Screenmg D.5.2 Criticality Events critical heat flux or excessive fuel enthalpy . BNL addressed early fuel damage from reactivity insertion nree criticality events were identified for consideration. events occurring given operation with instabilities, and ney are: concluded that early fuel damage due to excessive fuel enthalpy is not of concern [ Diamond et al.,1990]. No
- T4A: Rod Withdrawal Error detailed study of all design basis accidents occurring while core instabilities are pmsent has been performed f r the off power study. However, during off power
- T4B: Refueling Accident (rod or fuel conditions, instabilities are less likely than at full power,
,;,pg,;,;,g and therefore these events have been screened from the
- T4C: Instability Event.
BNL also concluded that a particular type of reactivity All three of these were screened from the analysis, based nse n can ecgr dunng an ATWS sequence, and it on the following reasons. may not be sufficiently low to be screened from T4A, the rod withdrawal accident at power (rod drop in c nsideration [ Diamond et al.,1990]. The reactivity a BWR), is a design basis accident. Thus, for significant inserti n results fr m failure of the operator to inhibit fuel damage to occur, other failures (such as control rod (aut matic) ADS following injection of borated water pattern errors) must exist. (Rod drop during startup is fr m the SLC. If the reactor depressurized, auto ! precluded by design.) BNL ccncluded that the likelihood injection of non-borated water from LPCI or LPCS can of significant fuel damage from a rod drop event at full displace borated water and result in a reactivity excursion ; power is < IE-8/RY [ Diamond et al.,1990]. The value which can damage fuel. This issue was not specifically for off-power conditions r.hould not be higher. It is addressed in the Grand Gulf full power PRA [Drouin et concluded that this event can be screened from the al.,1989). This regulation does not address inhibiting analysis. ADS for those sequences involving successful shutdown i with SLC. ADS can actuate if vessel level is low, and T4B, the refueling accident, can be of two types. He this can occur following an ATWS. (Table A-1 of , first type involves incorrect placement of a fuel bundle in NUREG 4550 indicates that the level will drop to the top the core during refueling. This is a design basis accident of the active fuel following an ATWS even with injection I cnd does not lead to unacceptable consequences. The from SLC, CRD, and HPCS.) Since ATWS sequences second type is associated with local loading of fuel when were contributors to core damage for accidents from full more than one control blade is removed. This accident power at Grand Gulf, this iaue should be addressed for is discussed in reference [Drouin et al.,1989] which full power. ATWS events are of concern for the off concludes that it can damage fuel and that its frequency power study only in POS 1, and in this POS, power is may not be below IE-7/RY (depending on the specific limited to 15% which reduces the severity of the ATWS. characteristics of a particular plant). BNL points out that The success criteria for the ATWS in POS I are the improvements in teshnical specifications, such as same as those used in NUREG 4550 for full power, j suspending fuel loadmg when control blades are out, can hence this particular reactivity excursion is not reduce the frequency of this accident [ Diamond et al., considered. 1990]. The pertinent technical specification for Grand Gulf that allows for removal of more than one control D.5.3 Support System Events blade during refueling is # 3.9.10.2, and it requires that oil fuel loading operations be suspended unless all control Several support system initiators wire identified based on a review of the equipment requirel o function during the blades are inserted in the core (USNRC 1984]. Based on this control provided by the technical specifications, it is POSs. These include: concluded that this event can be screened from the i analysis. 1. L ss f SSW (T5A), j T4C, the flow instability event refers to operation of the 2. Loss of TBCW (T5B), core with a local high power-to-mass-flow ratio. The concern is that with the instability, should a design basis 3. Loss of PSW (T5C), event take place, the high power regions of the core can be damaged due to the occurrence of phenomena such as 4. Loss of CCW (T5D), l l NUREG/CR-6143 D-18 Vol. 2, Part 2
IE Screening
' Table D.5.1 SpecialInitiating Events Flant State: Slean Frequency Description [per Calendar Year] Distribution Comments NOTE: THE FOLLOWINO "T4" EVENTS ARE " CRITICALITY EVENTS" T4A ROD WITilDRAWAL FULL POWER: N/A N/A 1 ERROR 1: N/A
- 2 T4B REFUELING ACCIDENT 2: " "
2 i T4C INSTABILITY EVENT 3: 2 4: 2 5: 2 6: 2 7: 2 T5A LOSS OF SSW FULL POWER: N/A N/A 3 1: N/A 3 2: N/A " 3 3: N/A
- 3 ,
4: 1.8 E-2 LOGNORMAL: EF=5 4 5: 4 6: 4 7: 4 TSB LOSS OF TBCW FULL POWER: N/A N/A 3 I 1: 1,8 E-2 LOGNORM AL; EF=5 5 2: 5 3: 5 4: 5 5: 5 6: 5 7: 5 T5C LOSS OF PSW FULL POWER: N/A N/A 3 1: 1.8E-2 LOGNORM AL; EF=5 5 2: 5 ) 3: 5 4: 5 5: 5 6: 5 7: 5 T5D LOSS OF CCW FULL POWER: N/A N/A 3 1: N/A 3 2: 3 3: 3 4: 1,8 E-2 LOGNORMAL: EF=5 5 5: 5 6: 5 7: 5 Vol. 2, Part 2 D-19 NUREG/CR-6143
IE Screening Table D.5.1 Special Initiating Events Plant State: hiean Frequency Description [per Calendar Year] Distribution Comments TAB OR TDB FULL POWER: N/A N/A 3 1: N/A 3 2: N/A
- 3 3: N/A 3 4: 9E-4 OR 6E-3 LOGNORMAL; EF-5 6 5: "
6 j 6: 6 7: 6 TIA LOSS OF INSTRUMENT FULL POWER: N/A SEE "T2" 7 AIR SYSTEM 1: 0.5 TBD 8 2: 0.5 8 3: 0.5 8 4: 0.5 8 5: 0.5 8 6: 0.5 8 7: 0.5 8 TORV INADVERTENT OPEN FULL POWER: N/A SEE "T3C" 9 RELIEF VALVE 1: N/A 9 2: 9 (SHUTDOWN) " 3: 9 4: 0.1 TBD 10 5: N/A N/A 11 6: N/A 11 7: N/A 11 TIOP INADVERTENT FULL POWER: N/A N/A 12 OVERPRESSURIZATION 1: N/A 12 EVENT 2: N/A 12 3: N/A 12 4: 0.16 TBD 13 5: 0.16 13 6: N/A N/A 14 7: N/A 14 TlHP INADVERTENT FULL POWER: See T3A N/A 15 OVERPRESSURIZATION 1: See T3A 15 VIA SPURIOUS HPCS 2: 15 ACTUATION 3: 15 4: IE-2 TBD 16 5: IE-2 TBD 16 6: N/A N/A 14 7: N/A 14 NUREG/CR-6143 D-20 Vol. 2 Part 2
IE Screening Table D.5.1 Special Initiating Events i Plant State: Mean Frequency ' l I Description [per Calendar Year] Distribution Comments TIOF INADVERTENT FULL POWER: N/A N/A 17 OVERFILL VIA LPCS OR 1: N/A 17 LPCI 2: 17 3: 17 4: 4E-2 TBD 18 5: 4E-2 TBD 18 6: N/A N/A 14 7: 14 TLM LOSS OF MAKEUP FULL POWER: See T3B N/A 19 1: N/A 19 2: 19 3: 19 4: 0.49 TBD 20 5: 0.49 20 6: 0.49 20 7: N/A N/A 21 l l l I i l I Vol. 2, Part 2 D-21 NUREG/CR-6143
IE Screening Table D.5.1 Comments {1} The Rod Withdrawal Error event for Full Power was included in the "T3A" frequency in Table 3.1-1. This is EPRI event number 27, Rod Withdraw at Power. (2) See Section D.5.2 forjustification for excluding these events. {3} System not normally used during these POSs or was excluded from the Full Power analysis. (4) NUREG-1275 Vol. 3 [ Lam et al.,1988] gives a value of 1.8E-2 for the frequency ofloss of service water. This i value was assumed to be appropriate for this screening study. {5} See note (4}. i l {6} TAB estimated using hourly failure rate for an AC Bus. TDB used TDC value given in [Drouin et al.,1989]. (7) For Full Power [Drouin et al.,1989), Loss of Instrument Air (TIA) was considered to result in the same plant response as transient category T2, Loss of PCS, and was thus considered part of this transient category. {8} Loss ofInstrument Air applies to all POSs. The frequency is based on two events at Grand Gulf over a four year period. (9) The Inadvertent Open Relief Valve (IORV) event, as it applies to causing a reactor SCRAM, is considered in event T3C (see Table D.2-1). (10} Conservatively assumed same value as for transient from inadvertent Open Relief Valve from [Drouin et al., 1989] Vol.1, Rev.1, page 8-20. {ll} Not applicable. Vessel is depressurized. I {l2} Not applicable. System pressure can be as high as normal (approx.1000 psi). 1 (13} Frequency estimated using value for EPRI category 20. (14} Vessel head is off, cannot pressurize, {l5} Included in T3A. (16} Frequency estimated using value for EPRI category 33. (17} Low pressure systems cannot overpressurize the primary. {18} Frequency estimated by multiplying the EPRI category 33 value by four. ' {l9} Included in T3B. {20} Frequency estimated using value for EPRI category 24. (21} Makeup can be off in POS 7. I NUREG/CR-6143 D-22 Vol. 2. Part 2 l
- - - - --_______________-________-_____\
IE Screening
- 5. Loss of IE AC Bus B (TAB),
- 6. less of IE DC Bus B (TDB), and
- 7. Loss ofIA (TIA).
'Ibe methods for quantifying these events are described in Table D.51 D.5.4 Other Events in addition to the events identified above, several other events were identified that could lead to problems if unmitigated. These include:
- 1. Inadvertent Open Relief Valve at Shutdown (TORV),
- 2. Inadvertent Overpressurization (makeup greater than letdown) (TIOP),
- 3. Inadvertent Overpressurization via Suprious IIPCS Actuation (TillP),
- 4. Inadvertent Overfill via LPCI or LPCS (TIOF),
and
- 5. less of Makeup (TLM).
The methods for quantifying these events are described in Table D.51. i I 1 l Vol. 2 Part 2 D 23 NUREG/CR-6143
IE Screening References for Appendix D [Drouin et al.,1989] M.T. Drouin et al.," Analysis [ Vine et al.,1986] G. Vine et al., " Residual Heat of Core Damage Frequency: Removal Experience Review Grand Gulf, Unit 1; Internal and Safety Analysis: Boiling Events,", NUREGICR-4550, Water Recctors," NSAC-88, SAND 86-2084, Vol. 6. Rev. March 1986. '
- l. Part 1, September 1989.
[ Wheeler et al,1989] T. A. Wheeler et al., [ Diamond et al.,1990] D.J. Diamond et al., ' Analysis of Core Damage
" Reactivity Accidents: A Frequency From Internal Reassessment of the Design- Events: Expert Judgment Basis Events," Elicitation,'
NUREG/CR-5368, BNL- NUREG/CR-4550. I NUREG- $2198, September SAND 86-2084, Vol. 2, April 1989. 1989. [Mackowiak et al.,1985] D.P. Mackowiak et al., [ Whitehead et al.,1991] D. W. Whitehead, J. L.
' Development of Transient Darby, B. D. Staple, B.
Initiating Event Frequencies Walsh, T. M. Hake, and T. for Use in Probabilistic Risk D. Brown, "BWR low Power Assessments," NUR EG/CR- and Shutdown Accident 3862. EGG-2323, May 1985. Frequencie Project, Phase 1 - Coarse Screening Analysis", l [ Booth,1988] H. R. Booth, " Analysis of Vol.1, Draft Letter Repon, l Refueling Incidents in Nuclear Sandia National laboratories , l Power Plants," NSAC-129, and Science and Engineering I December 1988. Associates, Inc., November l 23,1991 update, (Available at ! [Muench,1964] J.O. Muench,
- Cumulative the USNRC Public Document Binomial Distribution Room).
Computer,'Sandia Corporation, October 1964. (USNRC 1984] USNRC, " Technical Specifications, Grand Gulf
;Ericson, ed.,1990] D. M. Ericson, ed., Nuclear Station Unit No.1,"
" Analysis of Core Damage Docket No. 50-416, Appendix Frequency: Internal Events "A" to License No. NPF-29, Methodology," NUREG 0934, October, NUREG/CR-4550, 1984.
SAND 86-2084. Vol.1, Rev. [ 1. January 1990. [ Lam et al.,19881 P. Lam et al., ' Operating l Experience Feedback Report - [ Wright et al.,1987] R.E. Wright et al., " Pipe Service Water System Break Frequency Estimation Failures and Degradation," for Nuclear Power Plants," NUREG 1275, Vol. 3, NUREGICR-4407, November 1988. EGO 2421, May 1987. NUREG/CR-6143 D-24 Vol. 2, Past 2
Appendix E. Updated Success Criteria This Appendix is the Success Criteria used in the In terms of functions, the tree is very simple. Three screenmg study [ Whitehead et al.,1991], updated for the functions must be successfully provided to prevent core detailed study of POS 5. The update was performed for damage: (1) reactivity control to ensure that the core is POS 5, but if the update affected other POSs, then the not producing heat in excess of decay heat, (2) level success criteria for these POSs were also updated. control to ensure that the core is maintained " covered" with water, and (3) energy removal to remove energy This appendix provides the success criteria for POS 4,5, from the water covering the core. (The situation 6, and 7. (The success criteria for POS 1,2, and 3 are following r large LOCA in a recirculation line, for the NUREG 4550 success criteria for full power and are which only two thirds of the core is covered with water, not reproduced here.) is a special case.) The specific combinations of systems which can fulfill these three functions depend on the POS E.1 Summary Description of the and the specific accident initiating event. A discussion f each fundion foHows, addressing mecess uituia Success Criteria for the S) stems , which maintam system pressure low enough so that vs POSs: Low Pressure isolation of RilR/SDC is not required. Options for Conditions emling the core considering isolation of RHR/SDC and pressurization of the system are subsequently discussed. Here are two basic methods of cooling the core: Eunction 1: Reactivity Control (1) Injecting subcooled or saturated water so that Shutdown margin at Grand Gulf can be maintained with the fluid exiting the vessel after being heated by the rods alone all the way down to refueling conditions decay heat is subcooled or is a two phase without the need for boron injection. The SLC is a mixture of low quality. backup for the rods. Since in POS 4,5,6, and 7 the i rods are fully inserted, it is considered extremely (2) Injecting subcooled or saturated water in small improbable that loss of reactivity control can occur. quantities and steaming out the vessel. Function 2: Level Control Method (1) is the normal way of cooling the core. Mett.od (2) must be verified to work in the limiting case The core can be cooled as long as the top of the core is of natural convection of boiling saturated water at 15 " covered" with water, assuming that natural convection psia. 't must be verified that dryout due to flooding does of boiling saturated water does not lead to dryout (as not occur with 1% decay heat at 15 psia. NUREG 4550 discussed earlier). " Covered" means that the collapsed assumed that method (2) works after trip from full level of the water is above the top of the core. A design power. However, in this case, the dryout heat flux will has s large LOCA in a recirculat on suction line leads to be higher (even though the decay heat is also higher) due uncovery of about one third of the core. Licensing to a higher density for saturated vapor at the higher analyses verify that for LOCAs from full power, the top pressure (dryout heat flux is proportional to the square third can be cooled by steam. The situation for off root of the vapor density according to the Wallis flooding power is different, as discussed in the following criteria). Using Lahey and Moody, it is conservatively description of function 3, Energy Removal. estimated that the dryout heat flux for flooding is 8.5E+3 Bru/hr/ft/ft at 15 psia [ Lahey and Moody, Certain options for energy removal which cool liquid in 1984]. The UFSAR, table 4.4-1, specifies a maximum the downcomer region (such as RHR/DHR) require that full power heat flux of 3.62E+5 Bru/hr/ft/ft and 1% of the measured level, measured in the downcomer, be this value is less than the estimated dryout heat flux sufficiently high for adequate recirculation between the [SERI,1992]. Thus, method (2) should prevent core core and downcomer regions. This required measured damage. The success criteria used in this study assume level is significantly higher than the top of the core. that steaming the core at low pressure does not lead t The actual level of concern is the level in the core region flooding induced dryout. which must be above the minimum steam separator The functional event tree for POS 4,5,6 and 7 is shown in Figure E.1.1. Vol. 2, Part 2 B-1 NUREG/CR-6143
4 2: w C 1 Q R x - 9. E b E-8 i IE RC LC ER SEQ # OUTCOME FUNCTIONAL EVENT TREE E: PREEXISTNG KNOWN UNAVALABLITES APO ACCOENT NTRTOR '
- RC
- REACTMTY CONTROL i m LC: LEVEL CONTROL
' A ER: EtERGY REMOVAL ! i 1 OK 1 2 CD 3 CD 4 NA-FOR-4 - 1 0
.N
$ Figure E.1-1. Functional Event Tree for Plant Operational States 4,5,6, and 7
Success Criteria the downcomer. He actual core level is different from flooded, letdown and makeup can isolated. I the measured level in the downcomer due to the ! following reasons: For LOCA situations, level control is accomplished with ECCS, SSW cross-tie, or FW (given sufficient makeup
- Re core fluid is a two phase mixture (at power); until alignment of FW can be achieved). The ECCS sources ultimately recirculate from the SP. The SSW cmss-tie and FW system provide once through cooling.
- If the recirculation pumps are on, they raise the core level with respect to the downcomer level; When level control is provided with ECCS using the SP, i and fluid exiting the vessel must not bypass containment, or even with SPMU, eventual loss of SP inventory with subsequent loss of ECCS cannot be prevented,
- Re safety-related level measurements are based on converting a differential pressure measurement Function 3: Enercy Removal made using a reference leg into an equivalent level without compensating for changes in water density ,
Enugy Removal from the core is accomplished by with temperature which causes the measured level , maintammg level control. Adequate level cotatrol depends to be different than the actual downcomer level at n the method of energy removal, low temperature conditions. (If actuallevelis above instmment zero, then actual level is less Energy Removal from fluid in the vessel must match than measured level at cold conditions. If actual level is below instrument zero, then actual level is decay heat. The methods which can be used to remove energy depend on the accident situation and the greater than measured level at cold conditions.) availability of systems in that accident as we!! as the y heat level. Five options are available to remove At shutdown, operation of the recirculation pumps is not the energy, but not every option can be used in every required if level is sufficient, since natural circulation due to the difference in density between downcomer and situation. He five options are: core fluid can remove decay heat. If the recirculation (1) Closed loop cooling of subcooled vessel water pumps are not available and the measured level is too using the RHR on SDC, the ADHRS (not low for natural recirculation, it is possible to establish available in POS 4), or the fuel pool cooling core cooling by operating both loops of RHR/SDC at system (only available in POS 7). Downcomer high flow rates [ Vine et al.,1986]. This ' Enhanced level must be sufficient for recirculation from Shutdown Cooling' method can provide mixing of the core to the downcomer region when downcomer and core water with the measured level as RHR/SDC or ADHRS is used; with forced low as a few feet below normal. The required recirculati n the mimmum all wed measured l (measured downcomer) levels at shutdown used for c,ur level is + 11.4 inches, and with natural ! success criteria are: circulation the minimum allowed measured level l is +82 inches. (Enhanced shutdown cooling I
* + 11.4 inches With forced recirculation; can be used if the measured level is no lower than two feet below the average normal
* +82 inches for natural recirculation; and measured level of +36 mehes.)
* +36 inches minus 2 feet for enhanced shutdown cooling.
(2) Recirculation of water from the SP using the (Normal measured downcomer level, when forced ECCS (HPCS, LPCS, or LPCI) with water flow out a break and/or the SRVs, or the vessel when recirculation is on, is between +36 and +40 inches. RHR/SDC isolates on measured low level 3, + 11.4 the head is removed. For sufficiently small breaks, normal makeup with CDS or CRD can inches. Forced recirculation with at least one recire match the break flow if let down is isolated, and pump provides enough head to maintain core-to. method (1) can be used. The acceptable upper downcomer recirculation down to this level.) limit on this break size depends on the driving For Non-LOCA situations, level control is accomplished pressure. To prevent loss of SP inventory, fluid by matching letdown, with RWCU, to makeup, with exiting the vessel must not bypass containment. CDS or CRD. During refueling, after the cavity is Thus, the MSIVs must be closed except when Vol. 2 Part 2 E-3 NUREG/CR-6143
Success Criteria steam line plugs are in place. not render the SP unavailable [Drouin et al.,1989]. This impodant conclusion means that option (2) can be (3) Injection of water from the SSW cross-tie or the used to cool the core with the containment failed. That FW system with water flow out a break and/or is, containment overpressurization is an effective way to the SRVs, or the vessel when the head is vent containment. The success criteria use this removed. (If SPMU or SRVs are available, conclusion. then lower containment can be flooded up to the ' maximum level specified in the EP. If SPMU The SPMU system has two functions: (1) maintain SP and the SRVs are not available, then vessel level inventory by compensating for all water entrapment is controlled. Upper containment is not flooded volumes (e.g., drywell volume below the top of the weir ; and, if necessary, the core can be steamed.) wall) [Section 6.2.7.1 of SERI,1992], and (2) lower the long term containment pressure since the heat removal (4) Steaming out a break and/or the SRVs, or the capacity of one RHR train is less than the decay heat at vessel when the head is removed, with makeup 30 minutes, the time when containment cooling is from low capacity systems such as the CRD. If assumed to be actuated in a DBA [Section 6.2.7.3.4 of necessary, other sources of makeup can be used SERI,1992]. The second function of the SPMU is not (such as SSW cross-tie) and the core steamed. required for POS 4,5,6, and 7, since the maximum decay heat is .'8 Mw and the heat removal capacity of (5) At sufficiently low decay heat levels (e.g., after one RHR train is 54 Mw [185 E+6 Bru/hr from Table refueling), letdown of hot water through the 6.2-2 of SERI,1992]. RWCU with makeup from the CDS and/or the CRD. The first function ensures that the SP level is not decreased below the minimum level required for pumps ! Options (1) and (5) require a high enough water level for NPSH while the SP is supplying water to the core and adequate forced or natural recirculation between the core water out the break is filling up the drywell. This and downcomer regions, or for enhanced shutdown function of SPMU is required for LOCAs in POS 4,5, cooling. Options (2) and (3) fill the vessel to a level 6, and 7 since, as is the case at full power, the fluid is determined by the size and location of the exit path discharged to the drywell and not to the SP. (For a (break and/or SRVs). Option (4) requires the core to be small LOCA at full power, SPMU is not required until covered with water. 30 minutes due to the relatively low amount of water , drawn from the SP by HPCS/RCIC to feed the ! Of these five options, three are once through: (3), (4), pressurized vessel [Section 6.2.7.3.1 of SERI,1992).) L and (5). Option (5) seguires no heat removal from containment. Option (3) requires heat removal from SPMU is not required to maintain SP inventory for containment in the short term only if the core is stcamed. transients in POS 4 and 5, since any use of the SP in Iflower containment is flooded, containment heat these cases is associated with the use of the SRVs which I removal is required only after the entire inventory of discharge directly to the SP. (To prevent bypass flow water is heated to saturation. outside of containment, one of two MSIVs in eacn steam line must be closed.) In POS 6 and 7, the head is off the Options (2), (4), and sometimes (3) require coniainment vesel and steam line plugs are installed. Thus, the SRVs cooling to prevent containment overpressurization. are not available, and if the SP is used for core cooling l Containment cooling can be provided by either the SPC in plant states 6 or 7, the SPMU system must be made or CS. If containment cooling is not provided, the available to refill the SP with water pumped from the SP : containment can be vented and the heat sink for these out the vessel head into the upper cavity / upper : two options is boiling to the atmosphere at 15 psia, if containment pool. , containment cooling is lost and the containment is not f vented, for these options in which energy is being added Long term makeup to the suppression pool is required if to containment, the containment pressure will rise to the containment is vented, to prevent boiloff of water to maintain saturation conditions as the SP temperature where adequate inventory for ECCS is lost. - increases. NUREG 4550 concluded that containment would overpressurize and fail before equipment The three functions of the functional event tree have been temperature limits are reached (pumps, relays, and so discussed. From this disem-im =rc= criteria can be on), and that structural failure of the containment would developed. The success criteria need to be specified for NUREGICR-6143 E-4 Vol. 2 Part 2
I Success Criteria the following situations: and a water solid vessel, SRVs are required to be open to control pressure below the shutoff heads of the ECCS
- POS 4 at 38 Mw Pumps, and to allow for discharge of enthalpy. If RHR/SDC fails to auto-isolate on high pressure or low level, ne SRV is sufficient to prevent overpressurizing
- POS 4 at 6 Mw RHR/SDC piping, rated at 220 psig. However, two SRVs must be open to prevent possible overpressurizing a POS 5 at 34 Mw of ADHR piping, rated at 80 psig.)
L
- POS 5 at 6 Mw LOCAs in POS 5,6, and 7, with the primary subcooled ;
at 15 psia, are very different from LOCAs at higher ,
- POS 6 at 15 Mw pressure during the initial time period following the LOCA. No primary inventory is lost due to flashing,
- POS 6 at 6 Mw thus LOCAs in steam lines are not of concem unless they interrupt level control or energy removal. The only vessel penetrations which are located below the top of
- POS 7 at 12 Mw.
the core are the recirculation connections, and the control ; r d and instrumentation penetrations. A recirculation Both LOCAs and Transients need to be considered for these situations, line break will not completely drain the core since thejet pump riser separates the downcomer (the source for recirculati n) from the lower plenum. Instead about one A basic distinction between POS 4 and the other three third of the core would be uncevered. Similarly, a break POSs should be discussed. In POS 4 the primary in an RHR line during SDC, or diversion ofinventory to pressure is 100 psig (about one tenth the full power , the SP, cannot completely drain the core since the RHR value) and the temperature is 328 degrees F (full power c anects to a recirculation suction line. Licensmg l is 550 degrees F). For a LOCA in POS 4, the primary analyses demonstrate that for LOCAs from full power, will flash as in the full power case, but the blowdown rzte will be less due to the lower pressure. The internal the top one third of the core can be adequately cooled by steam. However, in POS 4,5,6, and 7 the core fluid ! energy of the primary water in POS 4 is about half that can be initially subcooled leading to no steam cooling of I tt full power since it is determined mainly by the the top one third of the core immediately following a temperature (32 degree F reference for zero intemal LOCA. (Vine et al.,1986 also points out the need to l energy). Thus about half of the full power energy is verify the coolability of the top 1/3 of the core with r deposited into containment following a large LOCA in POS 4. LOCAs in POS 4 are similar to LOCAs from ECCS in off-power modes.) IIPCS or LPCS should ) adequately cool the top 1/3, since they spray down over full power Instead of calculating detailed thermal hydrat;lic behavior for POS 4 LOCAs (a lengthy the top of the fuel. LPCI fills the volume outside of each fuel channel and flows over the top and down into process), we chose to use the full power LOCA success the fuel assemblies. Based on MELCOR analyses,2 of ; criteria with three modifications: (1) there is no need for 3 LPCI trains are needed to cool the top 1/3 of the core SPMU for long term containment pressure control as l at low temperature conditions. Since SSWXT and FW l discussed previously for event #3 of the functional event tree; (2) ADS is not required to allow low pressure inject into LPCI lines, for a large LOCA, the flow from l either of these two systems should be at least equal to i ECCS systems to be used since the initial pressure is that from 2 LPCI pumps. SSWXT can provide sufficient I rJready low; (3) the SRVs are required to be manually ~ flow, but FW cannot. l operated in a relief mode for small LOCAs, and for small size medium LOCAs, to prevent pressure from Vessel rupture, and failures in the control rod and rising to where the integrity of RilR/SDC components instrumentation penetrations in the bottom of the vessel cre tl.reatened during the time from when adequate level can drain the core. Vessel mpture can be screened out i for core cooling is lost and the time at which level has on low frequency. Failures of bottom penetrations were l dropped to the minimum ECCS auto-actuation setpoint. l screened from analysis in NUREO 4550. We discussed (If one SRV is opened allowing discharge of steam the potential for failure oflower vessel penetrations with ; following a small or medium LOCA, pressure will not Grand Gulf, and asked if any maintenance is performed , threaten RHR/SDC components durNg the time required ! for auto-actuation of ECCS. Following refill with ECCS during refueling which could contribute to an increased potential for such failure. Based on the results of this Vol. 2, Part 2 E-5 NUREG/CR-6143
Success Criteria discussion, we deferred examination of this event until injected. the detailed human action phase of the study, which is beyond the scope of this report. It is not por.sible to (b) The CRD flow rate is substantially less than the syphon or pump out water below the top of the core ECCS flow rate. This may not be too through any of the penetrations above the top of the core significant because the ECCS water that is not since the steam separators ensure that the pressure at the boi'ed merely flows out the break. Ilowever, top of the downcomer is that at the top of the core region mixing considerations may be important. (i.e., the steam separators act as a syphon break). We Without examining in detail the case for 1/3 verified with Grand Gulf that during refueling, no core uncovery, with steaming, and with bottom temporary lineups are used which could completely drain makeup sufficient only for inventory the core (e.g., hoses dropped to the lower plenum of the replacement, we do not know if this option will , vessel). work Also, the option of using CRD is only possible if the transient aspects of the LOCA are "Ibe same LOCA sizes as used in NUREG 4450 can be not of concern. By transient aspects, we mean used for POSs 4 through 7. A large LOCA is greater the flashing, blowdown, and rewetting aspects l than or equal to 0.4 sq ft. An intermediate LOCA is immediately following a LOCA in a pressurized l 0.007 sq ft to 0.4 sq ft. A small LOCA is less than primary. The CRD has insufficient capacity to l 0.007 sq ft. As previously discussed, for small and prevent cladding damage under these conditions. medium LOCAs SRVs must be opened to: (1) prevent Therefore, we cannot take credit for this option potential overpressurization of SDC piping (2) prevent in POS 4 (100 psig) even if the steady state system pressurization to pump shutoff heads, and (3) to situation is acceptable. We could take credit for allow for discharge of enthalpy sufficient to match decay this option in POSs 5, 6, and 7 (0 psig) if the beat. At full power, this requirement is provided by the steady state situation is acceptable since no safety function of the SRVs. In POS 4,5,6, and 7, the flashing / blowdown occurs. We decided to take pressure is low (below 135 psig, except for the special no credit for this option in POSs 5,6, and 7 Hydro condition which is discussed later) and the safety until detailed thermal hydraulic analysesjustify ; function of the SRVs (high pressure control) cannot be doing so. The only situation under which this ! used. The SRVs must be manually opened (relief option is needed is if all the ECCS injection l mode). In POS 6 and 7, the SRVs are unavailable due options fail, and even if CRD makeup is to the installation of steam line plugs, but the head is off available throughout the accident it cannot the vessel, thus providing a relief path, prevent level falling to the actuation setpoint of l ECCS due to the size of the break, and thus ! Option (2) considers the possibility that small breaks can CRD makeup is not an option for preventing the i be within the capability of the normal makeup systems. use of ECCS. l First, consider a large or medium size LOCA in the l worst kication, a recirc suction line. In the steady state, [ Note that using condensate makeup (as a backup for following blowdown and refill, the top 1/3 of the core is CRD makeup) for steaming in the steady state following not covered with water since the break is so large. (This a large or medium LOCA, should not even be is a conservative assumption for medium LOCAs.) Core considered, since condensate is supplied to the cooling is accomplished with injection of ECCS water downcomer, not the core, and thus the injected water , from above the core. In steady state it is possible that would run out the break and never reach the core.] ! injection from only the CRD, to match steaming, can ; cool the core. The CRD can supply about 240 gpm. 240 The situation for small break LOCAs is different from gpm can match decay heat if steaming is allowed. The the casejust discussed for the larger breaks. We defined situation with CRD makeup differs from the case of small break LOCAs as less than or equal to 0.007 sq ft ECCS addition in two imponant respects: in area, to be consistent with the NUREG 4550 full-power PRA. In general, a loss of inventory is not (a) CRD injection into the vessel is via the control considered to be a LOCA if it is within the capability of rod drive cooling water header through the rod the normal makeup systems. In POS 4 (100 psig), a drive seals (i.e., the water enters from the 0.007 sq ft hole discharges about 160 gpm (water bottom of the vessel). ECCS water is injected flashing, Moody model). In POS 5,6, and 7 (0 psig), a from above the core and provides for some 0.007 sq ft hole with a 100 foot head discharges about cooling of the top 1/3 of the core as it is 200 rpm (water draining through the hole). As NUREG/CR-6143 E-6 Vol. 2, Pan 2 L___-_________
Success Criteria discussed previously, the CRD can supply about 240 pressure. liowever, if the system pressurizes all the way gpm (CDS can supply even more), and normal letdown to the SRV safety setpoints, about 1000 psig, the ; via the RWCU can be isolated. Therefore, the small shutdown cooling systems will fail if they are not l break LOCA is not really a LOCA for the POS of isolated. I concern. We continue to call it a small break LOCA since it is treated so at full power, and we use success in POS 4, the high pressure auto-isolation for RilR/SDC criteria for a small break LOCA tree which accounts for (135 psig) is active, and the low level 3 auto-isolation for i the possibility ofisolation ofletdown/ir. creased makeup. Rif R/SDC is active. In POS 5, the high pressure auto- j isolation for Rif R/SDC (135 psig) is active, and the low ! Steaming through one open SRV is adequate to prevent level 3 auto-isolation for RHR/SDC is active. (in the < overpressurization of RilR/SDC and ADilR piping and screening study [ Whitehead et al.,1991], it was l components. assumed that in POS 5 auto-isolation of RIIR/SDC on high pressure was inactive, based on information An interfacing systems LOCA, V sequence due to received during the plant visit in January 1991. overpressurization of low pressure piping, can only occur During a subsequent visit to the site in June,1992, we in POSs 4 and 5 (non hydro condition) if a prior failure were informed that auto-isolation of RilR/SDC is pressurizes the primary, because the typical pressure in active in cold shutdown, POS 5.) POS 4 is 100 psig (unless a pressurization transient 1 occurs) which is below the 135 psig permissive pressure If the primary pressurizes and shutdown cooling is not for RHR SDC initiation. Overpressurization of low isolated on high pressure (either automatically or pressure piping is not an initiating event in POSs 4 and 5 manually), we assume that an mterfaemg systems LOCA (excluding the Hydro condition). Overpressurization of outside containment occurs. This LOCA can be isolated low pressure piping cannot occur in POS 6 and 7 since by the auto-isolation of shutdown cooling on low level 3, the vessel head is off which prevents pressurization of in which case the isolated LOCA becomes a transient. the primary. If the interfacing LOCA is not isolated, ECCS is lost since SP inventory cannot be maintained even with The likelihood of a pipe break LOCA in POSs 4,5,6 SPMU. In this case, we assume core melt since the l and 7 is lower than at full power due to the lower LOCA drains the top third cf the core and, without driving pressure (135 psig at most - excluding the ECCS, a partially drained core cannot be cooled. (It is flydro condition - as compared to 1000 psig at full possible to flood with SSWXT, but this leads to flomling power). For a LOCA to occur, a critical crack must of equipment in the auxiliary building. We have exist which can propagate under the driving pressure. conservatively assumed that timxling with SSWXT The lower the pressure, the greater the required size of cannot mitigate the RHR/SDC LOCA outside the critical crack. containment.) If shutdown cooling is isolated either on high pressure or E,2 Pressurization Concerns and low level, the system can pressurize up to the SRV safety setpoints and thnon: can be cooled by Meanung Success Criteria at Rated Pressure on the SRVs. (For operation in the safety mode, the SRVs do not require any support systems and do not Pressure control could be lost in POS 4 and 5. For require operator action. As discussed previously, for example, if cooling is lost and SRVs cannot be opened to m ration of the SRVs in the relief mode at low pressure, relieve p essure, the system pressurizes along the operator action. de power, and control air are required.) saturation line. Pressurization is not of concern m POS Steaming can be accomplished with one SRV cycling at 6 and 7, since the vessel head is off. its safety setpoint, and with makeup water from IIPCS or CRD. (LPCS, LPCI, and CDS -- without feedpumps - If pressure rises too high, and the shutdown cooling cannot in#ct at 1000 psig.) cystem is not isolated, the piping / components in the RHR/SDC or ADif R systems could rupture, leading to a During hydro testing in POS 5 coming up from a LOCA cuiside containment. The pressure rating of the refueling outage, the 200 degrees F subcooled water is RHR/SDC is 220 psig, and the pressure rating of the presurized to about 1000 psig. The low pressure SDC ADHR is 80 psig. Failure is not expected unless system system is isolated, and pressure protection is provided by pressure is about a factor of two greater than rated tt$e SRVs in the safety mode. Vol. 2, Part 2 E-7 NUREGICR-6143
Success Criteria E.3 Success Criteria An example of consideration (3) is as follows. Given a transient in POS 5 to be mitigated by pumping water Table E.1-1 thmugh E.5-4 presents the detailed success fr m the SP to the vessel and retuming the heated water criteria for POS 4,5,6 and 7. These success criteria to the SP via opening SRVs, SP cooling with the SPC or are based on the previous discussions. Hree CS systems is not needed until the SP water increases in considerations affect the application of these success temperature by at least 80 degrees F (100 to 180 degrees criteria: (1) Systems unavailabilities as allowed by tech F). At low decay heat levels, this requires a long time. specs. (2) Whether or not procedures are in place for The FSAR Table 1.3-4 specifies the SP inventory as every proposed option. (3) Re time available for 136,000 cubic feet. At an initial decay heat level of 38 instituting systems operations which can be substantial Mw it w uld take about 6 hours to heat the SP by 80 considering the low decay heat levels present. degrees F. At an initial decay heat level of 6 Mw, it would take about 32 hours to heat the SP by 80 degrees An example of consideration (1) is as follows. Given a F. Such long times available for operator action are large LOCA in POS 5, portions of ECCS are required to considered in the detailed analysis, be operable per tech spec 3.5.2, but the SPMU can be inoperable per tech spec 3.6.3.4. The success criteria require SPMU when ECCS pulls from the SP to pievent depleting the SP inventory (see earlier discussion on SPMU). Rus, if SPMU is unavailable, ECCS injection l from the SP following a large LOCA cannot be maintained and this option for core cooling is not valid. Similarly, tech spec 3.4.2.1 allows the SRVs to be r inoperable in POS 5, and without opening the SRVs, i transients cannot be mitigated by injection of water frorn any source since no relief path exists. In applying the success criteria, we modeled the availability of systems allowed unavailable by the Tech Specs based on discussions with Grand Gulf staff. For example, SPMU is taken out of service in POS 5, but two SRVs remain ; operable in POS 5. An example of consideration (2) is as follows. The success criteria allow for enhanced shutdown cooling if forced recirculation is not available and the level is , below that required for natural circulation. This option is not specified in the Grand Gulf procedures. l l NUREG/CR-6143 E-8 Vol. 2, Part 2
9- Table E.I.1 Succes Criteria for Plant Operational State (POS ) 4* u E Plant State Event Level Control Energy Ranoval 4 Large [HPCS or 2/3 LPCI' or LPCS]' and 1/2 SPMU'* {[l/2 SPC or 1/2 CS]* or [ Vent Contamment and (338 F. Saturated at 100 LOCA and 4,1/2 MSIVs' and 1/2 CVs' and ISRV' 1/2 SPMU']}' , psig) (;;t 0.4 ft')' I of Maximum decay heat is 1.0% (38MW),5 houn SSW Crosstie"' and I SRV" (Once through) after shutdown. After refueling decay heat is 0.16% (6MW),30 days after shutdown. Medium [HPCS or 1/3 LPCl* or LPCSl' and 1/2 SPMU'# {[1/2 SPC or 1/2 CS]' or [ Vent Containment and LOCA and 1 SRV4 sad 4,1/2 MSIVs* and 1/2 CVs' 1/2 SPMU')}' (0.007 to 2 0.4 ft ). m tp SSW crosstie'+' and 1 SRV'*" (Once through)
'O 1
Small isolate letdown and [ increase condensate / booster' Transfer to transient success criteria ' LOCA or (increase CRD and forced recirc} '] ( < 0.007 ft') ol [HPCS or 1/3 LPC1' or LPCS]' and 1/2 SPMU*" {[l/2 SPC or 1/2 CS]' or [ Vent Containment and and 1 SRVuand 4,1/2 MSIVs* and 1/2 CVs' 1/2 SPMU']}' os SSW crosstie and 1 SRV4 (Once through) E FW given temporary makeup ** and 1 SRV4 (Once through) b
?;
Q "l h. 6 1 c -
z Table E.1.1 Success Criteria for Plant Operational State (POS ) # 9 n O Plant State Event W Control % Renneval k 3 Transients' [ Letdown (RWCU) and Makeup (CRD
- or 1/2 RHR on SDC' with SSW heat sink' Condensate / Booster')] or alternate source of makeup" E
MM SDC' 2/2 RHR on SDC* with SSW heat sink' E j i SRV iand 4,1/2 MSIVs* and [HPCS or 1/3 {[I/2 SPC or 1/2 CS]doJVent containment and LPCl* or LPCS]' I/2 SPMU*]}' E ,' I SRV 8and [SSW" crosstie or FW given (Once through) l rp temporary makeup'*] o l E i [CRD' and/or Condensate / Boosteri j and 1 SRV ([l/2 SPC or I/2 CS]* oIIVent containment and (steaming)M i/2 SPMU*]}' E ((CRD* and/or Condensate / Booster'j and RWCU (Once through) (360 gpm)'"}" E Isolation of RHR/SDC and 1 SRV/ Safety and {[I/2 SPC or I/2 CS]* oJVent containment and {[HPCS and 4.1/2 MSIVs*] or CRD}' 1/2 SPMU*]}'if HPCS used I N
*Q l b
, a r,. , . , , , . - ,--m--s,,~~,sv,e- ,e+ ,
+v >,-e-- e,~-,w w - e. m, w-m- r,. ,,w,.,,-w, ,, , , . -n- -s ,-~ ,s.e, - , , .- - - - - - , - - , , - - - < - - -- -
Success Criteria l Table E.1.1 Notes Reactivity control by fully inserted rods LPCI Trains A and B require manual re-alignment from SDC. RHR SDC operability per Tech Spec 3.4.9.2. 2/3 LPCI per MELCOR cale. SPMU required to prevent loss of SP inventory SPMU not required since maximum decay heat less than one RHR train heat removal capability SPMU required to nukeup for boitoff from SP when containment vented i
' 1 SRV required to augment flow out break and prevent pressurization for break s; 0.3 ft' Use NUREG/CR-4550 model for FW; thus, assume for small LOCAs and Transients FW can be aligned in time.
Need to quantify makeup required until FW available
- PCS not available, and Feedwater not available. SPMU to compensate for loss ofinventory not required since SRVs discharge to SP. 1 8
Condensate / Boos'er injectien may either be on standby or be smavailable. l 8 1 SRV provides for flow of hot water or steam out of vessel to SP and prevents pressurization of primary - CRD flow rate at low vessel pressure is 240 gpm max. If forced recire lost, CRD cannot raise level for natural l recire before auto isolation of RHR/SDC occurs on high pressure in POS 4 at 38 MW. l ' 240 gpm injection required. l " Maximum RWCU letdown of 360 gpm per Inadequate Decay Heat Removal Procedure Step 5.1.3.
" This method can match decey heat only after refueling when decay heat is low. j
- NUREG/CR-4550 modeled SSW crosstie and FW.
' SPC, CS, SPMU required to be operable in POS 4 per Tech Specs 3.6.3.3, 3.6.3.2, and 3.6.3.4, respectively.
SRVs required to be operable in PS 4 per Tech Spec 3.4.2.1
- ECCS and SP operability per Tech Spec 3.5.2 and 3.5.3. SSW operability per Tech Spec 3.7.1.1
' Small LOCA is within makeup capability, but CRD cannot both match break flow and raise level.
- Adequate cooling with 1/3 core uncovered evaluated with MELCOR l
' With normal level and with no recire, increased SDC provides mixing between downcomer and core. Not enough i time to establish enhanced SDC in POS 4 at 38 MW before auto isolation of RHR/SDC occurs on high pressure
- To provide adequate natural circulation, raise level with alternate sources including ECCS
' If LOCA is Main Steam Line Break outside containment, one of two MSIVs in line with break must close to prevent eventual loss of SP inventoiy and subsequent loss of ECCS from SP. Following closure of MSIV to isolate break, one SRV must open to provide relief path for ECCS fluid injection, and at least one MSIV in each steam line without the break must close to prevent bypass flow outside containment which would result in loss of SP inventory. For Feedwater Line Break outside containment, one of two check valves in the broken line must close to prevent injection from the SP from draining the SP.
" If the LOCA is a feedwater line break that is isolated,1 SRV is required for egress of injected water.
- Whenever SRVs are used in conjunction with ECCS from SP, one of two MSIVs in all four steam lines must close to prevent bypass flow outside containmem, and subsequent loss of SP inventory and loss of ECCS.
" Only with forced recirculation, can level be sufficient following small break LOCA for core 4o-downcomer recirculation if CRD is the only hource of rnakeup.
' Cooling option for pressurization to rated pressure and temperature (1000 psig,545 F). In POS 4. RHR/SDC is auto-isolated on high pressure or low level. One SRV steaming at its safety setpoint can remove energy, makeup is from either the HPCS or CRD pumps which can supply sufficient water at rated pressure.
- FW not sufficient for large LOCA since flow not equal to 2 LPCit SSWXT provides sufficient flow.
Vol. 2, Part 2 E-11 NUREG/CR-6143
2 ca c Table E.1.2 Success Criteria for Plant Opwational State (POS) 5' g E E 9 n Q Plant State Event Level Control Enenty Removal g-r g. I 5 Large [HPCS or 2/3 LPCI' or LPCS]* and 1/2 SPMU ((l/2 SPC or 1/2 CS]' or [Vmt Contam-mt and (200 F, O psig, except for LOCA and 4,l/2 MSIVs' and I SRV' and 1/2 CVs' 1/2 SPMU']}' HYDRO; 200 F,1000 psig 2 (d 0.4ft )s. during HYDRO) which SE affects level Maximum decay heat is control CRD and/or condensate booster steaming'(for (Once through) 0.9% (34MW),7 hours and/or heat unisolated feedwater line break only) after shutdown. removal
- 9E After refueling decay heat is 0.16 % (6MW),30 days Transient Success Criteda' (for isolated feedwster Transient Suaess Criteria after shutdown line breaks only)
SE m SSW Crosstie and 1 SRV' (Once through) b er CRD makeup (steun out break)' ((l/2 SPC or 1/2 CS]' or [ Vent Contamment and I/2 SPMUS]}' 2 .N
- Q b
o
i
%< hhie E.1.2 Succes Criteria for Plant Operational State (POS) 5' i ." '
m Plant State Event Level Contal F===3y Raneral d Medium [HPCS or 1/3 LPCi or LPCS]* and 1/2 SPMU*" ([1/2 SPC or 1/2 CS]'or [ Vent Centsannet and LOCA and 1 SRV* and 4. If2 MSIVs' and 1/2 CVs' 1/2 SPMU']}' (0.007 to ; 4 0.4 ft')* g
- l which t
affects level CRD and/or condensate booster steaming' (for (Once through) I control unisolated feedwater line break only) and/or heat removal
- g Transient Success Criteria' (for isolated feedwater Transist Success Criteria l lite breaks only) i E
rp SSW crosstie
- and 1 SRVU (Once through)
U i CRD makeup and 1 SRV (steam out break and {[l/2 SPC or 1/2 CS]'or [Ve.-t Containment and SRV)' i12 SPMU']}' i i i 7 C " M k 8 A a
;c n
- 3. ,
; 6 f.
c ~ -
Z
- m Table E.1.2 Success Criteria for Plant Operational State (POS) 5*
9 O 9 Plant State Event Level Control Erwrgy Removal a
~
f, g , Small Isolate letdown and [ increase condensate booster *, Transfer to transient success criteria LOCA or { increase CRD and forced recirc} "] (<0.007 ft')' which or affects level control CRD and/or condensate booster steammg ' (for Transient Success Criteria and/or heat unisolated feedwater line break only) removal
- E Transient Success Criteria' (for isolated feedwater (Once throagh) line breaks ordy)
E tF -
*E [lIPCS or 1/3 LPCI' or LPCS]* and 1/2 SPMU ([l/2 SPC or 1/2 CS]'or [ Vent Contsnment and and 1 SRV and 4,1/2 MSIVs* and 1/2 CVs' 1/2 SPMU']}'
1 E l SSW crosstie" and 1 SRV (Once through) E FW given temporary makeup
- and 1 SRVA '
(Once through) E CRD makeup and I SRVs (steam out break and ([l/2 SPC or 1/2 CS]' or [ Vent Containment and SRV)' I/2 SPMU']}' b P
?
a 9 _ _ ___ . _ - . . . . ~ . _ , _ _ . . _ _ . _ , , _ ___. . - _ _ _ _ _ _ , _ . ~ -
P- Table E.1.2 Success Criteria for Plant Operational State (POS) 5' .N Flant State Event level Control Energy Removal Transients' [ letdown (RWCU) and Makeup (CRD or 1/2 RilR on SDC' with SSW best sink' Condensate / Booster *)] or altemate source of makeup" 91 mharw d SDC* 2/2 RHR or PDC' with SSW heat sick' 91 [ letdown (RWCU) and Makeup (CRD or I!! ADHRS' with PSW heat sink Condensate / Booster *)] or alternate source of makeup *
, L i SRV and 4,1/2 MSIVs'and [HPCS or 1/3 {[l/2 SPC or 1/2 CS]'o_riVent containment and LPCI' or LPCS]* I/2 SPM11']}'
ty G 1 SRV and [SSW" crosstie or FW given (Once through) ternporary makeup 9 gr [CRD" and/or Condensate / Booster *] and 1 SRV {[l/2 SPC or 1/2 CS]' gdVent contamment and (steaming)" l/2 SPMU']}' 91 {[CRD" and/or Condensate / Booster'] and RWCU (Once through) (360 gpm)'}' 91 Isolation of SDC and 1 SRV/ Safety and [{HPCS {[l/2 SPC or 1/2 CS]' o_rIVent containment and and 4,1/2 MSIVs'} or CRD] 1/2 SPMU']}'if HPCS used Isolation of RHR/SDC and 1 SRV/ Safety and [{HPCS ansd and [HPC [HPCS E w ia i e 6 !.- c
i Smaa Criteria Table E.1.2 Notes
- Reactivity Control by Fully inserted Rods ,
- Verify that in POS 5 lineups do not allow LOCA to drain the vessel (this cannot be mitigated); concem :s loss of !
level control and/or loss of heat removal due to LOCA LOCA in
- steam
- lines not of concern since O psig primary will not f; ash !
d LPCI Trains A and B require manual re-alignment from SDC. If ADHRS is operable, only one train of RHR on ' SDC required to be operable per Tech Spec 3.4.9.2. 2/3 LPCI per MELCOR calc. ADHR cannot handle decay heat load until 24 hrs after shutdown. SPMU required to prevent loss of SP inventory SPMU not required since maximum decay heat less than one RHR train heat removal capability 8 SPMU required to makeup for boiloff from SP when containment vented 1 SRV required to augment flow out break and prevent pressurization for break s: 0.3 ft* FW not sufficient for large LOCA since flow not equal to 2 LPCl; SSWXT provides sufficient flow. 3 ' PCS not available, and Feedwater not available. SPMU to compensate for loss of inventory not required since SRVs discharge to SP. Condensate / Booster injection may either be on standby or be unavailable 1 SRV provide for flow of hot water out of vessel to SP and prevents pressurization
CRD flow rate at low vessel pressure is 240 gpm max.
- I46 gpm injection required
' Maximum RWCU letdown of 360 gpm per Inadequate Decay Heat Removal Procedure step 5.1.3 !
P NUREG/CR-4550 modeled SSW crosstie and FW. This method can match decay heat only after refueling when decay heat is low. Either of two modes can be used. The RWCU can be used in a closed loop transferring heat to its heat exchangers, or RWCU letdown can be increased to a level such that the change in enthalpy between letdown and makeup matches decay heat.
' SPC, CS, SPMU not required to be operable in POS 5 per Tech Specs 3.6.3.3,3.6.3.2, and 3.6.3.4, respectively.
SRVs not required to be operable in POS 5 per Tech Spec 3.4.2.1
- ECCS and SP operability per Tech Specs 3.5.2 and 3.5.3. SSW operability per Tech Spec 3.7.1.1.
' Not modeled in the ET's; requires detailed thermal-hydraulic evaluation
- Small LOCA is within makeup capability, but CRD cannot both match break flow and raise level.
- Adequate cooling with 1/3 core uncovered evaluated with MELCOR.
- With normal level and with no recire, increased SDC provides mixing hetnen downcomer and core ,
' To provide adequate natural circulation, raise level with alternate sources incit ding ECCS
- Main Steam Line Break not a LOCA in POS 5 (even in Hydro, it just drains full vessel down to steam lines, no t
flashing), but Feedwater Line Break outside containment requires one of two check valves in the broken line to close, and an MSIV on each main steam line to close to prevent loss of SP ir ventory with ECCS injection. Given closure of check valve and MSIVs, one SRV must open to provide for egress of injected water (see footnote v for POS 4 success criteria). In POS 5, following feedwater line break,200 degrees F fluid does not flash, and level drops no lower than elevation of feedwater injection nozzle; no syphon concern since in a BWR the core region is
*open' to the downcomer region. Thus, in POS 5, if feedwater line break is not isolated, which renders ECCS from SP unavailable after SP level drops below ECCS suction, core is still covered and can be steamed.
' Whenever SRVs are used in conjunction with ECCS from SP, one of two MSIVs in all four steam lines must close to prevent bypass flow outside containment, and subsequent loss of SP inventory and loss of ECCS. l
" Only with forced recirculation, can level be sufficient following small break LOCA for core-to-downcomer recirculation if CRD is only source of makeup.
Cooling option if heat and pressurize to rated conditions (545 F,1000psig). RHR/SDC must be isolated; auto- I isolation either on high pressure or low level. SRV steams at safety setpoint. HPCS or CRD can provide l makeup for steaming at high pressure. I NUREG/CR-6143 E-16 Vol. 2, Part 2
E- Table E.1.3 Success Criteria for Plant Operational State (POS) 6' F m 5 Plant State Event level Control Enegy Removal 6 large [HPCS or 2/3 LPCl* or LFCS]' and 1/2 SPMU" ([l/2 SPC or I/2 CS]'or [ Vent Contamment and LOCA and I/2 CVs" l/2 SPMU']}' (140 F, O psig, Head off, (2 0.4ft')A' steam line plugs in place, which E upper cavity not filled) affects level g CRD and/or condensate booster steaming " (for (Once through)
"" * * " "* "'I' Maximum decay heat is and/or heat O.4% (15MW),4 days after rernoval' shutdown E After refueling decay heat Transient success Critena" (for isolated feedwater Transient Success Criteria is 0.16 % (6MW). 30 days line breaks only) after shutdown o_I en SSW Crosstie"*
(Once through)
'3 o_I CRD makeup (steam out break /open head)'
([1/2 SPC or 1/2 CS]' or [ Vent Containment and I/2 SPMU']}' Z C m b e H 9 9. s a y n. w = 3 - . .
! 2 , c Table E.1.3 Success Criteria for Plant Operational Siate (POS) 6* i N < m o a Plant State Event n , Q Level Control F== qty Rennovel 3-Medium d [HPCS or 1/3 LPCI or LPCS]'and I/2 ((l/2 SPC or 1/2 CS]'or (Vent Cose=====r and h-LOCA SPMU* and I/2 CVs* I/2 SPMU']}' ' (0.007 to 0.4 ft')"' 0 2 which affects level CRD and/or condensate booster steaming * (for (Once through) ! control unisolated feedwater line break only) ! and/or heat ; removal
- ol ,
Transient Success Criteria" (for isolated feedwater Transient Success Criteria line breaks only) 1 0 m SSW crosstie"* and [l/2 SPMU or control (Once Through) level *] ol CRD makeup (steam out break /open head)' ([1/2 SPC or I/2 CS]'or [ Vent Containment and 1/2 SPMU']}' 1 i o a N 1
. , . . , , _ , _ . . . , - . . - . . . . . _ , _ . . . . . _ _ . . . - . - - - . . . . . . . . . . _ . _ _,. -,._,, . . . _ _ _ , . . . , _ . . _ . _ . - ,..__ _ , . - _ . _ . _ . . . . . . _ _ _ , _ . . - . _ _ . _ _ _ =
e Table E.1.3 Success Criteria for Plant Operational State (POS) 6' e E Plant State Event Level Contml Fr gy Ranoval Small isolate letdown and [ increase CRD and/or Transfer to transient success criteria LOCA condensate / booster]* (< 0.007 ft')' which g affects level control d [1{PCS or 1/3 LPCi or LPCS]'and 1/2 {[1/2 SPC or 1/2 CS]'or [ Vent Containment and and/or heat SPMU*** and 1/2 CVs' 1/2 SPMU']}' removal
- ol CRD and/or condensate booster steaming ' (for (Once through) unisolated feedwater line break only)
E tp Transient Success Criteria" (for isolated feedwater Transient Success Criteria G line breaks only) o l SSW crosstie" and [l/2 SPMU"' or control (Once through) level'] ol FW given temporary makeup
- and [l/2 SPMU**
or control level *] (Once Through) 01 CRD makeup (steam out break /open head)' ([I/2 SPC or 1/2 CS]'or [ Vent Containment and
$ 1/2 SPMU']}' ro E $
e H 9 R b &- e
l a z c E Table E.1.3 Success Criteria for Plant Operational State (POS) 6' l E e n Plant State Event Level Contrul Energy Removal Q 6 *
% Transients' [ letdown (RWCU) and Makeup (CRD and/or 1/2 RHR on SDC' with SSW bed sink'
- Condensate / Booster *)) or long term makeup
- E 1/1 ADilRS' with PSW beat sink E
enhanced SDC' 2/2 RHR on SDC' with SSW heat sink' gr 1/2 SPMU* and [HPCS or 1/3 LPCI' or LPCSI' ((l/2 SPC or 1/2 CSl' oJVent containment and 1/2 SPMU']}' E m
@ [1/2 SPMU* or control level') and [SSW (Once through) crosstie *' or FW given temporary makeup *]
91 [CRD' and/or Condensate / Booster'] and steaming ([l/2 SPC or I/2 CS]' o_riVent containment and out the open head"and 1/2 SPMU* I/2 SPMU'j)' E {[CRD' and/or Condensate / Booster *] and RWCU (Once through) (360 gpmT}* e, m b u m- -
l i Success Criteria i Table E.1.3 Notes Reactivity Control by Fully Inserted Rods Verify that in POS 6 lineups do not allow LOCA to drain the vessel (this cannot be mitigated); concern is loss of level control and/or loss of heat removal due to LOCA LOCA in " steam
- lines not of concern since O psig primary will not flash. Assume steam line plugs are installed d
LPCI Trains A and B require manual re-alignment from SDC. If ADHRS is operable, only one train of RHR on SDC required to be operable per Tech Spec 3.9.11.2. 2/3 LPCI per MELCOR cale. ADHR can handle decay ! heat load in POS 6, since entry into POS 6 is longer than 24 hours after shutdown.
- SPMU required to prevent loss of SP inventory
' SPMU not required since maximum decay heat less than one RHR train heat removal capability 8
SPMU required to makeup for boiloff from SP when containment vented -
- FW not sufficient for large LOCA since flow not equal to 2 LPCI; SSWXT provides sufficient flow. j
' SRVs unavailable for water discharge due to presence of steam line plugs; water or condensed steam out top of open vessel retumed to SP by SPMU.
3 PCS not available, and Feedwater not available. SPMU required when SP used for injection since SRVs unavailable due to presence of steam line plugs and injected water flows out open vessel top to upper pool
- Condensate / Booster injection may either be on standby or be unavailable
' CRD flow rate at low vessel pressure is 240 gpm max.
'" 146 gpm injection required. SRVs unavailable due to presence of steam line plugs.
- Maximum RWCU letdown of 360 gpm per inadequate Decay Heat Removal Procedure step 5.1.3
- This method can match decay heat only after refueling when decay heat is low
' NUREG/CR-4550 modeled SSW crosstie and FW.
- SPC, CS, SPMU not required to be operable in POS 6 per Tech Specs 3.6.3.3, 3.6.3.2, and 3.6.3.4, respectively. SRVs not required to be operable in POS 6 per Tech Spec 3.4.2.1 ,
' ECCS and SP operability per Tech Specs 3.5.2 and 3.5.3. SSW operability per Tech Spec 3.7.1.1.
' Assume overfill of upper containment is a problem; SPMU drains upper pool to SP,
' Not modeled in the ET's; requires detailed thermal-hydraulic evaluation
" Small LOCA is within makeup capability, but CRD cannot both match break flow a . ..use level. In POS 6, level high enough for natural recire if letdown isolated early, and CRD can maintain level.
- Adequate cooling with 1/3 core uncovered evaluated with MELCOR
- 1evel sufficient for natural circulation, long term makeup to compensate for leakage.
" Main Steam Line Break not a LOCA in POS 6, since main steam line plugs in place. Feedwater Line Break LOCA outside containment requires check valve (s) to close for ECCS injection to not drain SP (as discussed for POS 5); MSIVs closure not required since steam line plugs in place; SRV not required since head is off. For Feedwater line break, core is not uncovered and can be steamed (as discused for POS 5).
- MSIV closure required whenever ECCS from SP used to not drain SP.
- With normal level and with no recire, increased SDC provides mixing between downcomer and core Vol. 2, Part 2 E-21 NUREG/CR-6143
Z c E Table E.1.4 Success Criteria for Plant Operational State (POS) 7' n
- n 9.
a g Plant State Event level Control Energy Rensoval {- 1
- 7 Large [HPCS or 2/3 LPCl* or LPCS]* and I/2 SPMU4 {[1/2 SPC or I/2 CS]' or [ Vent Conan.nneet and
-LOCA and I/2 CVs' I/2 SPMU']}3
! (100 F, O psig Head off. (2 0.4ft )u 2 steam line plugs in place, which o l upper cavity filled) affects level control CRD and/or condensate booster steaming * (for (Once Through) { Decay heat is 0.3 % and/or best unisolated feedwater line break only) t (12MW) initially- 6 days removal * * . after shutdown- decreasing of l to 0.16 % (6MW) at end of l refueling,30 days after Transient Success Criteria"(for isolated feedwater Transient Success Criteria refueling ' line breaks only) i f?' E SSW CrosstieW (Once through) ; ol i CRD makeup (steam out break /open headf , {[I/2 SPC or I/2 CS]' or [ Vent Containment and 1T2 SPMU']}3 i S 2
! u . . _ . . . _ . - _ . . _ _ _ - - . _ . . - . _ ~ . . _ _ . . _ _ _ - . . _ _ _ . _ . . . _ . _ . . . _ . . _ _ _ . _ _ . . . . . _ _ _ - . . ._. . . . . _ , . _ . _ _ _ _ . . - _ . . _ , . _ _ _ , _ . . _ . _ _ _ . . - . -
Table E.1.4 Success Criteria for Plant Operational State (POS) T F u E Plant State Event Level Control Fr gy Rar.cval Medium [HPCS or i/3 LPCl* or LPCS]' and I/2 ([l/2 SPC or i/2 CS]' or [ Vent Containment and LOCA SPMU'" and 1/2 CVs*
' 1/2 SPMU']}i (0.007 to O.4 ft')* g which affects level CRD and/or condensate booster steaming * (for (Once Through) control unisolated feedwater line break only) and/or heat removal
- o g
Transient Success Criteria' (for isolated feedwater Transient Success Criteria line breaks only) os tp SSW crosstie 8
"" (Once through)
U os CRD makeup (steam out break /open headT {[l/2 SPC or 1/2 CS]' or [ Vent Containment and I/2 SPMU']}i Z C m b e t 9 9.
$ l-
2 C Table E.1.4 S=ce=== Criteria for Plant Operationni State (POS) f E i
- e p-Q Plant State Event imel Control Emergy Remmes.: .
6 h- ! I Small isolate leklown and [ increase CRD and/or Transfer to transaeet -- criteria LOCA mwba=*alboosterf (< 0.007 , it')* which g affects level control [HPCS or 1/3 LPCI' or LPCS]* and 1/2 {[l/2 SPC or 1/2 CS]' or [ Vent Coats' _-tand and/or beat SPMU* and 1/2 CVs' 1/2 SPMtf]}3 . removal
- E CRD and/or condensate booster steaming ' (for (Once through) unisolated feedwater line break only)
E
- ip Transient Success Criteria" (for isolated feedwater Transient Success Criteria M line breaks only) i
- E i
SSW crosstie ^" (Once through) I
- E c
FW given temporary makeup"" (Once through) E CRD makeup (steam out break /open headf {[I/2 SPC or I/2 CS]' or [ Vent Containment and l/2 SPMIf]}3 b i e 7 2 tJ i _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ __ . . . . . . ~w-- --s -- v v' --em-= * ----n - t--* e -r
j R. Table E.1.4 Success Criteria for Plant Operational State (POS) f k~ Plant State Event Imel Control Nrgy Renoval Transients' ({ Letdown (RWCU) and Makeup (CRD and/or 1/2 RHR on SDC* with SSW best sink
- Condensate / Booster *)}'] or long term makeup' 9t I
j 1/1 ADHRS* with PSW heat sink oj Fuel Pool Cooling os enhanced SDC" 2/2 RHR on SDC* with SSW best sink' 9.E 1/2 SPMU'^' and [HPCS or 1/3 LPCl* or {[l/2 SPC or I/2 CS}' oriVent containment and_ , LPCS]. 1/2 SPMU']}' l tp or . [SSW crosstie ** or FW given temporary (Once through) makeup'T 3 o_r {[CRD' and/or Condensate / Booster *] and {[l/2 SPC or 1/2 CS]' oJVent containment and steaming out the open head'}= 1/2 SPMU']}' I ; (Once through) > {[CRD' and/or Condensate / Booster *] and RWCU (360 gpm)*}' y =
?;
O i b O lc 3.
& E 3 %
w E-
i Success Criteria Table E.1.4 Notes Reactivity Control by Fully Inserted Rods Verify in POS 7 lineups do not allow LOCA to drain the vessel (this cannot be mitigated); concern is loss of level control and/or loss of heat removal due to LOCA i LOCA in ' steam
- lines not of concern since O psig primary will not flash. Steam line plugs are installed in PS 7 Conservatively take decay heat as 0.3 % throughout POS 7
- LPCI Trains A and B require manual re-alignment from SDC. If ADHRS is operable, neither train of RHR on SDC is nquired to be operable per Tech Spec 3.9.11.1. 2/3 LPCI per MELCOR cale. ADHR can remove decay heat in POS 7 enice entry into POS 7 not within 24 hours from shutdown.
' SPMU required to prevent loss of SP inventory 8
ECCS not required to be operable, per Tech Spec 3.5.2, in POS 7. SSW required to be operable, per Tech Spec 3.7.1.1, in POS 7 (required operable only when RHR on SDC required operable).
- SPMU not required since .mximum decay heat less than one RHR train heat removal capability 8
SPMU required to makeup for boiloff from SP when containment vented 3 SPC, CS, SPMU not required to be operable in POS 7 per Tech Specs 3.6.3.3,3.6.3.2, and 3.6.3.1 respectively. SRVs not required to be operable in POS 7 per Tech Spec 3.4.2.1. NUREG/CR-4550 modeled SSW crosstie and FW.
' FW not sufficient for large LOCA since flow not equal to 2 LPCI; SSWXT provides sufficient flow.
SRVs unavailable for water discharge due to presence of steam line plugs; water out top of open vessel retumed to SP by SPMU.
" PCS not available and Feedwater not available. SPMU required when SP used for injection since SRVs unavailable due to presence of steam line plugs and injected water flows out open vessel top to upper pool
- Condensate / Booster injection may be either on standby or unavailable
' Letdown / makeup is normally isolated in POS 7
- CRD flow rate at low vessel pressure is 240 gpm max.
' SRVs unavailable for steaming due to presence of steam line plugs.146 gpm injection required (see footnote d) ' Maximum RWCU letdown of 360 gpm per inadequate Decay Heat Removal Procedure Step 5.1.3 ' This method can match decay heat only toward the end of refueling. Based on the assumption in footnote d, it is not to be considered
- Assume overfill of upper containment is a problem, but water flows out transfer canal to spent fuel pool
- Not modeled in the ET's; requires detailed thermal-hydraulic evaluation
- Small LOCA is within makeup capability, but CRD cannot both match break flow and raise level. In POS 7, level high enough for natural recire if letdown isolated early, and CRD can maintain level.
- Adequate cooling with 1/3 core uncovered evaluated with MELCOR.
' Level sufficient for natural circulation, long term makeup to compensate for leakage
- Main Steam Line Break not a LOCA in POS 7, since main steam line plugs in place. Feedwater Line Break LOCA outside containment requires check valve (s) to close for ECCS injection to not drain SP (as discussed for POS 5); MSIVs closure not required since steam line plugs in place; SRV not required since head is off. For !
Feedwater line break, core is not uncovered and can be steamed (as discused for POS 5).
" With normal level and with no recire, increased SDC provides mixing between downcomer and core ,
NUREGICR-6143 E-26 Vol. 2, Part 2 ;
Success Criteria References for Appendix E i [ Whitehead et al.,1991] D. W. Whitehead, J. L. Darby, B. D. Staple, B. Walsh, T. M. Hake, and T. i D. Brown, "BWR law Power and Shutdown Accident ; Frequerries Project, Phase 1 - Coarse Screening Analysis," - Vol.1, Diaft letter Rerjort, l Sandia Natio,wl Lak,ratories and Science -4 T.:.ngineering l Associates, Inc., November 23,1991 update, (Available at ' the USNRC Public Document ; Room). i [Iahey and Moody,1984] R. T. Lahey, Jr, and F. J. Moody, "The 'Ihermal-Hydraulics of a Boiling Water Nuclear Reactor." American Nuclear Society,1984. , [SERI,1992] System Energy Resources, Inc.," Grand Gulf Updated , Final Safety Analysis Report," 1992 [ Vine et al.,1986] G. Vine, et al., ' Residual Heat Removal Experience Review and Safety Analysis: Boiling Water Reactors," l Nuclear Safety Analysis Center, NSAC-88, March, I 1986. l [Drouin et al.,1989] M. T. Drouin et al., i
" Analysis of Core Damage i Frequency: Grand Gulf, Unit I 1 Internal Events."
NUREG/CR-4550, SAND 86-2084, Vol. 6, Rev.1, Part 1, September 1989. 1
- I I
l E-27 NUREG/CR-6143 1 1
J m --, m --J $k-aw.-6. %$, -- L 3- -a J 8A--- Amga~~->+A. Ae., a 4 -. _,,,. e e 1 z t I P f I I s I i 1 1 4 D s P 5 t t f e L P D b I b I 1 l l , h l l 1 I l l , a .._.-,,. , - , ., - - . - . . . -- .- --. - . , . , , . - - . - -. , ,, . --
i i Appendix F. Supporting Calculations This Appendix summarizes calculations performed to Recirculation support the success criteria and event tree development for the detailed analysis of POS 5. (9) Heat Removal Capability of ADHR at 200 F Some of the calculations summarized were performed to (10) Heat Removal Capability of FPCCU at 200 F. support the earlier screening study [ Whitehead et al., i 1991], and they are s!so described in this Appendix. The results of these calculations are given in Table F.2-
- 1. The decay heat was determined by a curve fit to that l The actual calculations which are described in this given in the NRC Standard Review Plan [USNRC, Appendix are maintained in project files. To facilitate 1987]. For times ofinterest for POSs 4,5,6, and 7 [5 cross referencing of the information in this Appendix to to 720 hours] the fit is:
the actual calculations, the information in this Appendix is referenced by calculation number. In(DH,) = -0.368 In(t,) + 0.593 F.1 Calculation Files where DH, is decay heat in per cent of full power and t,is time after shutdown in hours. Table F.1-1 summarizes the calculations performed. A Based on information received during a visit to Grand brief summary of each calculation that is active is Gulf [ Plant Visit,1991], appropriate conservative times, provided in the following discussions. after reactor shutdown, for entry into the POSs are as f " ** F.2 Scoping Calculations To understand the basic characteristics of POSs 4,5,6, and 7, various scoping calculations were performed. POS 5,7 hours Based on the results of these scoping calculations, and the development of the event trees, more detailed POS 6. 4 days calculations were subsequently performed, as necessary. F.2.1 Calculation #2 Heatup After Refueling Outage,30 days. Calculation 90-492-01-A:2, "Thennodynamics Cales for Grand Gulf", documents scoping calculations perfonned F.2.2 Calculation #3 for POS 4,5,6, and 7. The following topics were cddressed: Calculation 90-492-01-A:3, " Miscellaneous Thermodynamics Cales for Grand Gulf", documents (1) Decay Heat additional scoping ar.alyses. the topics addressed were: (2) Injection to Remove Decay Heat without (1) Capacity of I SRV in Safety Mode at Rated Steanung Pressure (3) Injection to Remove Decay Heal with Steamin8 (2) Capacity of I SRV in Relief Mode at 100 psig (Steam) (4) Heat Vessel Water to Saturation (3) Capacity of 1 SRV in Relief Mode at 200 psig (5) Boil Off Vessel Water to Top of Fuel (Steam) (6) Overheat Suppression Pool (4) Capacity of 1 SRV Passing Water at 100 pssg i and 200 psig l (7) Drain Vessel to Top of Core (5) Loss through Small LOCA in POS 4 (8) Pressurize to 200 psig after Loss of Vol. 2. Pan 2 F-1 NUREG/CR-6143 1
I. Trble F.1.1 Calculations Performed *
]
5 k Calculation Name and Number Purpose of Calculation Status of Cale=I=eia=
$
- Grand Gulf Shutdown 24 Hour Success Perform Scopmg Thermalhydraulic Calculabons SuperW by Calculatma 90-492-01-A:2 based i
Criteria", 90-492-01-A:1 for POSs 4,5,6, and 7 on more accurate informahon reneived dunng 1/91 Site Visit (Plant Visit,1/91) i
- Thermodynamics Cales for Grand Gulf *,90- Perform Scoping Thermalhydraulic Calculations Active k.
) 492-01-A:2 for POSs 4,5,6, and 7 !
" Miscellaneous Tbuciyuamics Calculations Expand Calc 90-492-01-A:2 Active
+ for Grand Gulf *,90-492-01-A:3 j
- Multiple Initiators for GG Shutdown *,90-492- Perform Screening Search for Multiple Initiating Active, but Updated for POS 5 by Calc 90-492-01-A:4 Events of Potential Importance for POSs 4,5, Ol-A;14 6, and 7 i 3
- " Relief Capabilities at Grand Gulf',90-492 Calculate Relief Capabilities for SRV and Vent Active ;
I A:4.1 Line, Calculate Pressures for ECCS Water Solid l Cases (ECCS pumps and I or 2 SRVs)
*!evels for Grand Gulf', 90-492-01-A:5 Determine Actual vs. Measured Level, Levels Active i
.n required for Shutdown Cooling b "SRVs for Small/ Medium LOCAs*,90-492- Determine Need for SRV for -w LOCA in Active, levels Recalculated with Calc 90-492-OI-A:6 POS4 Ol-A:19
*Iess of ECCS due to less of SP",90-492 Calculate Conditions under which SP Inventory Active A:7 is Insufficient for ECCS ;
" Containment Flooded or Vented *, 90-492 Estimate Time to Boil Off SP Inventory to lose Active
, A:8 ECCS if no Heat Removal, Estimate Time for i Containment Overpressure if Flooded with no j Heat Removal I
- Restore Makeup for Recirculation *,90-492 Estimate Time Available to Restore Makeup Active A:9 given No Makeup, Letdown Isolated, Nominal leakage
! *l CRD Pump for POS 5*,90-492-01-A:10 Calculate Effectiveness of I CRD Pump for Active, levels Recalculated with Calc 90-492-Restoring level, and for Matching Steaming in 01-A:19 POS5 9 g SDC Relief Valves for POS 4 and 5*,90-492- Calculate Ability of Relief Valves in RHR/SDC Active, Levels Recalculated with Calc 90492-01-A:11 to Prevent Overpressurizing RHR and ADHR 01-A:19 { q Components E < tJ _ _. . . . ___ . - - . _ - ~ - - . ~ . _ . , . __ . _ . . - ~ _ _ . . ~ . _ _ _ . . _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _
{ w Table F.1.1 Calculations Performed l *t Calculation Name and Number Purpose of Calculation Status of Calculation E w " Time for Operator Actions POS SH Conservatively Estimate Times Available for Superseded by Calculation 90-492-01-A:16 Transients," 90-492-01-A:12 Operator Actions for Operator Events on Event Trees "Overpressurizatiori of ADHR in POS SH",90- Calculate Time to Overpressurize ADHR in Active, levels Recalculated with Calc 90 492-492-01-A:13 POS5 01-A:19
- Multiple Initiators for POS SH",90-492 Perform Screening Search for Multiple Initiators Superseded by Calculation 90 492-01-A:19 A:14 in POS 5
- Time for Operator Actions POS 5, Complete Conservative Estimates for Operator Superseded by Calculation 90-492-01-A:16 Completion",90492-01-A:15 Action Times Begun in Calculation 90-492 A:12
" Update: Time for Operator Actions POS 5*, Conservatively Estinste Times Available for Active 90-492-01-A:16 Operator Actions for Opator Events on Event Trees "SRVs for Small/ Medium LOCAs in POS 5*, Determine Need for SR'l eor Small LOCA in Active, levels Recalculated with Calc 90-492-y 90-492-01-A:17 POS5 01-A:19 0
- Multiple Initiators for POS 5 (Revised)*,90- Update Calculation 90 492-01-A:14 to Reflect Active 492-01-A:18 Final POS 5 Initiating Event Frequencies
- Energy Balances Update *, 90-492-01-A:19 Check on All Previous Energy Balances, include Active Calculation of Levels Accounting for Swell
*SGTS Filter Overbeating Scoping Study *,90- Estimate Temperatures of SGTS Filters Draft 492-01-A: DRAFT following Core Meltdown
" Flooding Induced Dryout*,90-492-01-A:22 Document Conclusion that Flooding Does Not Active Occur at 0 psig E
m r z a C E' b o D 8 Ir 38 E 6 g-e ii
r to z Tchte F.2.1. Results of Initial Thermal Hydraulic Calculatiom for Screening Study m e t-Boiloff to Drain to Top Prinsense to Ability of Alulity of h Itant Decay Rennere Remaeve fleet Vessel Top of Cere* Overbeet Suppression of Core 200 psig" ADilRS se 77CCU to k Ileet Decay llent thcay lleet Water to h State Pool Renneve Decay Remmere { g without with Seteratinn lleet Dersy IIent g, Steamina Stessaias o 278 gpm' O min
- 2.0 hr 15.5 hr 1.7 hr 12 min f f E 4* 38 MW 1333 gpm 5' 34 MW 2087 gpm 249 gpm* 5.4 rnia 2.6 hr 16.8 br 1.7 hr 0.8 h/ h f 6' 15 MW 921 gpm i10 rpm I.8 hr 12.0 hr 35.9 hr 3.1hr e 2HX f 88gpm 100.1hr 41.2 hr 20.7 hr e 2 HX' 2 HX f II MW 737 gpm 19.4 hr 6' 6MW 368 gpm 44 gym 3.8 hr 24.8 br 72.2 hr 3.1 he e I HX f 44 gym 30 min 13.8 hr 72.2 hr 1.7 hr 4.5 h/ 1 IlX f 5' 6MW 368 gpm 4' 6MW 368 gpm 44 gpm 0 min
- 11.7 hr 72.2 hr 1.7 hr 1.1 hr f f NOTES:
y
- Coming down from full power b ' Going up abr 30 days
*240 gpm makeup adequate to prevent core uncovery
' Saturated initially
*llead off, cannot pressuriz:
'Not available in this POS
'Results indicates 1 ADHRS HX can just match decay heat: 2HX to be sure
'ADHRS cannot remove 34 Mw; ADHRS can match decay heat at 24 hours she shutdown
' Neglecting relief through vent line
%sume water in downcomer has no e(Tect (Conservative) b a
tJ
Supporting Celcul tions (6) Loss through Small LOCA at 0 psig (POSs 5,6, in POS 4 the SP is required to be at low Water Level, 18 feet 41/12 inches. However, in POSs 5,6, and 7, and 7) the SP can be at 12 feet 8 inches, or empty if 170,000 (7) Drop in Level when SRV Opens in POS 4 at gal are available to HPCS from the CST. This 100 psig. calculation concluded that: The conclusions of this calculation are as follows: (1) In POS 4 or 5 with SP at Low Water Level: (1) 1 SRV steaming at its safety setpoint can match (a) For a LOCA inside containment, SPMU is 4 % decay heat without nukeup, and 8% decay required, heat with makeup at 100 degrees F to maintain constant level, (b) For water solid operation with SRVs returning water to the SP, no SPMU is (2) At 100 psig,1 SRV steaming in relief can match required except if long term boiloff occurs, 0.5 % decay heat without makeup, and 0.6% and decay heat with makeup at 100 degrees F to maintain constant level, (c) For a LOCA outside containment that is not isolated, adequate SP inventory can be (3) At 230 psig,1 SRV steaming in relief can match lost between 6 and 25 minutes, depending 1 % decay heat without makeup. At 200 psig, I on the number of ECCS pumps operating. SRV steaming in relief can match 1.2% decay heat with makeup at 100 degrees F to maintain (2) In POS 5 with SP at 12 feet 8 inches: constant level, (a) For a LOCA inside containment, adequate (4) When injecting with one ECCS pump at 8000 SP inventory is lost even with SPMU, and gpm: (b) For water solid operation with SRVs (a) at 100 psig,2 SRVs can provide relief (2 returning water to the SP, no SPMU is SRVs pass water at 9600 gpm), required except iflong term boiloff occurs. (b) at 200 psig ,1 SRV cannot provide relief (1 (3) In POS 5 with SP Empty and 170,000 for SRV passes water at 6700 gpm), HPCS: (5) Makeup with 2 CRD pumps at 240 gpm can (a) For a LOCA inside containment, adequate equal mass loss from small LOCA (0.007 sq ft) SP inventory is lost even with SPMU, and in POSs 4,5,6, and 7. Loss is about 160 gpm in POS 4 200 psig (flashing water), loss is about (b) For water solid operation with SRVs 200 gpm in POSs 5,6, and 7 (subcooled water, returning water to the SP, adequate SP 100 ft gravity head), and inventory cannot be maintained even with SPMU. (6) If I SRV spuriously opens in POS 4 at 100 psig, with no operator action, and assuming instant F.2.4 Calculation #8 flashing to O psig, level drops below low level 3, SDC isolation setpoint, but not below level 2 Calculation 90-492-01-A:8, " Containment Flooded or setpoint for ECCS actuation (a later calculation, Vented", addressed two issues:
# 6, performed a time dependent analysis including heat addition). (1) Time for heating flooded containment to failure pressure (taken as 70 psia) with no heat F.2.3 Calculation #7 removal, and Calculation 90-492-01 A:7, " Loss of ECCS due to Loss of SP", evaluated under what conditions the SP inventory (2) Time to boil off SP inventory to where ECCS is is inadequate for ECCS. According to the Tech Specs, lost.
Vol. 2. Part 2 F-5 NUREG/CR-6143
Supporting Calculations ne calculation concluded: that ignition of the charcoal filters may or may not occur depending on the fraction of iodine released in vapor (1) Time to heat flooded containment to 70 psia is form, the number of SGTS trains running (1 or 2), and 54 to 80 hours, depending on volume flooded. the filter peaking factors. HEPA filter ignition is unlikely. (2) Time to boil off SP inventory at 15 psia to where ECCS is lost, assuming initially saturated F.2.7 Calculation #22 water, is as follows: Calculation 90-492-01 A:22 " Flooding Induced Dryout", (a) SP at Low Water Level: documents a conservative calculation showing that at zero psig the core can be steamed. The Wallis flooding 12 hours for LOCA, criterion (in combination with an energy balance and a 18 hours for Transients mass balance) is used to calculate the maximum heat flux allowed: 8.5E+3 Bru/ht/ft'. (b) SP at 12 Feet 8 Inches: LOCA cannot be nu.tigated (see calc #7) F.3 Calculations for Multiple 3 hours for Transients. Initiators F.2.5 Calculation #9 Three calculations addressing multiple initiating events were performed. Calculation 90-492-01-A:4, "Mult? , j Calculation 90-492-01-A:9, " Restore Makeup for Initiators for GG Shutdown", addressed multiple Recirculation", estimates the time available to restore initiators for the earlier screening study. Two i makeup if makeup is lost and letdown is isolated, before calculations, 90- 192-01-A:14 " Multiple Initiators for recirculation from the' core to the downcomer is lost. POS 5H" and 90 492-01 A:18 " Multiple initiators for Two cases are of interest, forced recirculation and POS 5: Revised", addressed multiple initiators for the enhanced shutdown cooling. In either case, the time detailed study of POS 5. The latter of these two available is that for leakage to lower level from the calculations updated the analysis of the former, by using initial level (+36 inches measured or +27.5 inches revised initiating event frequencies. actual) to the low level 3 SDC isolation setpoint (+ 11.4 inches measured or +8.7 inches actual). This section provides results of the search for multiple imtiating events of potential importance at Grand Gulfin The Tech Specs allow a total leakage of 30 gpm at rated POS5. pessure. We assumed a nominal full power leakage of 10 gpm. At full power the leaking water flashes, and If every possible event subsequent to the first event is in converting 10 gpm flashing at full pressure to subcooled the PRA model, then the concept of a multiple initiating water draining from a 100 foot head of water, the event is merely one of semantics. No " multiple" initiator estimated leak rate at shutdown is about 6 gpm. His is p ssible, since every event subsequent to the first one cllows 10 hours before level drains to low level 3. is included in the mitigation model. In practice, PRAs do not include every possible event subsequent to the F.2.6 Calculation # DRAFT first event in the mitigation model. For example, randomly occurring LOCAs following a transient Calculation 90-492-01 A: DRAFT, *SGTS Filter initiating event are not considered. Thus, the concept of Overheating Scoping Study", was performed to assist * ""I'i I'P""I"'I".g event is ne f r which the events su mt to th imjial event are not in the model. Sandia personnel examining the source term for core melt in POS 6. His calculation showed that for the Many such multiple mitiating events are oflow radionuclides released into the auxiliary building, it is '9"*"CY "*I #"" ""*#" "I' ***'
.Ii"i'I*II"8
- possible that the SGTS can maintain aux building events can be analyzed to quantitatively identlfy those integrity and its filters possibly not overheat. He cn at ns ents that are numerically sigmficant, calculation was a scoping study using a filter heatup and that are not present m the ongmal model. Once model developed for the Savannah River K Reactor t nm pie imdanng eats am identified, they can be Confinement [Darby et al.,1991]. He results indicate """D* I ' *P '**"
NUREG/CR-6143 F-6 Vol. 2, Part 2
Supporting Calculations ne frequency of a multiple initiating event containing
- included as a failure during the fault exposure time n' events is the product of: everywhere in the fault trees.
(a) the frequency of the first initiating event A listing of all multiple initiating events with a frequency of greater than 104 per year is provided in Table F.3.2. (b) the probability the second initiating event There are about 450 double initiating event sequences, occurring within the fault exposure time and no triple initiating event sequences. Those multiple following the first initiating event initiating events with a frequency greater than or equal to 4 10 per year which are not already addressed by the (n) the probability the n' initiating event occurs existing models are as follows (NOTE: Not all within the fault exposure time following the first sequences of table F.3-2 greater than 10
- per year are initiating event. listed. Upon detailed examination of the model, many of these sequences were determined to already be Let T denote the fault exposure time. Let f, denote the considered):
frequency ofinitiating event i. Let Pgdenote the probability that event j occurs, given i, within time T. If EIT*H1,1.8E4 per year, event j is independent of event i, then Pg equals P,, where P,is: 1-exp(-f,T). EIV*H1,1.8E4 per year, in shorthand notation, a double event multiple initiator T!*TORV,1.5e-6 per year, can be expressed as 'ij', a triple event multiple initiator can be expressed as 'ijk', and so on, where the first EIT*TORV, 4.2E4 per year, index refers to the frequency of the first event, and the succeeding indices refer to the probability of the EIV*TORV,4.2E4 per year, and indicated initiating event over time T. Note that numerically, assuming no dependence among events: TIA*TORV,2.lE-6 per year. (3) ij g ji The calculated frequencies consider the fraction of time j that the plant is in POS 5, 0.031, but do not factor in the fractions of time that POS 5 is in HYDRO, on (2) ijk # jik # kij SDC/RHR, or on ADHR. These fractions are 0.11, 0.81, and 0.08, respectively. When these six sequences (3) ijk = ikj. are corrected for these effects, only the first one is above 104, and its frequency is 1.5E4 per year. Furthermore, When dependent effects are considered, it may be that: EIT is isolation of the SDC common suction line when using RHR, and HI (diversion of water through the SDC l (4) ijk # ikj.. system (s) to the suppression pool) cannot occur if the i common suction line is isolated. Therefore, EIT*HI is A code was written to identify and quantify all double a valid sequence only if the operators restore the and triple multiple a,mtiating events. He code is common suction line, which requires success of event MULINIT. PAS, written m TurboPascal 6.0; source code RESCS, and then the remainder of the sequence is is provided m Table F.3-1. This code eliminates user- essentially the same as the H1 sequence. Herefore, the defined illogical dependencies, and it clunmates user- impact of the multiple initiating event, EIT*Hl is to i defined combinations of multiple mitiating events for increase the frequency of the H1 initiating event by a which events subsequent to the first event are already fa tw -* considered in the' fault trees. An example of an illogical dependency is loss of offsite power followed by loss of (1 + EIT*R ESCS) main feedwater, because the event trees for loss of offsite power already account for the fact that main where RESCS is success of RESCS. Numerically, this feedwater is unava !able given loss of offsite power. An factor is equal to 1 +(0.356)*(0.9) = 1.32. cxample of a dependency already 'hard-wired" into the f: ult trees is any initial initiating event followed by loss of shutdown cooling, ifloss of shutdown cooling is Vol. 2, Part 2 F-7 NUREG/CR-6143
Supporting Calculations Table F.3.1 MULINIT. PAS Source Code i program mulinit; {scarch for multiple initiators for GG shutdown} { search for double and triple initiators} { include GG specific precedure to remove unallowed} ! { combinations per cale 492-001-A:4} { revised to include 3/18/92 initiators and) (dependencies as noted} { Turbo Pascal 6.0 J. Darby, SEA, Inc., Oct 15,1991 Version} { type basdat= record name: string!10]; freq:real end; strtype= string [10]; var outfil: text; pos,ij,n,k aryctr: integer; init: array [1. 50] of basdat; l trune ovrlap,posfrac,mulfreq:real; flag 2, flag 3,depflag: boolean; , depstr: array [1. 50] of string [20]; j procedure dep2(eventi, event 2:strtype); { remove doubles per GG logic} var events: string [20]; ctr: integer; begin depflag:= false; events: = event! + event 2; i ctr: = 0; ! while (depflag-false) and (ctr< =50) do begin ctr: = ctr+ 1; if pvents-depstr[ctr] then depflag:=true; { dependence is true} if event 2='TI' then depflag:= true {## 3/18/92 revision, since Tl is an) { event in every detailed POS5H event tree ########} end (while} , end; { procedure} procedure dep3(eventi, event 2, event 3:strtype); { remove doubles per GG logic} var eventsa,eventsb,eventsc: string [20]; ctr: integer; begin depflag:-false; eventsa: = eventI + event 2; eventsh: = eventI + event 3; eventsc: = cvent2 + event 3; NUREG/CR-6143 F-8 Vol. 2, Part 2
l Supporting Colculctions 1 l Table F.3.1 MULINIT. PAS Source Code (Continued) ctr: = 0; while (depflag = false) and (ctr < = 50) do begin ctr:= ctr + 1; , if eventsa = depstr[ctr] then depflag: = true; ) if eventsb=depstr[ctr] then depflag:=true; ) if eventsc=depstr[ctr] then depflag:= true; ) { dependence is true} j if (event 2= 'TI') or (event 3 = 'TI') then depflag: = true (### 3/18/92 change since Tl is in every POS5H detailed event tree ##} end {while} end; { procedure} begin { main program} ; assign (outfil,'mulinit.dat'); rewrite (outfil); l l depstr[1]:=' TIT 2*;depstr[2]:=' TIT 3A';depstr[3]:=' TIT 3B'; { Grand Gulf} , { specific dependencies as defined in calc 90-4p2-001-A:4) depstr[4]: = 'T1 E l C';depstr[5]: = 'T l E l D';depstr[6]: = 'Tl E2C'; depstr[7]: = 'TI E2D';depstr[ 8]: = ' TIT 5 B';depstr[9]: = ' TIT 5C'; l depstr[ 10): = 'T2T3 A';depstr[ I l ]: = 'T2T3 B';depstr[ 12): = 'T3 BT3 A'; depstr[ 13 ]: = 'T5BT5 C';depstr[ 14]: = 'T5 BTI A';depstr[ 15]: = 'TS CT5 B '; > depstr[ 16]: = 'T5 CTI A';depstr[ 17]: = 'TI AT5 B';depst r[ 18): = 'TI ATS C'; i depstr[19]: = 'T5 AElB';depstr[20): = 'T5 AE2B';depstr[21 ]: = 'T5 BT2*; depstr[22]: = 'T5 BT3 A* ;depst r[ 23]: = 'T5 BT3 B';depstr[24]: = 'T5CT5 D'; depstr[25]: = 'T5CE I D';depstr[26]: = 'T5 CE2D';depstr[27]: = ' E2VE l V'; depstr[28]: = ' E2TE IT';depstr[29]: = 'E2D El D ';depstr[ 30]: = ' E2CE 1 C'; depstr[31]: = 'E2B E l B';depstr[ 32]: = 'T5 D E I C';depstr133]: = 'T5 DE2C'; depstr[34]: = ' TAB E l B';depstr[35]: = ' TAB E2B';depstr[36]: = 'TDB E l B'; depstr[37]: = 'TDB E2B';depstr[38]: = 'TD BTAB';depstr[39]: = 'TI AT2'; depstr[40]: = 'TI AT3 A';depstr[41 ]: = 'TI AT3 B';depstr[42]: = 'TI ATLM * ; depstr[43]: = 'TI AE I C';depstr[44]: = 'TI AE2 C'; {### 3/18/92 dependencies for TRFT follow ###} depstr[45]: = 'TITRFT';depstr[46]: = 'T5BTRFT';depstr[47]: = 'T5CTRFT'; depstr[48]: = 'TS DTRFT';depstr[49]: = 'TI ATRFT'; , for aryctr:=50 to 50 do depstr[aryctr]:='xxxxxxxxxxxxx*; flag 2:= true; flag 3: = true; writeln(' enter truncation value in 1/yr, e.g.le-8');readin(trunc); writeln(' enter POS ofinterest*);readin(pos); writeln(' enter overlap time in hours');readin(ovrlap); writeln(' enter fraction of time in POS');readin(posfrac); writeln(' enter number of initiating events < =50'); readin(n); writeln(outfil);writeln(outfil,* SEARCH FOR MULTIPLE INITIATORS'); writeln(outfil);writeln(outfil); writeln(outfil,' INPUT');writeln(outfil); write (outfil,* truncation value for multiple initiator search in 1/yr is *); writeln(outfil trunc:12); writeln(outfil,'POS is # *,pos:2); writeln(outfil,'Overlep time in hours is ',ovrlap:12); Vol. 2 Part 2 F-9 NUREG/CR-6143
Supporting Calculations Table F.3.1 MULINIT. PAS Source Code (Continued) writeln(outfil,' Fraction of time spent in POS is ',posfrac:12); writeln(outfil,' Number ofinitiating events examined is ',n:3); writeln(outfil); for i:= 1 to n do begin { input} with init[i] do begin writeln('for initiator no. ',i:2,' enter name up to 10 characters'); readin(name); writeln(' enter its freq in Ilyr');readin(freq);writelc; writeln(outfil,name,' has freq 1/yr of ',freq:12); end; {with} end; (iloop} (end input} writeln(outfil);writeln(outfil); writeln(outfil,' OUTPUT');writeln(outfil); write (outfil,' List of double and triple multiple initiators '); writeln(outfil,'with freq > ',trunc:12,* per yr,'); writeln(outfil,' using ',ovrlap:12,' hours as overlap time ,and weighted by*); writeln,(outfil,posfrac:12,' the fraction of time in the selected POS.'); writeln(outfil); writeln(outfil,' DOUBLE INITI ATORS');writeln(outfil); for i:= 1 to n do begin forJ:=1 to n do begin ifi< >j then begin dep2(init[i].name,init[j].name); { search for GG specific dependencies} mul freq : = ini t[i] . freq *( 1 -ex p(-init[jl . freq *ov rlap/(24 *365.25))); {l/(24*365.25) yr/hr} mulfreq:=mulfreq*posfrac; { weight by fraction of time in POS} if (mulfreq > = trunc) and (depflag= false) then begin flag 2: = false; writeln(outfil,'freq in 1/yr of ',init[i].name,' and ',init[j].name,' is'); wri teln(out fil,mul freq: 12); writ eln(out fil); end (if mulfreq) end (ifi< >j} end (j} end; (i} if flag 2=true then writeln(outfil,'NO DOUBLE INITIATORS ABOVE TRUNCATION VALUE'); writeln(outfil,' TRIPLE INITI ATORS');writeln(outfil); : for i:= 1 to n do begin forj:= 1 to n do begin for k:= 1 to n do begin if (i < >j) and (i < > k) and (j < > k) then begin dep3(init[i].name,init[j].name,init[k].name); { search for GG sepc. dep's} mulfreq:=init[il,freq* ( 1 -e x p(-init[j ] . freq *ovrlap/(24 *365.25 ))) * ( 1 -exp(-init[k]. freq *ovrlap/(24 *365.25))); {l/(24*365.25) yr/hr} ; mulfreq:=mulfreq*posfrac; (weight by fraction of time in POS} NUREG/CR-6143 F-10 Vol. 2, Part 2
Supporting Calculations Table F.3.1 MULINIT. PAS Source Code (Continued) if (mulfreq > -trune) and (depflag- false) then begin flag 3:= false; write (outfil,'freq in 1/yr of ',init[i].name,' and ',inity].name); writeln(outfil,' and ',init[k].name,' is'); writeln(outfil,mt.lfreq:12);writeln(outfii); end {if mulfreq} end {ifi< >j} end {k) end(j) end; {i} if flag 3=,true then writeln(outfil,'NO TRIPLE INITIATORS ABOVE TRUNCATION VALUE'); close(outfil); end. l l I 1 l Vol. 2 Part 2 F-11 NUREG/CR4143 l l l
Supporting Calculations
, Table F.3.2 Multiple Initiating Events for POS 5 ,
SEARCH FOR MULTIPLE INITIATORS List of double and triple multiple initiators with freq s 1.00000E-08 per yr, using 2.40000E+ 01 hours as overlap time ,and weighted by 3.10000E-02,the INPUT fraction of time in the selected POS. truncation value for multiple initiator search in 1/yr is DOUBLE INITIATORS 1.00000E-08 ! POS is # 5 freq in I/yr of T1 and HI is 6.72990E-07 Overlap time in hours is 2.40000E + 01 Fraction of time spent in POS is 3.10000E-02 freq in 1/yr of T1 and J2 is 1.72120E-07 i Number of initiating events examined is 34 freq in 1/yr of Tl and ElB is 6.28863E-07 Tl has freq 1/yr of 1.30000E-01 A has freq 1/yr of 3.62000E-05 freq in 1/yr of T1 and EIT is 3.92603E-06 A5HY has freq 1/yr of 1.25000E-04 l 5,1 has freq 1/yr of 3.62000E-05 freq in 1/yr of T1 and ElV is 3.92603E-06 StH has freq llyr of 1.25000E-04 l S2 has freq 1/yr of 3.62000E-05 freq in 1/yr of T1 and E2B is 7.17116E-07 S2H has freq llyr of 1.25000E-04 S3 has freq 1/yr of 3.62000E-05 freq in 1/yr of T1 and E2T is 4.19253E-07 i S3H has freq 1/yr of 1.25000E-04 H1 has freq 1/yr of 6.10000E-02 l freq in 1/yr of T1 and E2V is 4.19253E-07 l J2 has freq 1/yr of 1.56000E-02 l ElB has freq 1/yr of 5.70000E-02 freq in I/yr of T1 and TS A is 2.64796E-07 ' EIC has freq 1/yr of 1.57000E-03 l EID has freq 1/yr of 5.70000E-02 freq in 1/yr of T1 and T5D is 2.64796E 07 ,- EIT has freq 1/yr of 3.56000E-01 1 ElV has freq 1/yr of 3.56000E-01 freq in 1/yr of T1 and TAB is 1.8315bE-08 E2B has freq llyr of 6.50000E-02 ] l E2C has freq l/yr of 1.57000E-03 freq in 1/yr of T1 and TDB is 6.62007E-08 E2D has freq 1/yr of 6.50000E-02 E2T has freq 1/yr of 3.80000E-02 freq in 1/yr of T1 and TIA is 1.98555E-06 E2V has freq llyr of 3.80000E-02 TSA has freq 1/yr of 2.40000E-02 freq in 1/yr of T1 and TORV is 1.54440E-06 TSB has freq 1/yr of 2.40000E-02 T5C has freq 1/yr of 2.40000E-02 freq in 1/yr of T1 and TIOP is 1.73226E-08 j T5D has freq llyr of 2.40000E-02 4 TAB has freq 1/yr of 1.66000E-03 freq in 1/yr of T1 and TlHP is 1.54467E-07 TDB has freq llyr of 6.00000E-03 TIA has freq 1/yr of 1.80000E-01 freq in 1/yr of T1 and TIOF is 2.42731E-07 TORV has freq 1/yr of 1.40000E-01 TIOP has freq 1/yr of 1.57000E-03 freq in 1/yr of T1 and TRPT is 7.94336E-07
' TIHP has freq llyr of 1.40000E-02 TIOF has freq 1/yr of 2.20000E-02 freq in 1/yr of T1 and TLM is 8.82673E-08 TRI'T has freq 1/yr of 7.20000E-02 TLM has freq 1/yr of 8.00000E 03 freq in 1/yr of H1 and J2 is 8.07638E-08 freq in 1/yr of H1 and ElB is 2.95082E-07 NUREG/CR-6143 F 12 Vol. 2, Part 2
I l l Supporting Calcule2 ions j Table F.3.2 Multiple Initiating Events for POS 5 (Continued) freq in 1/yr of H1 and EID is 2.95082E-07 freq in 1/yr of J2 and TSA is 3.17755E-08 freq in I/yr of H1 and EIT is 1.84221E-06 freq in 1/yr of J2 and TSB is 3.17755E-08 freq in 1/yr of H1 and EIV is 1.84221E-06 freq in 1/yr of J2 and T5C is 3.17755E-08 freq in 1/yr of H1 and E2B is 3.36493E-07 freq in 1/yr of J2 and TfD is 3.17755E-08 freq in 1/yr of Hi and E2D is 3.36493E-07 freq in 1/yr of J2 and TIA is 2.38266E 07 freq in 1/yr of H1 and E2T is 1.M726E-07 freq in 1/yr of J2 and TORV is 1.85328E-07 freq in 1/yr of H1 and E2V is 1.96726E-07 freq in 1/yr of J2 and TIHP is 1.85360E-08 , freq in 1/yr of Hi and T5A is 1.24251E-07 freq in 1/yr of J2 and TIOF is 2.91277E 08 freq in I/yr of H1 and TSB is 1.24251E-07 freq in 1/yr of J2 and TRPT is 9.53204E-08 freq in 1/yr of Hi and T5C is 1.24251E-07 freq in 1/yr of J2 and TLM is 1.05921E-08 freq in 1/yr of H1 and T5D is 1.24251E-07 freq in 1/yr of ElB and H1 is 2.95080E-07 freq in 1/yr of H1 and TDB is 3.10634E 08 freq in 1/yr of ElB and J2 is 7.54678E-08
)
freq in I/yr of H1 and TIA is 9.31680E-07 freq in 1/yr of ElB and EID is 2.75732E-07 { freq in 1/yr of H1 and TORV is 7.24680E-07 freq in 1/yr of ElB and EIT is 1.72141 E-06 freq in 1/yr of H1 and TIHP is 7.24805E-08 freq in 1/yr of ElB and EIV is 1.72141E-06 freq in 1/yr of H1 and TIOF is 1.13897E-07 freq in 1/yr of ElB and E2B is 3.14428E-07 freq in 1/yr of H1 and TRPT is 3.72727E-07 freq in 1/yr of ElB and E2D is 3.14428E-07 freq in 1/yr of H1 and TLM is 4.14178E-08 freq in 1/yr of ElB and E2T is 1.83826E-07 l i freq in 1/yr of J2 and H1 is 8.07588E-08 freq in 1/yr of ElB and E2V is 1.83826E-07 l freq in 1/yr of J2 and ElB is 7.54635E-08 freq in 1/yr of ElB and T5A is 1.16103E-07 freq in 1/yr of J2 and EID is 7.54635E-08 freq in 1/yr of ElB and TSB is 1.16103E-07 freq in 1/yr of J2 and EIT is 4.71123E-07 freq in 1/yr of ElB and TSC is I.16103E-07 freq in 1/yr of J2 and ElV is 4.71123E-07 freq in 1/yr of ElB and T5D is 1.16103E-07 freq in 1/yr of J2 and E2B is 8.60539E-08 freq in 1/yr of ElB and TDB is 2.90265E-08 . freq in 1/yr of J2 and E2D is 8.60539E-08 freq in 1/yr of ElB and TIA is 8.70586E 07 i freq in 1/yr of J2 and E2T is 5.03103E-08 freq in 1/yr of ElB and TORV is 6.77160E-07 freq in 1/yr of J2 and E2V is 5.03103E-08 freq in 1/yr of ElB and TIHP is 6.77277E-08 Vol. 2, Part 2 F-13 NUREG/CR-6143
Supporting Calculations Table F.3.2 Multiple Initiating Events for POS 5 (Continued) freq in 1/yr of ElB and TIOF is 1.06428E-07 freq in 1/yr of EIT and H1 is 1.84296E-06 freq in 1/yr of ElB and TRPT is 3.48286E-07 freq in 1/yr of EIT and J2 is 4.71343E-07 freq in 1/yr of ElB and TLM is 3.87018E-08 freq in 1/yr of EIT and ElB is 1.72212E-06 freq in 1/yr of E1C and EIT is 4.74143E-08 freq in 1/yr of EIT and ElC is 4.74373E.08 l freq in 1/yr of EIC and E1V is 4.74143F freq in 1/yr of EIT and eld is 1.72212E-06 freq in 1/yr of ElC and TIA is 2.39793Eh freq in 1/yr of EIT and ElV is 1.07513E-05 freq in 1/yr of ElC and TORV is 1.86516E-08 freq in 1/yr of EIT and E2B is 1.96380E-06 freq in 1/yr of E1D and H1 is 2.95080E-07 freq in 1/yr of EIT and E2C is 4.74373E-08 freq in 1/yr of eld and J2 is 7.54678E-08 1 in 1/yr of EIT and E2D is 1.96380E-06 freq in 1/yr of eld and ElB is 2.75732E-07 f req in 1/yr of EIT and E2T is 1.14811E-06 freq in 1/yr of eld and EIT is 1.72141E-06 freq in 1/yr of EIT and E2V is 1.1481IE-06 freq in 1/yr of eld and ElV is 1.72141 E-06 freq in 1/yr of EIT and T5A is 7.25134E-07 freq in 1/yr of E1D and E2B is 3.14428E-07 freq in 1/yr of EIT and TSB is 7.25134E-07 freq in 1/yr of EID and E2D is 3.14428E-07 freq in 1/yr of EIT and TSC is 7.25134E-07 freq in 1/yr of eld and E2T is 1.83826E-07 freq in 1/yr of EIT and T5D is 7.25134E-07 freq in 1/yr of eld and E2V is 1.83826E-07 freq in 1/yr of EIT and TAB is 5.01567E-08 freq in 1/yr of EID and TSA is 1.16103E-07 freq in 1/yr of EIT and TDB is 1.81288E-07 freq in 1/yr of EID and TSB is 1.16103E-07 freq in 1/yr of EIT and TIA is 5.4.'735E-06 freq in 1/yr of EID and T5C is 1.16103E-07 freq in 1/yr of EIT and TORV is 4.22928E-06 freq in 1/yr of eld and T5D is 1.16103E-07 freq in 1/yr of EIT and TIOP is 4.74373E-08 freq in 1/yr of EID and TDB is 2.90265E-08 freq in 1/yr of EIT and TlHP is 4.23001E-07
- freq in I/yr of eld and TIA is 8.70586E-07 freq in 1Iyr of EIT and TIOF is 6.64708E-07 freq in 1/yr of EID and TORV is 6.77160E-07 freq in 1/yr of EIT and TRPT is 2.17526E-06 freq in 1/yr of eld and TlHP is 6.77277E-08 freq in 1/yr of EIT and TLM is 2.41717E-07 freq in 1/yr of EID and TIOF is 1.06428E-07 freq in 1/yr of ElV and H1 is 1.84296E-06 freq in 1/yr of eld and TRPT is 3.48286E-07 freq in 1/yr of EIV and J2 is 4.71343E-07 freq in 1/yr of eld and TLM is 3.87018E-08 freq in 1/yr of EIV and ElB is 1.72212E-06 NUREG/CR-6143 F-14 Vol. 2, Part 2
Supporting Calculations Table F.3.2 Multiple Initiating Events for POS 5 (Continued) freq in 1/yr of ElV and ElC is 4.74373E-08 freq in Ilyr of E2B and E2T is 2.09626E-07 freq in 1/yr of EIV and EID is 1.72212E-06 freq in 1/yr of E2B and E2V is 2.09626E-07 freq in 1/yr of EIV and EIT is 1.07513E-05 treq in 1/yr of E2B and TSA is 1.32398E 07 freq in 1/yr of ElV and E2B is 1.96380E-06 freq in 1/yr of E2B and TSB is 1.32398E-07 freq in 1/yr of EIV ani E2C is 4.74373E-08 freq in 1/yr of E2B and T5C is 1.32398E-07 freq in 1/yr of ElV and E2D is 1.96380E-06 freq in 1/yr of E2B and TSD is 1.32398E-07 freq in 1/yr of EIV and E2T is 1.14811E-06 freq in 1/yr of E2B and TDB is 3.31003E-08 freq in 1/yr of ElV and E2V is 1.1481IE-06 freq in 1/yr of E2B and TIA is 9.92774E-07 freq in 1/yr of ElV and T5A is 7.25134E-07 freq in 1/yr of E2B and TORV is 7.72200E-07 freq in 1/yr of ElV and TSB is 7.25134E-07 freq in I/yr of E2B and TlHP is 7.72333E-08 ; freq in 1/yr of EIV and T5C is 7.25134E-07 freq in 1/yr of E2B and TIOF is 1.21365E-07 l freq in 1/yr of EIV and T5D is 7.25134E-07 freq in 1/yr of E2B and TRPT is 3.97168E-07 frey in 1/yr of EIV and TAB is 5.01567E-08 freq in 1/yr of E2B and TLM is 4.41337E-08 freq in 1/yr of Elv and TDB is 1.81288E-07 freq in 1/yr of E2C and EIT is 4.74143E-08 freq in 1/yr of EIV and TIA is 5.43735E-06 freq in 1/yr of E2C and ElV is 4.74143E-08 freq in 1/yr of EIV and TORV is 4.22928E-06 freq in 1/yr of E2C and TIA is 2.39793E-08 freq in 1/yr of EIV and TIOP is 4.74373E-08 freq in 1/yr of E2C and TORV is 1.86516E-08 frey in 1/yr of EIV and TillP is 4.23001E-07 freq in 1/yr of E2D and 111 is 3.36495E-07 freq in 1/yr of EIV and TIOF is 6.64708E-07 freq in 1/yr of E2D and J2 is 8.60598E-08 ; freq in 1/yr of EIV and TRIT is 2.17526E-06 freq in 1/yr of E2D and ElB is 3.14431E 07 freq in 1/yr of EIV and TLM is 2.41717E-07 freq in 1/yr of E2D and EIT is 1.96301E-06 freq in 1/yr of E2B and til is 3.36495E-07 freq in 1/yr of E2D and ElV is 1.96301E-06 freq in 1/yr of E2B and J2 is 8.60598E-08 freq in 1/yr of E2D and E2B is 3.58558E-07 frey in 1/yr of E2B and eld is 3.14431E-07 freq in Ilyr of E2D and E2T is 2.09626E-07 freq in 1/yr of E2B and EIT is 1.9630lE-06 frey in 1/yr of E2D and E2V is 2.09626E-07 freq in 1/yr of E2B and EIV is 1.9630lE-06 freq in 1/yr of E2D and T5A is 1.32398E-07 freq in 1/yr of E2B and E2D is 3.58558E-07 freq in 1/yr of E2D and T5B is 1.32398E-07 Vol. 2 Part 2 F-15 NUREG/CR 6143
1 Supporting Ccicuhtions Table F.3.2 Multiple Initiating Events for POS 5 (Continued) freq in 1/yr of E2D and T5C is 1.32398E-07 freq in 1/yr of E2T and TLM is 2.58012E-08 freq in 1/yr of E2D and T5D is 1.32398E-07 freq in flyr of E2V and III is 1.96720E-07 freq in 1/yr of E2D and TDB is 3.31003E-08 freq in 1/yr of E2V and J2 is 5.03119E-08 freq in 1/yr of E2D and TIA is 9.92774E-07 freq in 1/yr of E2V and ElB is 1.83821 E-07 freq in 1/yr of E2D and TORV is 7.72200E-07 freq in 1/yr of E2V and EID is 1.83821E-07 , freq in 1/yr of E2D and TIHP is 7.72333E-08 freq in Ilyr of E2V and EIT is 1.147d1E-06 freq in 1/yr of E2D and TIOF is 1.21365E-07 freq in 1/yr of E2V and E2B is 2.09619E-07 freq in 1/yr of E2D and TRPT is 3.97168E-07 freq in 1/yr of E2V and E2D is 2.09619E-07 freq in 1/yr of E2D and TLM is 4.41337E-08 freq in I/yr of E2V and E2T is 1.22551E-07 freq in 1/yr of E2T and HI is 1.96720E-07 freq in 1/yr of E2V and TSA is 7.74020E-08 freq in 1/yr of E2T and J2 is 5.031 ICE-08 freq in 1/yr of E2V and T5B is 7.74020E-08 freq in 1/yr of E2T and ElB is 1.83821E-07 freq in 1/yr of E2V and T5C is 7.74020E-08 f freq in 1/yr of E2T and eld i. 1.83821E-07 freq in 1/yr of E2V and TSD is 7.74020E-08 1 freq in 1/yr of E2T and EIV is 1.14761E-06 freq in 1/yr of E2V ad TDB is 1.93510E48 r freq in 1/yr of E2T and E2B is 2.09619E-07 freq in 1/yr of E2V and TIA is 5.80391E-07 freq in 1/yr of E2T and E2D is 2.09619E-07 freq in 1/yr of E2V and TORV !: 4.51440E-07 freq in 1/yr of E2T and E2V is 1.22551E-07 freq in 1/yr of E2V and TlHP is 4.51518E-08 freq in 1/yr of E2T and T5A is 7.74020E-08 freq in I/yr of E2V and TIOF is 7.09520E-08 freq in 1/yr of E2T and TSB is 7.74020E-08 freq in 1/yr of E2V and TRIT is 2.32191E-07 freq in 1/yr of E2T and TSC is 7.74020E-08 freq in 1/yr of E2V and TLM is 2.58012E-08 freq in 1/yr of E2T and T5D is 7.74020E-08 freq in 1/yr of T5A and H1 is 1.24244E-07 freq in 1/yr of E2T and TDB is 1.93510E-08 freq in 1/yr of T5A and J2 is 3.17759E-08 freq in 1/yr of E2T and TIA is 5.80391E-07 freq in 1/yr of T5A and EID is 1.16098E-07 freq in 1/yr of E2T and TORV is 4.51440E-07 freq in 1/yr of T5 A and EIT is 7.24805E 07 , freq in 1/yr of E2T and T!HP is 4.51518E-08 freq in 1/yr of T5A and EIV is 7.24805E-07 freq in 1/yr of E2T and TIOF is 7.09520E-08 freq in 1/yr of T5 A and E2D is 1.32391E-07 freq in 1/yr of E2T and TRPT is 2.32191E-07 freq in 1 Yr of TSA and E2T is 7.74005E-08 NUREG/CR-6143 F-16 Vol. 2, Part 2 l
Supporting Colculations Table F.3.2 Multiple initiating Events for POS 5 (Continued) freq in 1/yr of TSA and E2V is 7.7400SE-08 freq in I/yr of TSB and TRPT is 1.46647E-07 freq in 1/yr of T5A and TSB is 4.88855E-08 freq in 1/yr of TSB and TLM is 1.62955E-08 freq in 1/yr of T5A and TSC is 4.88855E-08 freq in 1/yr of T5C and H1 is 1.24244E-07 freq in 1/yr of T5A and T5D is 4.88855E-08 freq in 1/yr of T5C and J2 is 3.17759E-08 freq in 1/yr of T5A and TDB is 1.22217E-08 freq in 1/yr cf T5C and ElB is 1.16098E-07 freq in 1/yr of T5A and TIA is 3.66563E 07 freq in 1/yr of T5C and EIT is 7.24805E-07 freq in 1/yr of TSA and TORV is 2.85120E-07 freq in 1/yr of TSC and EIV is 7.24805E-07 freq in 1/yr of T5A and TlHP is 2.85169E-08 freq in 1/yr of TSC and E2B is 1.32391E-07 freq in 1/yr of T5A and TIOF is 4.48118E-08 freq in 1/yr of T5C and E2T is 7.74005E-08 freq in 1/yr of TSA and TRPT is 1.46647E-07 freq in 1/yr of T5C and E2V is 7.74005E-08 freq in 1/yr of T5A and TLM is 1.62955E-08 freq in 1/yr of T5C and T5A is 4.88855E-08 freq in 1/yr of TSB and H1 is 1.24244E-07 freq in 1/yr of T5C and TDB is 1.22217E-08 freq in liyr of TSB and J2 is 3.17759E-08 freq in 1/yr of T5C and TORV is 2.85120E-07 freq in 1/yr of TSB and ElB is 1.16098E-07 freq in 1/yr of T5C and TIHP is 2.85169E-08 freq in 1/yr of TSB and eld is 1.16098E-07 freq in 1/yr of TSC and TIOF is 4.48118E-08 freq in 1/yr of TSB and EIT is 7.24805E-07 freq in 1/yr of T5C and TRPT is 1.46647E-07 freq in 1/yr of TSB and ElV is 7.24805E-07 freq in 1/yr of T5C and TLM is 1.62955E-08 freq in 1/yr of TSB and E2B is 1.32391E-07 freq in 1Iyr of T5D and H1 is 1.24244E-07 freq in 1/yr of TSB and E2D is 1.32391E-07 freq in 1/yr of T5D and J2 is 3.17759E-08 freq in 1/yr of TSB and E2T is 7.74005E-08 freq in 1/yr of T5D and ElB is 1.16098E-07 freq in 1/yr of TSB and E2V is 7.74005E-08 freq in 1/yr of T5D and EID is 1.16098E-07 freq in 1/yr of TSB and T5A is 4.88855E-08 freq in 1/yr of T5D and EIT is 7.24805E-07
- freq in 1/yr of TSB and T5D is 4.88855E-08 freq in 1/yr of T5D and ElV is 7.24805E-07 freq in 1/yr of T5B and TDB is 1.22217E-08 freq in 1/yr of T5D and E2B is 1.32391E-07 freq in 1/yr of TSB and TORV is 2.85120E-07 freq in 1/yr of T5D and E2D is 1.32391E-07 freq in 1/yr of TSB and TillP is 2.85169E-08 freq in 1/yr of T5D and E2T is 7.74005E-08 freq in 1/yr of TSB and TIOF is 4.48118E-08 freq in 1/yr of T5D and E2V is 7.74005E-08 Vol. 2. Part 2 F-17 NUREG/CR-6143
~
Supporting Calculations Table F.3.2 Multiple initiating Events for POS 5 (Continued) freq in 1/yr of T5D and TSA is 4.88855E-08 freq in 1/yr of TDB and TORV is 7.12800E-08 freq in 1/yr of T5D and TSB is 4.88855E-08 freq in 1/yr of TDB and TIOF is 1.12029E-08 freq in 1/yr of TSD and T5C is 4.88855E-08 freq in 1/yr of TDB and TRPT is 3.66617E-08 freq in 1/yr of TSD and TDB is 1.22217E-08 freq in 1/yr of TIA and H1 is 9.31832E-07 l freq in 1/yr of T5D and TIA is 3.66563E-07 freq in 1/yr of TIA and J2 is 2.38319E-07 freq in 1/yr of TSD and TORV is 2.85120E-07 freq in 1/yr of TIA and ElB is 8.70733E-07 freq in 1/yr of T5D and TIHP is 2.85169E-08 freq in 1/yr of TIA and eld is 8.70733E-07 freq in 1/yr of T5D and TIOF is 4.48118E-08 freq in 1/yr of TIA and EIT is 5.43604E-06 freq in 1/yr of T5D and TRirT is 1.46647E-07 freq in 1/yr of TIA and ElV is 5.43604E-06 freq in 1/yr of TSD and TLM is 1.62955E-08 freq in 1/yr of TI A and E2B is 9.92930E-07 freq in 1/yr of TAB and EIT is 5.01323E-08 freq in 1/yr of TI A and E2D is 9.92930E-07 freq in 1/yr of TAB and EIV is 5.01323E-08 freq in 1/yr of TI A and E2T is 5.80504E-07 freq in 1/yr of TAB and TI A is 2.53539E-08 freq in 1/yr of TI A and E2V is 5.80504E-07 freq in 1/yr of TAB and TORV is 1.97208E-08 freq in 1/yr of TIA and T5 A is 3.66641E-07 freq in 1/yr of TAB and TRPT is 1.01431 E-08 freq in 1/yr of TIA and T5D is 3.66641E-07 freq in 1/yr of TDB and H1 is 3.10611E-08 freq in 1/yr of TIA and TAB is 2.53601E-08 freq in 1/yr of TDB and eld is 2.90244E-08 freq in 1/yr of TI A and TDB is 9.16625E-08 freq in 1/yr of TDB and EIT is 1.81201E-07 freq in 1/yr of TI A and TORV is 2.13840E-06 freq in 1/yr of TDB and EIV is 1.81201E-07 freq in 1/yr of TIA and TIOP is 2.39852E-08 l freq in 1/yr of TDB and E2D is 3.30977E-08 freq in 1/yr of TIA and TlHP is 2.13877E-07 freq in 1/yr of TDB and E2T is 1.93501E-08 freq in 1/yr of TI A and TIOF is 3.36088E-07 freq in 1/yr of TDB and E2V is 1.93501E-08 freq in 1/yr of TI A and TRPT is 1.09985E-06 freq in 1/yr of TDB and T5 A is 1.22214E-08 freq in 1/yr of TORV and 111 is 7.24758E-07 freq in 1/yr of TDB and TSB is 1.22214E-08 freq in 1/yr of TORV and J2 is 1.85359E-07 freq in 1/yr of TDB and T5C is 1.22214E-08 freq in 1lyr of TORV and ElB is 6.77237E-07 freq in 1/yr of TDB and T5D is 1.22214E-08 freq in iIyr of TORV and ElC is 1.86551E-08 freq in 1/yr of TDB and TI A is 9.16407E-08 freq in I/yr of TORV and eld is 6.77237E-07 F-18 Vol. 2, Part 2 NUREG/CR-6143
Supporting Calculations Table F.3.2 Multiple Initiating laents for POS 5 (Continued) freq in 1/yr of TORV and EIT is 4.22803E-06 freq in 1/yr of T!HP and EIT is 4.22803E-07 freq in 1/yr of TORY and EIV is 4.22803E-06 freq in 1/yr of T!HP and EIV is 4.22803E-07 freq in 1/yr of TORV and E2B is 7.72279E-07 freq in 1/yr of TlHP and E2B is 7.72279E-08 freq in 1/yr af TORV and E2C is 1.86551E-08 freq in 1/yr of TlHP and E2D is 7.72279E-08 freq in 1/yr of TORV and E2D is 7.72279E-07 freq in 1/yr of TlHP and E2T is 4.51503E-08 i i freq in 1/yr of TORV and E2T is 4.51503E-07 freq in 1/yr of T!HP and E2V is 4.51503E-08 l i freq in 1/yr of TORV and E2V is 4.51503E-07 freq in 1/yr of TiliP and TSA is 2.85165E-08 freq in 1/yr of TORV and T5A is 2.85165E-07 freq in 1/yr of TlHP and TSB is 2.85165E-08 freq in 1/yr of TORV and TSB is 2.85165E-07 freq in 1/yr of TillP and T5C is 2.85165E-08 freq in 1/yr of TORV and T5C is 2.85165E-07 freq in 1/yr of TillP and TSD is 2.85165E-08 freq in 1/yr of TORY snd T5D is 2.85165E-07 freq in 1/yr of TIHP and TIA is 2.13828E-07 freq in 1/yr of TORV and TAB is 1.97245E-08 freq in 1/yr of TlHP and TORV is 1.66320E-07 freq in 1/yr of TORV and TDB is 7.12931E-08 freq in 1/yr of T!HP and TIOF is 2.61402E-08 l freq in 1/yr of TORV and TIA is 2.13828E-06 freq in 1/yr of TIHP and TRPT is 8.55439E-08 freq in 1/yr of TORV and TIOP is 1.86551E-08 freq in 1/yr of TIOF and H1 is 1.13891E-07 freq in 1/yr of T' iRV and TlHP is 1.66349E-07 freq in 1/yr of TIOF and J2 is 2.91279E-08 freq in 1/yr of TORV and TIOF is 2.61402E-07 freq in 1/yr of TIOF and ElB is 1.06423E-07 freq in 1/yr of TORV and TRPT is 8.55439E-07 freq in 1/yr of TlOF and eld is 1.06423E-07 l freq in I/yr of TORV and TLM is 9.50571E-08 freq in 1/yr of TIOF and EIT is 6.64404E-07 freq in 1/yr of TIOP and EIT is 4.74143E-08 freq in 1/yr of TIOF and EIV is 6.64404E-07 freq in 1/yr of TIOP and EIV is 4.74143E-08 freq in 1/yr of TIOF and E2B is 1.21358E-07 freq in 1/yr of TIOP and TIA is 2.39793E-08 freq in Ilyr of TIOF and E2D is 1.21358E-07 freq in 1/yr of TIOP and TORV is 1.86516E-08 freq in 1/yr of TIOF and E2T is 7.09505E-08 freq in 1/yr of TlHP and HI is 7.24758E-08 freq in 1/yr of TIOF and E2V is 7.09505E-08 i I freq in 1/yr of TlHP and 12 is 1.85359E-08 freq in I/yr of TIOF and TS A is 4.48117E-08 freq in 1/yr of TIHP and ElB is 6.77237E-08 freq in 1/yr of TIC and TSB is 4.48117E 08 freq in 1/yr of lillP and EID is 6.77237E-08 freq in 1/yr of TIOF and T5C is 4.48117E-05 Vol. 2, Part 2 F-19 NUREG/CR-6143
Supporting Calculations Table F.3.2 Multiple Initiating Events for POS 5 (Continued) freq in 1/yr of TIOF and T5D is 4.48117E-08 freq in 1/yr of TRPT and TLM is 4.88865E-08 freq in 1/yr of TIOF and TDB is 1.12032E-08 freq in 1/yr of TLM and 111 is 4.14147E-08 > freq in 1/yr of TIOF and TIA is 3.36016E-07 freq in 1/yr of TLM and J2 is 1.05920E-08 9 freq in 1/yr of TIOF and TORV is 2.61360E-07 freq in 1/yr of TLM and ElB is 3.86992E-08 freq in 1/yr of TIOF and TIllP is 2.61405E-08 freq in 1/yr of TLM and eld is 3.86992E-08 freq in 1/yr of TIOF and TRPT is 1.34426E-07 freq in 1/yr of TLM and EIT is 2.41602E-07 freq in 1/yr of T10F and TLM is 1.49376E-08 freq in Ilyr of TLM and EIV is 2.41602E-07 freq in 1/yr of TRIrr and }{l is 3.72733E-07 freq in 1/yr of TLM and E2B is 4.41302E-08 freq in 1/yr of TRPT and J2 is 9.53277E-08 freq in 1/yr of TLM and E2D is 4.41302E-08 freq in 1/yr of TRPT and ElB is 3.48293E-07 freq in 1/yr of TLM and E2T is 2.58002E-08 freq in 1/yr of TRPT and EID is 3.48293E-07 freq in 1/yr of TLM and E2V is 2.58002E-08 I freq in 1/yr of TRPT and EIT is 2.17441E-06 freq in 1/yr of TLM and T5A is 1.62952E-08 freq in 1/yr of TRPT and EIV is 2.17441E-06 freq in 1/yr of TLM and TSB is 1.62952E-08 freq in 1/yr of TRPT and E2B is 3.97172E-07 freq in 1/yr of TLM and T5C is 1.62952E-08 freq in 1/yr of TRirr and E2D is 3.97172E-07 freq in 1/yr o; TLM and TSD is 1.62952E-08 freq in 1/yr of TRirr and E2T is 2.3220!E-07 freq in 1/yr of TLM and TIA is 1.22188E-07 freq in 1/yr of TRPT and E2V is 2.32201E-07 freq in 1/yr of TLM and TORV is 9.50400E-08 freq in 1/yr of TRPT and T5A is 1.46656E-07 freq in 1/yr of 7LM and TIOF is 1.49373E-08 freq in 1/yr of TRPT and TSB is 1.46656E-07 freq in i/yr of TLM and TRPT is 4.88822E-08 freq in 1/yr of TRPT and TSC is 1.46656E-07 TRIPLE INITIATORS freq in 1/yr of TRPT and TSD is 1.46656E-07 NO TRIPLE INITIATORS ABOVE TRUNCATION VALUE freq in 1/yr of TRPT and TAB is 1.01440E-08 freq in 1/yr of TRPT and TDB is 3.66650E-08 freq in 1/yr of TRPT aM TIA is 1.09969E-06 freq in 1/yr of TRPT and TORV is 8.55360E-07 freq in 1/yr of TRPT and TillP is 8.55507E-08 freq in 1/yr of TRPT and TIOF is 1.34435E-07 NUREG/CR-6143 F-20 Vol. 2, Part 2
l l l Supporting Calculations F.4 Detailed Calculations U,u . (1-x,u) H,,,, < u,,,,, + x,, .M,ue u,,,,, Based on results of the scoping calculations as described in Section F.2 of this report, more detailed calculations uug(1.x ,3.Mg gu ,,,
+x 3pM y gu, ,,,
were performed. At shutdown, the normal methods for core cooling use the shutdown cooling system, either with RHR or with H,,, = [inassouttt) .h ,, de ADHR. The minimum design pressure for these systems is 220 psig for RHR and 80 psig for ADHR. In POSs 4 and 5 the vessel head is on and pressurization transients can overpressurize these systems. We have taken the #3, = [rnassirge) .h, de failure pressure of these systems as twice the design rating - namely,440 psig for RHR and 160 psig for ADHR. Overpressurization of these systems leads to an M denotes total fluid mass, x denotes quality, u denotes interfacing systems LOCA outside containment. In specific internal energy, subscript fin denotes final state, POSs 4 and 5 these systems are auto-isolated at 135 psig, subscript ini denotes initial state, subscript wat denotes and they are auto-isolated at low level 3. If the systems water, and subscript stm denotes vapor (steam). ; cre isolated, shutdown cooling is lost, but the Massout and massin are time dependent mass flow rates overpressurization is prevented. out of and into the vessel, respectively. *h" denotes SP*Cific enthalpy, subscript outof denotes mass out, and , To perform these calculations, a computer code was subsen.p t into denotes rnass m. written. This code, GGENER. PAS, performs an energy balance on a system of saturated steam / water accounting The source code is given as Table F.4-1. The code was , for time dependent decay heat, addition of water, and modified and improved throughout the project. For l blowdown of steam or flashing water. The code uses the example, the capability to handle time dependent decay l following special case of the first law of thermodynamics heat was added, and the numerical fit to Moody's for the energy balance: blowdown model was improved. Also, in the latest version, the code calculates actual and measured water fP(tidt = AU + NI levels, relative to instrument zero, accounting for changes in actual density of water at the calculated thermodynamic state. Calculation 90-492-01-A:19 where P(t) is the power (decay heat), 4U is the change contains the latest version of the code (that listed in m mternal energy of the water / steam m the vessel, and Table F.4-1). Also, this calculation contains detailed AH is the net enthalpy lost from the vessel. results for the re-analysis of all earlier energy balances. The re-analysis results agreed with the original analysis results. However, levels were more accurately calculated in the re-analyzed results. The re-analysis was P(t) = exp(-0.3 68 In(t,') +0.593) performed for the following calculations in the 90-492-01 series: A:6, A:10, A:11, A:13, and A:17. A u = u,y - u, F.4.1 Calculation #11 Calculation 90-492-01 A:11,: SDC Relief Valves POS 4 and 5", addressed whether or not relief valves in the at = n ,-n , RHR/SDC system could prevent overpressurization given heatup of the system due to loss of heat removal. The where P(t) is the power m. % of full power as a function calculation concludes the following (including the effects of time m hours since shutdown (t,), U,,,,is final internal of the re-analysis of calculation 19): energy, U, is mitial internal energy, H is enthalpy out of the vessel, and H, is enthalpy into the vessel. (1) For POS 4,440 psig is reached at 49 min even l F-21 NUREG/CR-6143 Vol. 2, Part 2
1 l Supporting Calculations Table F.4.1 GGENER. PAS Source Code (J. Darby, SEA 7/22/92 Version} program ggbifil; { modification of blowfil. pas code to include} {$N+} (Grand Gulf time dependent decay heat} (initial saturated state, blowdown sat water or sat steam via Moody} {from tank out to 15 psia sink; M AKEUP AT CONSTANT RATE and no work} { case of two phase IN tank NOT modeled here) , { calculates final sat state, fixed volume,both initial and final} { states must be sat > 212 F,15 psia} (stops if tank has no water} { limit polynomial fit of Moody's data to 5 points in dataset to } (better fit high pressure data} { change Moody steam mass flux from 500 to 600 for steam at 300 psia} {7/15/92 add option for static head into driving pressure for) { FLASHING water out the hole; no effect if steam out hole} {7/22/92 use simple linear fit to Moody, add level indication} b var nameofmn: string [50]; filevar,outfil: text; stopit: boolean; i,no:longint; p,numdatapts: integer; massperarea:real; holesize:real;id: string [1]; v,x,m,uw,us,u, tend dt, time:real; actlevel measlevel,1bmtolevel:real; temp, press,diff,difft:real; heigh t, heightin ,inspvol,sta tiepress , statiep ressin : real; vw,va,enthw,enths mo,xo,uwo uso,a,tempp,pressp,xp, hop;real; mir,hi:real; { mass rate IN Ibm /sec, and specific enthalpy in} ti,pinit:real; qr,qri,timpos,mor,ho,entnet,engnet:real; {qri is initial decay heat} {timpos is time since shutdown in HOURS at which initial decay heat} {qri is specified} procedure linfit(xu,hxu:real; var pxu real); (for use in blowdwn. pas} {piecewise Linear Fit of Moody Blowdown data} {xu is given pressure, pxu is calculated blowdown Ibm /ft"2/sec} (hxu is hole enthalpy} begin if id = 'w' then begin if xu> 100 then pxu:=21.5*hxu-3.75c3; (function of enthalpy} if(su < = 100) and (x u > 15) then px u: = 19.33 *xu + 767;{ function of pressure) {use pressure to more accurately include static head of water} if xu< = 15 then pxu:=0 end; (end if 'w'} ifid='s' then begin I if xu>2000 then pxu:=-28.23*hxu+3.71e4; l NUREG/CR-6143 F-22 Vol. 2, Part 2
=
F
Supporting Calculations Table F.4.1 GGENER. PAS Source Code (Continued) if (zu < = 2000) and (xu > 600) then pxu: = -48.28thxu + 6.02e4; if (xu < = 600) and (xu > 25) then pxu: = 2.087*xu-2.174;{ function of pressure} {in this range pressure fit better) if xu< =25 then pxu:=5*hxu-5.75e3 end {end if'a'} end- { procedure linfit} function massout(tankpress,holeenthalpy:real):real; begin linfit(tankpress,holeenthalpy,msssperarea); { Moody sat steam lbm/ft**2/sec} massout: = massperarca end; (function massout} procedure thereql; { calculate new saturated state in tank} {at end of timestep} begin reset (filevar); readin(filevar);readin(filevar);readin(filevar);readin(filevar); temp: = ti; press: = pinit;x: = xo; , repeat begin tempp:= temp;pressp:= press;xp:= x;{p's,eg xp, are previous iteration values} hop: = ho;{enthalpy out hole for previous iteration} { read string leader} readin(filevar, temp, press,vw.vs,enthw.enths); uw: = enthw-press *vw*l44/778; us: = enths-press *vs*144/778; (for assumed sat at temp, calc x from ist law} x: = engnet + xo*mo*uso + (1-xo)*mo*uwo; x: = x-en(net; x:-(x-m*uw)/(m*us-m*uw); { check volume balance} diffi: =diff; a: = vw*(1-x)*m + vs*x *m; diff: = abs (a-v); if id = 's' then ho: = enths;if id = 'w' then ho: = enthw; end; until (diff> =diff1) or (cof(filevar)); if cof(filevar)=true then begin writeln(outfil,'OUT OF CODE P/T LIMITS');stopit:=true; exit end; if xp<0.0 then xp:=0.0;{ avoid - x due to interpolation} { actual and measured levels} actlevel:=(1-xp)*m*1bmtolevel*vw/inspvol;{ water mass
- inches /lbm *}
{ density ratio for new water density rei to initial} actievel: = actlevel-533; { actual level wrt instr 0} measlevel: =actlevel*0.02177/vw;{ meas level wrt instr 0 uncompensated} ifi mod p=0 then begin {##### print out values each 0.l*p sec ########} writeln(' time is ', time:12,' sec'); Vol. 2. Part 2 F-23 NUREG/CR-6143
I Supporting Calculations L ble F.4 J ';GENER. PAS Source Code (Continued) writeln(outfil); { Note time step set at 0.1 sec} writeln(outfil,'at time sec', time:12,* quality is ',xp:12); writeln(outfil,' ',' steam mass Ibm is ',xp*m:12); writeln(outfil,' ',' water mass Ibm is *,(1-xp)*m:12); writeln(outfil,' *, ' temp F is ',tempp:12); writeln(outfil,' ',' vapor press psia is ',pressp:12); writeln(outfil,' ',' pressure psi at hole from static head'); writeln(outfil,' ',' of water is ',statiepress:12); writeln(outfil,' ' ' actual level wrt instr 0 inches ',actievel:12); writeln(outfil,' ',* meas *d level wrt instr 0 inches ',measlevel:12); if id ='s' then writeln(outfil,' ',' static head has no effect since steaming out hole'); writeln(outfil,' ',' heat Btu /sec is ',qr:12); writeln(outfil,' ',' Ibm /sec out hole is ',mor:12); writeln(outfil,' * ' spec enthalpy Btu /lbm out hole is ', hop:12) end; { mod if to output} {specify mass out for next time step} { calculate pressure from static head of water} height:=heightin*(1-xp)/(1-xo)*m/mo*inspvol/vw; { static head in ft} staticpress: = 1/vw* height /144;(static presure in psi} - ifid='s' then staticpress:=0.0; { static head does not affect steaming case} mor: = holesize*massout(pressp + staticpress, hop) end; { procedure theregl} begin (main program} stopit:= false; engnet: = 0;entnet: = 0;qr: = 0;qri: = 0; { input data} (access steam table data for sat conditions) assign (filevar,'blowdwn.dat*); assign (outfil,' tank.dat'); rewrite (outfil); writeln(' enter name of case to be run');readin(nameofrun); writeln(' enter initial temp,f');readln(ti); writeln(' enter initial pressure, psia');readln(pinit); writeln(' enter fixed volume v,ft3'); readln(v); writeln(' enter initial specific volume of sat liquid in ft"3/lbm'); reatlin(inspvol); writeln(' enter initial height in feet from hole to liquid / vapor surface'); i writeln(* enter 0.0 if static head not of interest'); writeln(' static head only affects water, flashing case, not steam case'); readin(heightin); { calculate initial static pressure from height ofliquid above hole} staticpressin: = 1/inspvol*heightin/144; write?n(' enter initial actual level in inches above instr. zero (e.g. 60)'); readlai(actievel); meas!.: vel: = actievel*0.02177/inspvol;{ measured level above instr 0} (uncompensated} writeln(' enter initial quality, fraction'); readin(xo); NUREG/CR-6143 F-24 Vol. 2, Part 2
Supporting Calculations Table F.4.1 GGENER. PAS Source Code (Continued) writeln(' enter initial total mass water & steam,1bm'); readin(mo); lbmtolevel: =(533 +actievel)/((1 xo)*mo); { actual inches /lbm, 533 is instr 0} writeln(' enter initial spec internal energy water, btu /lbm'); readin(uwo); writeln(' enter initial spec internal energy steam, btu /lbm'); readin(uso); { start time is 0} writeln(' enter end time,sec'); readln(tend); writeln(' enter number of data sets to be saved'); readin(numdatapts); p:= round(tend /numdatapts); dt:-1; {l second time step} (FOR TIME STEP OF 1 SEC CilANGE ABOVE 2 STATEMENTS TO:} {p:=round(tend /numdatapts)} - (dt:= 1; I second time step} (FOR TIME STEP OF 0.1 SEC CHANGE ABOVE 2 STATEMENTS TO:) {p:= round(10* tend /numdatapts)} {dt:=0.1; 0.1 second time step} m: = mo; writeln(outfil,' NAME OF Tills RUN '); writeln(outfil,' ' nameofrun:30); writeln(outfil); writeln(outfil,' INITIAL CONDITIONS *); writeln(outfil,' Initial temp F ',ti:12); writeln(outfil,' Initial pressure psia ',pinit:12); writeln(outfil,' Fixed Tank Volume cubic ft ',v:12); writeln(outfil,' Initial quality ',xo:12); writeln(outfil,' Initial total mass water & steam Ibm',mo:12); writeln(outfil,' Initial height water above hole in ft is ',heightin:12); writeln(outfil,' Initial specific volume water ft*3/lbm is ',inspvol:12); writeln(outfil,' Initial pressure from static head of water psi is '); writeln(outfil,' ',statiepressin:12,' only affects water, flashing case'); writeln(outfil,' not steaming case'); writeln(outfil,' Initial Actual Level inches wrt instr. 0 ',actievel:12); writeln(outfil,' Initial Measured Level inches wrt instr. 0 ',measlevel:12); writeln(outfil,' Initial spec int ener Btu /lbm water ',uwo:12); writeln(outfil,' Initial spec int ener steam Btv '" m ',uso:12); writeln(outfil,' Time step sec ',dt:12); writeln(outfil,'End time sec ', tend:12); write!@utfil); { calculate number of intervals} no:= round(tend /dt); { input data) writeln(' enter initial heat input in bru/sec');readin(qri); { initial decay heat} writeln(' enter time in HOURS corresponding to initial heat input'); readin(timpos); { time initially, used for time dependent decay heat calc} Vol. 2, Part 2 F 25 NUREO/CR-6143
1 Supporting Calculations Table F.4.1 GGENER. PAS Source Code (Continued) writeln(' enter hole size in ft**2');readin(holesize); writeln(' Water or Steam from break (enter w or s) 7');readin(id); writeln(outfil,' Initial heat input at ',qri:12,' Btu /sec'); writeln(outfil,' Initial heating at ',timpos:12,' HOURS after shutdown'); writeln(outfil,' Hole size in square flis ',holesize:12); if id ='s' then writeln(outfil,' Steam out hole'); if id = 'w' then writeln(outfil,' Water out hole (flashes)'); writeln(' enter constant mass rate in, Ibm /sec');readin(mir); wdteln(outfil,' Mass coming in at 6onstant rate Ibm /sec of ',mir:12); writeln(' enter enthalpy of mass in, in Bru/lbm');readin(hi); writeln(outfil,' Specific enthalpy of mass coming in Btu /lbm is ',hi:12); writeln(outfil); ifid='s' then begin writeln(' enter spec enthalpy Btu /lbm of steam at ',pinit:12,' psia'); readin(ho); writeln;writeln('End time is ', tend:12,'sec');writeln; { pressure at hole from static head of water for steaming is 0} staticpressin: = 0.0; mor: = holesize*massout(pinit + statiepressin,ho) end; ifid='w' then begin writeln(' enter spec enthalpy Btu /lbm of water at ',pinit:12,' psia'); readin(ho); writeln;writeln(*End time is ', tend:12,' sec');writeln; { calculate pressure at hole from static head of water} statiepressin: = 1/inspvol*heightin/144; mor:=holesize*massout(pinit+statiepressin ho) end; { iterate to get equil state via procedure} for i:= 1 to no do begin time: =i*dt; gr:=exp(-0.368*lrDime/3600+ timpos)+0.593); { decay heat per cent} {via calc 492-01:2, page 4, note time is in HOURS in this equation} qr:=qr*0.0l*3833e6*3.413/3600; {per cent to fraction to watts} {to Btu /hr to Btu /sec} if gri=0 then qr:=0; {0 Heat Case} diff: = le8; entnet:=entnet+(mor*ho-mir*hi)*dt; { net enthalpy out from time 0} engnet: =engnet + qr*dt; { net heat in from time 0} m:=m+(mir mor)*dt; if m< =0.0 then begin writeln(outfil,'OUT OF FLUID'); close(filevar);close(outfil); exit end; if stopit-true then begin close(outfil);close(filevar);cxit end; thereql end; close(filevar); close(outfil); end. NUREG/CR-6143 F-26 Vol. 2, Part 2
Supporting Calculations 1 with relief from both RHR trains available. The vessel pressure for various combinations of ECCS i i
, injection and either 1 or 2 SRVs open is provided in (2) For POS 5,440 psig is reached at 120 min even Figure F.4-8 and F.4-9.
with relief from both RHR trains available, Steaming through 1 SRV will match 1 % decay heat, (3) For ADHR with decay heat at 24 hours,160 without makeup, at 220 psig. With makeup, steaming i psig is reached at 113 min even with relief from can match I % decay heat at 180 psig, both RHR trains available. Steaming through the vent line is inadequate to prevent Pressurization to SRV safety setpointa in POSs 4 and 5 De relief capability is inadequate to prevent with decay heat at 1 % and 0.9 %, respectively. After a overpressurizing the components, 30 day refueling outage, with decay heat at 0.16%, steaming through the vent line can match decay heat only F.4.2 Calculation #4.1 if pressure is 600 psig (without makeup), or 400 psig C lculation 90-492-01 A:4.1, " Relief Capabilities at (with makeup). Grand Gulf', was a more detailed evaluation of the t.bility of the SRVs to relieve pressure than performed in F.4.3 Calculation #6 the earlier scoping calculation # 3. This calculation Calculation 90-492-01-A:6, "SRVs for Small/ Medium addressed the following topics: LOCAs in POS 4" evaluated the ability of breaks and ; i SRVs to control pressure in POS 4. The re-analyses of (1) Friction Factors for SRV Relief and the 2 Inch vent line calculation 19 agreed with the results of the original i calculation, except that level was calculated to be higher ! (2) Relief of Saturated Steam and 200 degree F due to swell. Water from One SRV between 100 and 1400 psig The updated results are as follows. The calculation evaluated the need for opening an SRV in relief on POS (3) Relief of Saturated Steam and 200 degree F 4 following a small LOCA (0.007 sq ft) to prevent Water from the Vent Line between 100 and pressurization hfore ECCS is auto-actuated. Assuming a steam line break of 0.007 sq ft, complete phase 1400 psig separation in the vessel, and complete mixing of core and (4) Grand Gulf Steaming Rate: downcomer water, the system pressure / measured water level history is as follows: (a) No Makeup (a) 135 psig and + 88 inches at 420 seconds (b) Makeup with 100 degree F Water to Maintain Level (b) 440 psig and + 128 inches at 3220 seconds. (5) Vessel Pressure for Water through SRVs from: The high measured levels at these pressures are due to HPCS, LPCS, LPCI, and Combinations swell of the actual level with temperature. ECCS does not actuate until level 2, -41.6 inches measured, or level (6) Steam Relief through 1 SRV to match I% 1, .150.3 inches measured. Thus, a small (or small, Decay Heat for the two cases of Item (4) medium LOCA) will pressurize the system before ECCS injection is auto-initiated. A 0.007 sq ft water break was (7) Ability of the Vent Line to Match Decay Heat. also analyzed, and the conclusions are the same as for the steam break as expected, since water breaks do not ne calculated relief capacities for one SRV and for the depressurize as effectively as steam breaks. This same vent line, for steam and water, are provided in Figures calculation showed that if one SRV is opened for steam F.41 through F.4-4. relief, even with a zero size LOCA, pressure never exceeds 135 psia before. the level 1 ECCS actuation The steaming rate Sr Grand Gulf, with and without setpoint is reached. Thus, opening an SRV prevents makeup, is given in Figure F.4-5 and F.4-6. The decay significant pressurization of the system. [The difference heat curve used to canelate these steaming rates is given in Figure F.4-7. Vol. 2, Part 2 F-27 NUREG/CR-6143
Supporting Calculations 8E+006 . . . . 1
-1 SRV 200 F Water :
4 - . . . . . . .
. .f . .;.. .
...j.........
- : i : i : -
y - s 6E+006 - i i
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1 g4 .........j...................... ..... . .. . ...i..... ...... ............ E "
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g4g " ....... . .... ............. .. .. .. . . ...*..... .............. .... ........ l ! : : ! ! 2E+006 ' l 0 200 400 600 800 1000 1200 1400 l Vessel Pressure, psig l l l 1 1 1 1 1 i 1 l , 1 I t L Figure F.4-1 1 SRV, Water NUREG/CR-6143 F-28 Vol. 2, Part 2
Supporting Criculitions 6 i 1E+006 . g00000 -.......-
-1SRV Sat. Steam -{:
.........i..........9......................i............j.........I...... '
g .........j...........
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c i ! -
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.............4.. . .. .. . . . '.. . . . . . . . . . . .
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g
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I i ! A A A A E 2 E 1 1 A A E .A A 1 a a 1 1 1 1 1 A I B A 0 200 400 600 000 1000 1200 1400 i Vessel Pressure, psig i i Figure F.4.21 SRV, Steam Vol. 2, Part 2 F-29 NUREG/CR-5143 l . .
Suppoding Calculations 450000 -
~
4o0000 _ . . .
-Vent 200 F Water .!.. . . . . . ... . !
.2..........h......................4...... ..............l.........
I - y g : :- :- - S - u- 250000 -- i ! i i- i !- - 2 200000 ~
~
I 150000 - - i- ;ii-100000 O 200 400 600 800 1000 1200 1400 Vessel Pressure, psig C Figure F.4.3 Vent Line, Water NUREG/CR-6143 F-30 Vol. 2, Part 2
- - - - F i.
Supporting Calculations 70000 . 60000 l- . . . . -Vent ..... Sat. Steam . i . . . . . . . . . . ! .. . . . . m m _......,:..........3... .....,............,.......3..
.....p.......
R : ; l. _ _ . . . . . . . . . . . . . . . . . . . . . . . . ...f., . . . . . . . . . . . . . . . . . . . . . . . . . It g _ . . . . . . j. . . . . . .; . . . . . . . . ; . . . . . . . . . . . .;, . . . . . . . ;. . .. 2 m _.......:............!........+......3..........j........ 10000 --
+!+ +-
- 0. .' '
0 200 400 000 800 1000 1200 1400 Vessel Pressure, psig Figure F.4.4 Vent Line, Steam Vol. 2, Part 2 F-31 NUREG/CR-6143
Supporting Calcult.tions l l I I l
-GG Steaming Rate Naming with 100 F Water Makeup
...e.... 1. . . . . . - .
3s.2 .. . . , . . 3. . " " 1 " . . .. . , i . ... . . ..
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.i Figure F.4.5 Steaming with Makeup NUREG/CR-6143 F-32 Vol. 2, Part 2
1 Supporting Calculations
-GG Steaming Rate st=*wm No Makeup .
12.5 q -
.i: :
12- - : : . i.. . ! '- , . ,:
': . . ;. l . , .r.
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t Figure F.4.6 Steaming with No Makeup Vol. 2 Part 2 F-33 NUREG/CR-6143
I Supporting Calculations 18.8 .
, i . .
jg _.........*..............!.... .. GG Decay Heat 18.4 ............::..........:... g , ..
- 6. : : : : :
3 . : . . : : 18 . ..... .....+:.. ............g.... ....p..... . . . . . .
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g-- g j{g . . . . . . . . . . ..
. . . . . . . . . . . . . . . .. ..' . .... ..,.4............. . .. ...
g .g ..........1............................ O ..........:.............g:.. :
. . . . > . . . . . . . . . . < . . . . . . . . . . . . . .3... ... ...
C 17*4 - j . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..4....... . . . . . . . . . .. jf ........9...........g o . ;...o . . go o o n . . og o no o 16.8 1 2 3 4 5 6 7 In of: Time Shutdown in Hours Figure F.4.7 Decay lleat NUREGICR.6143 F-34 Vol. 2, Part 2 r
Supporting Calculations 8Et006 i ,1 r I I fe.'efo
-1[RV 200 F Waterj
/-
7E+006 - j- 7 14,53o j ?SRV 200 F WATER M 6E+006 J 12.4eo ) E f I D . ,
/ #
5E+006 f 1o.32o
/
t l:. 4E+006, - - - e.304 SE+006 -- A, e.228 gggggg .. .1 i. ... . ... x .. .... .... ....
,,,,, j l
0 200 400 600 800 1000 1200 1400 Vessel Pressure, psig l XllPCS IIPCS intersects ISRV curve at 260 psig,7000 gpm aLPCS LPCS intersects ISRV curve at 170 psig,5700 gpm o LPCI LPCI intersects ISRV curve at 120 psig,4700 gpm (1 pump) Figure F.4-8 Pressure: Water Solid With 1 ECCS Pump Vol. 2, Part 2 b l-35 NUREGICR-6143
I l l 1 l l Supporting Calculations BE+006 u , f, i i ; l
-1%RV 200 F Water 7E+006 y ,
?SRV 2C 0 F Watar j
k 6E+006 -- y
/
. / /
5E+006 - g - l 2 4E+006 -c I
]
3E+006 / , 2E+006 '
- J ' ' '
O 200 400 600 800 1000 1200 1400 Vessel Pressure, psig i i X LPCI and LPCS A IIPCS and LPCS o 2 LPCI Pumps (Separate lines) Figure F.4-9 Pressure: Water Solid With 2 ECCS Pump 1 l NUREG/CR-6143 F-36 Vol. 2, Part 2
a -- - -- Supporting Calculations between the 135 psia calculated here and the 220 psig level, in agreement with NSAC-88 (NSAC 88). Because calculated in # 4.1, is that a more conservative friction levels can be negative with respect to instrument zero, factor was used in 4.1, while this calculation used actual level is less than measured level for actual level Moody data.] This calculation also showed that for a above instrument zero, and actual level is greater than 0.04 sq ft water LOCA, level I is reached before the measured level for actual level below instrument zero. system pressurizes above about 118 psia. Therefore, for For example, if actual level is + 10 inches, measured a large LOCA (or large, medium LOCA) opening of an level is + 13 inches. If actual level is -10 inches, SRV is not required to prevent pressurization before measured level is -13 inche . This calculation also ECCS auto-actuation is reached. concludes that with one recirculation pump in operation, the height of water in the core region is above the F.4.4 Calculation #17 minimum steam separator tumaround point so long as measured (downcomer) level is above level 3 ( + 11.4 Calculation 90-492-01:17, *SRVs for Small/ Medium inches measured). At low level 3, shutdown cooling is LOCAa in POS 5", performed the same analyses for isolated. POS 5 that calculation #6 performed for POS 4. The re-enalyses of calculation 19 agreed with the results of the Calculation 90-492-01 A:19,' Energy Balances Checked *, original calculation, except that level was calculated to be included calculations of actual and measured levels at higher due to swell. Assuming a water line break of each thermodynamic state during an energy balance calculation. Based on the derivations on Calculation #5, 0.007 sq ft (a steam line break is of no<cacern in POS 5), and complete phase separation in the vessel, and , complete mixing of core and downcomer water, the 3/casLv = v
/v . (h ar -533) system pressure / measured water level history is as follows:
where MeasLv is the measured level in inches, with (a) 135 psig and +78 inches at 4000 seconds, and ' respect to instrument zero. r is the uncompensated (b) 440 psig and +39 inches at 7200 seconds. water specific volume,0.02177 cu ft per Ibm, r,is the actual specific volume, h is the actual height of water The high measured levels at these pressures are due to relative to vessel bottom,Ed 533 inches is the distance swell of the actual level with temperature. ECCS does from vessel bo: tom to instrument zero, h is
~
not actuate until level 2, -41.6 inches measured, or level calculated from water mass as follows:
- 1. 150.3 inches measured; thus, a small (or small, l medium LOCA) will pressurize the system before ECCS h,, = Tennl . Tenn? !
injection is completely auto-initiated. This same calculation showed that if one SRV is opened for steam relief, even with a zero size LOCA, pressure never exceeds 118 psia before the level 1 ECCS actuation Tenn/ =MauUWn3/auuk (533ddaN i setpoint is reached; thus, opening an SRV prevents significant pressurization of the system. This calculation clso showed that for a 0.4 sq ft water LOCA, level 1 is reached before the system pressurizes above 50 psia; Tenn2 = @, thus, for a large LOCA (or large, medium LOCA) opening of an SRV is not required to prevent pressurization before ECCS auto-actuation is reached. where Termi is the actual water level relative to vessel bottom, not corrected for density changes. MassWtr is F.4.5 Calculation #5 water mass, InMasswtr is initial water mass, and InActLv is initial actual level with respect to instrument Calculation 90 492-01-A:5, %vels for Grand Gulf", zero. Term 2 corrects for density changes (due to swell) derived factors for converting from actual to measured where r is water specine volume, and r is initial levels, water sliecine volume. Actual level with'r"espect to instrument zero is: For 200 *F water, measured level is 1.31 times actual Vol. 2, Part 2 F-37 NUREG/CR-6143
l I Supporting Calculations pointed out that when on water solid ECCS operation, if ActLv = ho,,- 533 auto-isolation of shutdown cooling at 135 psig does not occur, and if only 1 SRV is available for relief, ADHR and measured level with respect to instrument zero is: can overpressurize (assuming a failure pressure of 160 psig, twice design rated pressure). Figure F.1-8 of this Appendix illustrates this concern. He calculation also MeasLv = 0.02177/v, . Acs/v showed that if one SRV is opened in response to a small LOCA (or no LOCA), pressure does not exceed 78 psia, a :d ADHR will not overpressurize. Note that 0.02177/r'is equal to 1.31 only for 200 degree F water. F.5 Operator Actions Calculation 90-492-01-A:16, " Update: Time for Operator F.4.6 Calculation #10 Actions POS 5", provided estimates of times available for operator actions in the event trees. Calculation 90-492-01-A:10,*1 CRD pump for POS 5H', evaluated the ability of I CRD pump to restore level or Table F.5-1 summarizes the times available for operator match steaming in POS SH. The re-analyses of actions from this calculation. calculation 19 agreed with the results of the original calculation, except that level was calculated to be higher due to swell. His calculation was performed, beca ase, as discussed in Section 3 of the main report, the det. tiled model for POS 5 assumes train A is out for maintenance. Hus, only one CRD pump is available. The calculation concluded that if forced recirculation is lost, one CRD pump can raise level to allow natural circulation in 33 minutes, and pressure is only 103 psia, below the auto-isolation setpoint of 135 psig for auto-isolation of shutdown cooling. De calculation also concluded that if the core is steamed and only one CRD pump is available for makeup, the makeup rate is insufficient to prevent core uncovery. He core uncovers by about four feet. F.4.7 Calculation #13 Calculation 90-492-01-A:13. "Over Pressurization of ADHR in POS 5', evaluated overpressurization concerns for ADHR. In comparison with RHR, ADHR has a lower failure pressure, but the maximum decay heat , when on ADHR is less than when on RHR, since ADHR cannot be used until at least 24 hours after shutdown. The re-analyses of calculation 19 agreed with the results of the original calculation, except that level was calculated to be higher due to swell. The calculation concluded that the time to overpressurize ADHR piping is similar to times calculated for overpressurizing RHR piping. He calculation concluded that the effect of having 1 CRD pump when on ADHR is similar to that when on RHR - namely,1 CRD pump can restore level for natural circulation shutdown cooling before auto-isolation or overpressurization occur. The calculation l NUREG/CR-6143 F-38 Vol. 2. Part 2
Supporting Calculations Table F.5.1 Times Available for Operator Actions: POS 5 Operator Action in Event Trees Times Available for Action RM-LT 10 hr, All Trees LCMK 2.5 hr, All Trees OPDHR 10 min, All Trees _ OPLEC Action Simultaneous with OPDHR OPSDC 37 min, All Trees OPECS, OPFLD, OPSTM 23 min each All Trees OPIS Action Simultaneous with OPSTM, All Trees OPISA Action Simultaneous with OPECS, All Trees RESCS, RESAD, RESB Action Simultaneous with OPSDC, All Trees RESRW No Time, All Trees OPSTH 4.0 hr, All Trees OPMSV 4.4 min for Trees: E, EA, ES, EP, EX, EAP, EAX, ESP,ESX 35 min for Trees: S150U SlHOU, S, SP, SX, FS, FSP,FSX Action Simultaneous with OPOSF for Trees: F. FP, FX, FNP, HWSPR OPOMS Operators will not do this event (open MSIVs) LCHPC, LC-LP 7.7 min each, All Trees OPISV Action Simultaneous with OPECS, All Trees OPHIS Action Simultaneous with OPECS, All Trees OPICT 6.4 hr but Simultaneous with OPSTM (11 hr time) for Trees: ECAOH, ECACH, ECOHP, ECOHX, ECCHP, ECCHX, EC, ECP, ECX, ECNP, ECNPL, ECACN, ECAON, CAUXN, CAUXP, CAUXX,CAUX 6.4 hr for Trees: ECAC, ECAOP, ECACP, ECACX, ECAOX, ECAO For Trees FC, FCACP, FCACX, FCAO, FCAOP, FCAOX, FCP, FCX, FCAON, FCACN, FCN: 20 min if event 'CTGOP' is 'No'; 6.4 hr if event
'CTGOP' is 'Yes*
Vol. 2, Part 2 F-39 NUREG/CR-6143
l 1 Supporting Calculations Table F.5.1 Times Available for Operator Actions: POS 5 Operator Action in Event Tree Times Available for Action OPCMT 54 hr, All Trees j OPSPM, SPMUN 13 min for Trees: ASIN ASINH, S151N, SlHIN l 11 hr for All Other Trees i OPVNT Action Simultaneous with SPMKP (11 hr) for Trees: ECAC. ECACH, ECACP, ECACX, ECCHP, ECCHX, EC, ECP, ECX, ECACN Action Simultaneous with OPCMT for Trees: FCAC, FC, FCACP, FCACX, FCP, FCX, FCACN,FCN SPMKP Action Simultaneous with OPSPM (11 hr) for Trees: ECAOH, ECACH, ECOHP, ECOHX, ECCHP, ECCHX, EC, ECP, ECX 1I hr for Trees: ECAC, ECAO, ECAOP, ECAOX, ECACP,ECACX OPSOF 20 min, All Trees CS,CSA Action Simultaneous with SPMKP, All Trees HPCAO 7.7 min, All Trees ISSSL 15 min, All Trees OPDSV No Time, All Trees OPDEP 8.7 hr, All Trees OPFLL 0.64 hr, All Trees OPHPC 7.7 min, All Trees OPNCF 8.7 hr, All Trees OPLDM 15 min for Trees: S2-5 and S2H-5 Action Simultaneous with ISSSL for Trees: S3-5 and S3H-5 OPLMS 6.4 hr, All Trees OPLST 1.7 hr, All Trees OPLil 23 sec, All Trees OPLIS 3.8 min, All Trees OPL2L 3.5 min, All Trees NUREG/CR-6143 F-40 Vol. 2, Part 2 l
Supporting Calculations Table F.5.1 Times Available for Operator Actions: POS 5 l i Operator Action in Event Trees Times Available for Action OPSLP 7.7 min, All Trees l OPSRV l.9 hr, All Trees l OPSTL 33 hr, All Trees SDCUI 8.7 hr if event 'OPDEP' not in r.equence Action Simultaneous with OPDEP if event
'OPDEP' m sequence SPC,SPCA Action Simultaneous with SPMKP, All Trees l l
ISO 89 Action Simultaneous with OPECS for Tree , HPSWA Action Not Required for Tree HPSWR , i FNWN Action Simultaneous with OPSPM (11 hr) for Trees: ECNP, ECNPL, ECACN, ECAON 35 min for Tree SNP 1 FWMAN Action Simultaneous with OPFLD for Tree FNP Action Simultaneous with OPFLL for Tree FAMN Action Simultaneous with OPSTM for TREE SNP , i r i Vol. 2, Part 2 F-4I NUREO/CR-6143
Supporting Calculations References for Appendix F [ Whitehead et al.,1991] D. W. Whitehead, J. L. [USNRC,1987] USNRC, " Standard Review Darby, B. D. Staple, B. Plan for the Review of Nuclear Walsh, T. M. Hake, and T. Power Plants," NUREG 0800, D. Brown, "BWR Low June,1987. Power t.nd Shutdown Accident Frequencies [Darby et al.,1991] J. L. Darby, et al., " Savannah Project, Phase 1 - Coarse River Site K Reactor Filter Screening Analysis," Vol.1, Heatup Model," SEA 90-500-Draft Letter Report, Sandia 007-A:1, July 31,1991. National Laboratories and Science and Engineering Associates, Inc., November 23, 1991 update, (Available in the NRC Public Document Room). l l NUREG/CR-6143 F-42 Vol. 2. Part 2
hppendix G. Calculation of the Frequency and Recovery of LOSP Plus Recovery of LOSP/DG Failures ne process used to estimate the frequency of loss of offI each single unit site, the plant centered and grid / weather I site power (LOSP) for the Low Power and Shutdown LOSP events were combined, the amount of time the unit i Program (LP&S) is similar to the one used in NUREG- is operated in low power and shutdown conditions was 1150 [1]. The only significant difference is that for the determined, the total calendar years of commercial LP&S Program the events occuring during shutdown operation were calculated, and the plant name was > conditions (i.e., the Category IV events) were used in replaced by a unique number identifier. Using this determining the frequency of LOSP for those plant interim information, the two data bases needed to start operational states (POSs) wherein the plant was shutdown the LOSP frequency calculation were constmeted by ; (i.e., POSs 2 through 7). In addition, the data base parsing the above interim data base into one containing ! used in Reference I was updated to the end of 1988 plant information for non-Category IV events and l using the information in NSAC-144 [2]. another containing Category IV events. The information j in these two data bases is presented in Tables G.I.4 and ; G.1 Calculation of the Frequency of G.I.5 respectively, j LOSP These two data bases were then processed using the same i procedures used in the NUREG-il50 analysis of LOSP l G.I.1 Process for Grand Gulf [1]. ; G.I.I.1 Overview G.I.l.2 Procedure ) The information contained in Reference 2 was examined The processing of the data which led to the LOSP to determine which events should be used in estimating frequency was done on a VAX computer. While the the frequency of LOSP for either power operation or for description given here describes the operations for a j shutdown conditions. Table G.I.1 lists the events used VAX, the detail should be sulficient to allow the reader { in determining the initiating event frequency for LOSP to translate it to a PC or any other appropriate machine. for low power and staitup conditions, and Table G. I.2 The process is described in steps with additional detail provides additional evens which must be considered given in sub-steps as appropriate. The determination of j when calculating the LOSP f.mquency (or shutdown LOSP frequency was done in two phases. The first l conditions. phase, which had nine steps, resulted in 32 point ! I frequency / probability distributions for initiating events i After the shutdown events were i;'entified, a data base of for PCGW (Plant Centered, Grid and Weather) and i all LOSP events was created. He data base includes Category IV scenarios. The second phase, which had six information on how long each plant has been in steps, used these distributions to determine the point , operation, how much time the plant has been in estimate LOSP frequency. I shutdown conditions, and the number of LOSP events th:t have occurred at the plant. Table G.I.3 presents the G.I.I.2.1 Phase 1 : information contained in this data base, j , The processing started with a file titled IE.BCK. This i In order to calculate the LOSP initiating event frequency file contained the following information for 67 plants. l for each plant operational state (POS), certain plant name, plant name abbreviation, number of PC information in Table G. I.3 was extracted and combined (plant centered) LOSP events at the plant, number of into two data bases. First, information for each multi- years the plant had been on line, number of G/W (grid unit site was combined to produce an aggregate data set or weather caused) LOSP events at the plant, and the for each plant. This process involved combining the number of years that the plant had been operational. plant centered and grid / weather LOSP events into a single number, combining the Category IV events into a Step 1. The IE.BCK file was edited to: single number, estimating the total amount of time multi-unit sites are operated in the low power and shutdown a. Add a line number for each plant entry. conditions ofinterest, determining the total site calendar years of commercial operation, and replacing the plant b. Update the number of LOSP events for each plant name (site name) with a number identifier. Next, for since the data were originally entered. Vol. 2. Part 2 G-1 NUREG/CR-6143
1 i LOSP Frequency i
- c. Add Category IV events and shutdown times. b. At the command to run the code it is only '
necessary to respond to a few simple prompts on the This file was saved under a different version number of screen. i IE.BCK in order to preserve the original data. It is , given in Attachment G-1. (1) At the plant ID input (GGNS=23) the code l summarizes the input file data for the plant and the l Step 2. The new IE.BCK was further edited to: total number of plant years for the whole file. (2) At the prompt "If you know the value of the {
- a. Delete plant names and abbreviations (the line constant..." input 2 to let the code determine it.
numbers served as plant identifiers in subsequent (3) At the prompt " Input the failure frequency..." steps). input the best estimate (a guess based on i engineering judgement) for LOSP. The code will
- b. Combine PC and G/W events (the occurrences retum the cumulative probability for LOSP for the were added). input failure frequency.
(4) Iterate on the failure frequency of step (3) I
- c. Delete the on-line time. until a cumulative probability of .99900 is obtained.
This file was saved under still another IE.BCK version (5) When .99900 is obtained number. It is given in Attachment G-2. (a) Record the input failure frequency. (b) Enter "Y" at the prompt "Is this Step 3. The latest IE.BCK file was then edited to: satisfactory?" (c) The .99900 value for PC/GW for GGNS
- a. Delete Category IV events. was found to be .416. .
l
- b. Delete shutdown times. A copy of the screen and prompts is included in Attachment G.5. ,
nis file contains the data for the non-Category IV LOSP ! events. It was saved as LOSP_lE_PCGW.DAT and is Step 6. In preparation for running the IEBATI code, given in Attachment G-3. and input file for the code , LOSP_IE,,,PGCW.INP, was prepared. This input file consisted of a single line which Step 4. The latest IE.BCK file was again edited to: contained:
- a. Delete the operating time. a. The file containing the PC/GW data for the listed plants enclosed in single ticks.
- b. Delete the PC and G/W events,
- b. Plant ID number. i nis file was saved as LOSP_lE_IV.DAT. It contained the Category IV initiating events. It is given in c. The failure frequency for the .999 LOSP Attachment G-4. probability obtained in Step 5.b.(4) above. t t
Step 5. The program lEFREQl.EXE was run for d. The number of points to output. I PC/GW data. This is an interactive program that calculates the cumulative probability for LOSP for a user The single line was: , specified failure frequency at a user specified plant. The plant is identified by the line number in the input file. 'LOSP_lE_PCGW.DAT' 2.i .416 30
- a. The code requires a data base from which to The IEBATI code produces an initiating event draw basic plant data for the initiating event. For probability distribution for a range of failure frequencies the PC/GW events the LOSP_lE_PCGW.DAT file from near zero to the frequency .999 frequency was copied to IE.DAT (Attachment G-5) and determined in Step 5.b.(4) above. The number of output ;
IE.DAT was used as input. The file title IE.DAT is points is specified by the last entry of the single line i the input file title hard-wired into the code. input file. 'ine input file is given in Attachment G-6. L NUREG/CR-6143 G-2 Vol. 2. Part 2 N__ ___ _ _ _
LOSP Frequency Step 7. The IEBAT.COM file (Attachments G-7, G 7A (b) Puts the 1006 output points from LHS into a 20 bin histogram. & G-7B) was created to run IEBAT1. This file: This file is used as a diagnostic tool to assure the
- a. Renames LOSP_lE_PCGW.INP to IEFREQ.INP, the name of the input file hard-wired analyst that the 1000 points fit a distribution that into IEBAT1. makes sense.
- b. Runs IEBATI. b. Prepare LHS.INP (Attachment G-19), the input file to LHS:
- c. Renames IEFREQ.INP back to TITLE -(Specify Title of Analysis)
LOSP_IE_PCGW.INP. RANDOM SEED (Specify a 10 digit integer)
- d. Renames the plot file of frequency and IE NOBS 1000 (no. of observations desired) probability produced by *b8AT1, PLOT.DAT, to RANDOM SAMPLE (LilS Option)
USER DISTRIBUTION IE_PCGW.DAT (Attachment G-8).' IE_PGCW.DAT (I line w/above) Once the COM file for IEBATI was completed, the file USER DISTRIBUTION IE_IV_.DAT was executed producing the above mentioned .DAT file. OUTPUT HIST Step 8. IE_PCGW.DAT was updated to include c. Edited SUBROUTINE USRDST (Attachment G-probabilities of 0.0 and 1.0. This was done by plotting 20): the 30 output points of IEBATI and, using engineering Four lines were edited to specify input files and titles judgement, extrapolating the resulting curve to 0.0 and in FORM AT statements. 1.0. See Attachment G-9. (1) Nested IF: Step 9. Steps 6-9 were repeated for Category IV data. IF(IFLAG.EQ.1)OPEN(UNIT =60, FILE File titles had IV instead of PCGW in them. Otherwise, = IE_PCGW.DAT'....) the process was exactly the same. The input and output files for the Category IV analysis are given in (2) 12 FORM AT ('I',/,/.6X, Attachments G-10 through G-17. ' INPUT DATA FOR IE_PCGW',/...) G.I.l.2.2 Phase 2 (3) ELSEIF(J.EQ.2)THEN IF(IFLAG.EQ.2)OPEN(UNIT = 61, FILE 3' ne second phase of the process produced 1000 point = IE_IV',/...) distributions for the PCGW and Category IV scenarios from the 30 point distributions determined in Phase 1. (4) 16 FORM AT('l',/,/,6X,*lNPUT DATA ne files IE_PCGW.DAT and IE_IV.DAT produced in FOR IE_IV',/...) the first phase were used as input to the LHS code to produce 1000 point distributions. Step 2. Run LHS with the above files: Step 1. Preparation for the LHS run. a. Compile USitDST
- b. Link USRDST to LHS
- a. Prepared LHS.COM (Attachment G-18): c. Run LHS.COM (i.e. @ LilS)
ASSIGN LilS.DAT FOR001 Step 3. LilS Outputs ASSIGN LilS.INP FOR005 ASSIGN LilS.OUT FOR006 a. LHS.OUT-Described above RUN LilS b. LilS.DAT - 4 columns,1000 lines DELETE FOR*.D AT;* (1) Line Number (2) No. of data points in the line (1) LilS.D AT is the 10Gu poi,8 output from LHS. (3) PCGW value (2) LilS.OUT is a histogram outp9t f,ie that (4) Category IV value. (a) Lists IE_XXX.DAT data. Vol. 2, Part 2 G-3 NUREG/CR-6143 l 1 i l
i LOSP Frequency LHS.OUT and LHS.DAT are given in Attachments G-21 Step 5. Prepare TEMAC input file. The Cat IV data and G-22. was removed from LHSLOSP.INP by a second REMOVECOL program (Attachment G-27). This left Step 4. The analysis requires the combined values of the just the PC/GW data. This file was stored as PC/GW and Category IV data. Thus, the two data sets PCGWLOSP.DAT (Attachment G-28). were added. Step 6. The STAT.SAS program (Attachment G-29)
- a. LHS.DAT was edited to remove the first and was run on LHSLOSP.DAT and PCGWLOSP.DAT.
second columns. This required the use of the PROC UNIVARIATE was specified for the two files to program REMOVECOL2.FOR (Attachments G-23). determine the statistical characteristics of the data in each. Among the outputs was the mean value of the data (1) The program input is LHS.DAT. 'Ihis file which was used as the point estimate for the LOSP name is hard wired into the program. frequency in the ensuing PRA analyses. The outputs are given in STAT.LIS, Attachment G-30. (2) The output file is LHSLOSP.INP (Attachment G-24). This is also hard wired into the program. Step 6 completed the LOSP frequency point estimate The output is two columns of data, PC/GW and calculation. CAT IV. G.I.2 Results
- b. Using LHSLOSP.lNP as input, the program LHSADDITION (Attachment G-25) was run to add Using the above process, the mean frequency for LOSP the PGCW and Cat IV columns. The output was in POS I was calculated to be 0.0649. For POSs 2-7 it contained in LHSLOSP.DAT (Attachment G-26). was 0.1235.
The two file names are hard wired into LHSADDITION. NUREG/CR-6143 G-4 Vol. 2 Part 2
l LOSP Frequency Table G.1.1 Loss of Offsite Power Events Used to Estimate Frequency During POS 1
# PLANT SY CAT DATE DURATION FREQ? RECOV?
! ANO 2 PC 09/16n8 1.480 F R i 2 Beaver Valley 2 PC 07/2808 0.280 F R ,
3 Big Rock Point 3 G 01/25n5 0.333 F R 4 Brunswick 2 PC 03/26/75 0.070 F R 5 Calvert Cliffs 3 PC 07/23/87 1.970 F R 6 Davis Besse ! PC 11/29/77 0.002 F R 7 Davis Besse 1 PC 10/15/79 0.430 F R 8 Diablo Canyon 1 PC 07/17/88 0.633 F R 9 Dresden 2 W 11/12/65 4.000 F R 10 Dresden 2 PC 08/16/85 0.083 F R II Farley 3 PC 09/16/77 0.900 F R 12 Farley 3 PC 10/08/83 2.750 F R 13 Fort Calhoun 3 PC 02/21/76 0.900 F R 14 Fort Calhoun 3 PC 08/22/77 0.015 F R 15 Fort St. Vrain 3 W 05/17/83 1.750 F R 16 Ginna 2 PC 03/04/71 0.500 F R 17 Ginna 2 PC 10/21/73 0.670 F R 18 liaddam Neck 1 PC 04/27/68 0.480 F R 19 liaddam Neck I PC 07/15/69 0.150 F R 20 liaddam Neck 1 PC / 07/19'72 0.017 F R 21 liaddam Neck 1 PC 01/19/74 0.330 F R 22 liaddam Neck 1 PC 06/26/76 0.270 F R 23 liaddam Neck 1 PC 08/01/84 0.167 F R 24 Indian Point 3 G 11/09/65 - F 25 Indian Point 3 G 07/20 '2 0.920 F R l 26 Indian Point 3 G 07/13n7 6.470 F R Vol. 2 Part 2 G-5 NUREG/CR-6143
LOSP Frequency Table G.I.1 Loss of Offsite Power Events Used to Estimate Frequency During POS 1 (Continued)
# PLANT SY CAT DATE DURATION FREQ? RECOV?
27 Indian Point 3 PC 06/03/80 1.750 F R 28 Indian Point 3 PC 06/03/80 0.500 F R , 29 McGuire 2 PC 08/21/84 0.334 F R 30 Millstone- 1 PC 07/21/76 0.080 F R , 31 Millstone 1 W 08/10/76 5.000 F R 32 Millstone 1 W 09/27/85 5.500 F R 33 Monticello 1 PC 04/27/81 0.250 F R 34 Nine Mile Point 1 PC 11/17/73 0.003 F R 35 Nine Mile Point i PC 12/26/88 0.150 F R i 36 Oconee 1 PC 01/04/74 0.013 F R 37 Oyster Creek 2 PC 09/08/73 0.003 F R 38 Palisades 3 PC 09/02/71 0.930 F R I 39 Palisades 3 PC 09/24/77 0.500 F R i 40 Palisades 3 PC 07/14/87 7.430 F R 41 Palo Verde 3 PC 10/03/85 0.400 F R 42 Palo Verde 3 PC 10/07/85 0.200 F R 43 Pilgrim 1 W 05/10/77 2.670 F R 44 Pilgrim 1 W 02/06/78 8.900 F R 45 Pilgrim 1 W 11/19/86 4.317 F R 46 Pilgrim 1 W i1/12/87 11.000 F R , 47 Point Beach 2 PC 02/05/71 0.130 F R i 48 Point Beach 2 PC 04/27/74 0.020 F R l 49 Prairie Island 2 PC 07/15/80 1.030 F R 50 Quad Cities 3 PC 11/06/77 1.150 F R 51 Quad Cities 3 PC 06/22/82 0.570 F R 52 River Bend 3 PC 01/01/86 0.767 F R l NUREG/CR-6143 G-6 Vol. 2. Part 2 t l l
1 i LOSP Frequency Table G.1.1 Loss of Olisite Power Events Used to Estimate Frequency During POS 1 (Continued)
# PLANT : SY CAT DATE DURATION FREQ? RECOV?
l 53 Robinson 3 PC 01/28/86 1.667 F R l 54 San Onofre 3 PC 11/22/80 0.004 F R 55 San Onofre 3 PC 11/21/85 0.067 F R 56 St. Lucie 2 G 05/16n7 0.330 F R 57 St. Lucie 2 G 05/16/77 1.500 R 58 St. Lucie 2 G 05/14n8 0.130 F R 59 Susquehanna 1 PC 07/26/84 0.183 F R 60 Turkey Point 2 0 04/03n3 0.300 F R 61 Turkey Point 2 G 04/04n3 0.250 F R 62 Turkey Point 2 G 04/2504 0.330 F R 63 Turkey Point 2 G 06/28/74 0.180 F R 64 Turkey Point 2 G 05/16'/77 1.030 F R 65 Turkey Point 2 G 05/16/77 2.000 F R 66 Turkey Point 2 PC 02/12/84 0.250 F* R* 67 Turkey Point 2 PC 02/16/84 0.250 F R 68 Turkey Point 2 G 05/17/85 2.083 F R 69 Yankee Rowe 3 G 11/09/65 0.550 F R C%is event is used in the LOSP calculation for power ohration and startup only, not for the shutdown states. l i Vol. 2, Part 2 G-7 NUREG/CR-6143
LOSF Frequency Table G.1.2 Additional Loss of Off-Site Power Events Used to Estimate Frequency During POS 2 - 7 ; r
# PLANT SY CAT DATE DURATION FREQ? RECOV
? }
I Brunswick 2 PC 04/26/83 0.283 F R L 2 Fitzpatrick 1 PC 04/10/78 0.004 F R 3 Fitzpatrick 1 PC 03/27/79 0.050 F R 4 Fitzpatrick 1 PC 10/31/88 1.000 F R 5 Ft. Calhoun 3 PC 03/13/75 11.083 F R I 6 Indian Point 3 PC 11/16/84 0.233 F R 7 Haddam Neck 1 PC .08/24/84 0.367 F R 8 McGuire 2 PC 09/16/87 0.417 F R 9 Monticello 1 PC 06/04/84 0.033 F R 10 Oyster Creek 2 PC 11/14/83 4.000 F R 11 Palisades 3 PC 01/08/84 2.683 F R 12 Point Beach 2 PC 10/13/73 - F 13 Point Beach 2 PC 10/22/84 0.050 F R 14 Quad Cities 3 PC 05/07/85 0.717 F R 15 Salem 2 PC 06/05/84 2.000 F R 16 San Onofre 3 PC 06/07/73 4.983 F R 17 San Onofre 3 PC 04/22/80 F 18 Turkey Point 2 PC 04/29/85 F 19 Yankee Rowe 3 PC 05/03/84 0.117 F R I i NUREG/CR-6143 G-8 Vol. 2, Part 2 I
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! y Table G.I.3 Informational Worksheet for LOSP Calculation (Continued) {
m
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$ plant Start % % End Optimme Omane Mndmatie Caamassas eye haw Cat. FF MsMP 3D Madsp j M Daae Cap- Avail. the LDSP ID6F IV h h h h >
! b I devabensel Jul-78 0.4 0.52 Dec-88 10.51 4.2 4.2 2 0 0 5.46 5.46 5.04 5.04 M E.a t. < doblecesryant May-85 0.7 0.79 De88 3.67 2.57 3.16 1 0 0 2.9 3.35 0.77 1.31 diablocanyon2 Mar-86 0.69 0.76 h88 se 1.% am 2.16 mm 0.68 . ma 1
- drendent Aug.60 na un Dec.88 en an en . an na en as i dre= den 2 Jun-70 0.58 0.72 h 88 18.6 10.79 14.83 1 1 0 13.37 16.68 5.23 9. 8 drenden) Nov-71 0.56 0 69 Dec-88 mm 9.62 as 11.78 en 5.39 as duasuarneW M75 0.55 0 69 Dec.82 13.92 7.66 7.66 0 0 0 9.62 9 62 4.3 4.3 fadeyt Dec-77 0.7 0.73 Dec-88 11.09 7.76 9.63 2 0 0 8.I 9 84 2.99 3.76 farley2 Juk81 0.83 0.86 Dec-88 mm 6.23 na 6.46 mm 1 05 en l l Fermi 2 as as na h88 na en as seempyet as en na em i
!, O. 0 9.59 9.59 3.92 3.92 g fitryetru.k Jul.75 0.65 0.71 h 88 13.58 8.78 8.78 0 3 0.77 14.59 9.92 9.92 2 0 t 11.19 11.19 3.4 3.4 for e " h 74 0.68 Dec.88 t [ 9.51 1.33 1.33 0 0 2.85 2.85 6.66 6.66 j fortstvrain Jul-79 0.14 0.3 Dec-88 1 13.7 2 0 0 I4.2 14.2 4.31 4.31 ginna Jul-70 0.74 0.77 Dec88 18.52 13.7 2.42 G 0 0 2.35 2.35 1.16 1.16 grarutgulft J35-85 0.69 0.67 Dec-88 3.5 2.42 6 0 17.19 17.19 4.24 4.24 h k Aug67 0.78 0.8 Dec-88 21.43 16.72 16.72 1 7.72 10.06 0 0 G 8.81 19 93 4.28 6.2I i hasch! Dec 75 0.59 0 67 Dec-88 13.09 5.7 na 6.47 mm 2.57 mm hasA2 Sep-79 0.61 0.69 Dec-88 na 0 0 0 1.67 1.67 0.37 0.37 Dec-86 0.79 0.82 Dee88 2.03 1.61 1.61 ? lv.a eumlows en am na en Aug43 Dec-88 na na na
%7 na en 2 3 I 9.67 12.18 4.76 8.16 ind' _ , . ..J? Aug.74 0.61 0 67 Dec-88 14.43 8.8 11.77 4 _
- 2. 7.61 mm 7.61 am 5.07 na y ind , - _ _t May-76 0.6 0.6 Dee88 na 0 0 0 12.27 12.27 2.32 2.32 Dec88 14.59 11.82 11.82
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-peacbet2 34 74 05 0.57 b88 14.51 7.26 10.99 0 0 0 8.27 11.91 6.24 9.45 4 peaMon3 -Dec 74 0.53 0.6 t h 88 mm 7.47 an 8.46 em 5 64 na perryl Nov-87 0 68 0.76 A 88 1.12 0.76 0.76 0 0 0 0.85 0.85 0.27 0.27 pdsrirni Dec-72 0.46 0.55 b88 16.09 7.4 7.4 0 4 0 8.85 8.85 7.24 7.24 poetbeecht Dec-70 0.7) 0 81 h88 18.1 13.21 16.77 2 0 2 14 66 17.33 3.44 5.23 pointhench2 Oct.72 0.81 0.86 Dec 88 am 13.17 as 14 05 na 2.21 en preirwal Dec-73 0.79 0 83 Dec-88 15.09 11.92 14 4I 1 0 0 12.53 14.61 2.57 4.11 promem2 Dec-74 0 84 0 87 Dec-88 ne !I.84 na 12.23 na 1.86 no gandenseil Feb-73 0 66 0.78 Dec-88 15.92 10.51 13.88 2 0 1 12.36 15.02 3.57 6.63 qun&staes2 Mar-73 0.63 0.75 Dec-88 na 99 as 11.9 na 3.95 mm O.
y rendweeco Apr-75 0. 4 0.47 Dec.88 13.76 5.5 5.5 0 0 0 6.47 6.47 7.29 7.29 rwerbend t Jun 86 06 0.69 b88 2.59 1.55 1.55 1 0 0 1.78 1.78 0. 8 0.8 robsenn2 Mer-71 0.64 0.7 Dec-88 17.85 11.42 11.42 1 0 0 12.48 12.48 5.37 5.37 eslesn t Jun 77 0.55 0.62 h 88 11.59 6.38 8.04 0 0 1 7.19 8.81 4.4 6.25 malern2 Oct 81 0.51 0 59 b88 as 3.7 na 4.28 na 2 97 en sanonofrel Jan-68 0.52 0.56 Dec-88 21.01 10.93 13.19 2 0 2 11.77 13.9 9.25 10.74 annonofre2 Aus-.s 0.69 0.71 A 88 em 3.74 na 3.85 na 1.57 ma annonofre3 Jen-84 0.63 0 69 Dec-88 nm 3.15 na 3.45 na 1.55 na 0.57 7.51 2.48 e.24 0 0 0 4.23 5.58 3.23 5.26 semel Jul-81 0.33 Dec.88 sequoyah2 Jun. 82 0.4 0.46 Dec-88 na 2.64 na 3.03 na 3.56 na 1.67 1.15 I.15 0 0 0 1.23 1.23 0.44 0.44 ehreronharrul May 87 0 69 0.74 Dec-88 4 1 g .horchers n. n. n. Dec 88 ne n. - notupre na n. e. n. 8.62 9.98 0 2 0 8.89 10.16 3.2 3.78 ethsciel Dec-76 0.71 0.74 Dec98 12.09 2 ta
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Z r , C O E Table G.I.3 Informational Worksheet for LOSP Calculation (Continued) 5 9 7 9 + StartDate = Beginning Date of Conunercial Operation [ Nuclear Safety, Vol. 28, No. 4] $ h% Cap = Cumulative Plant Capacity Factor [ Nuclear Safety, Vol. 30, No. 2] @ O + End Date = End Date of Analysis, December 31,1988 x
+ Optime = Site Calendar Years of Commercial Operation (End Date - StartDate)
Online = Optime times the Capacity Factor Modonline = Effective Online Time for Multiple Unit Sites
+ PC LOSP = Number of Plant-Centered LOSP Occurring at Site During Optime
+ G&W LOSP = Number of Grid and Weather Events Occurring at Site During Optime
+ Cat IV = Number of Category IV Events (Unique to Shutdown) Occurring at Site During Optime FP time = Optime times the Availability Factor modFPtime = Effective FP time for Multiple Unit Sites
+ SDtime = Optime times (1 - Avail Factor)
+ modSDtime = Effective SD time for Multiple Unit Sites
+ Parameter Used in Shutdown Study LOSP Calculation 9
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LOSP Frequency Table G.I.4 Non-Category IV Event Data Plant No. Events Site Years Plant No. Events Site Years 1 1 14.09 51 2 21.01 2 1 12.25, 52 0 7.50 3 1 25.85 53 2 12.09 4 0 14.42 54 0 1.69 5 1 13.17 55 0 5.00 6 0 3.33 56 0 16.09 7 0 4.08 57 1 5.59 8 1 13.68 58 0 14.34 9 0 3.58 59 0 12.67 l 10 0 1.10 60 9 16.09 11 0 13.42 61 0 16.17 12 0 14.51 62 0 1.58- , 13 0 11.84 63 0 4.08 14 0 10.51 64 0 3.33 15 1 3.67 65 0 3.33 i 16 2 18.59 66 1 28.18 l 17 0 13.92 67 0 15.09 : 18 0 11.09 19 0 13.51 l 20 2 14.59 21 1 9.51 i 22 2 18.51 ! 23 0 3.50 ' 24 6 21.43 25 0 13.09 26 0 2.03 l 27 5 14.42 28 0 14.59 29 0 5.00 30 0 2.92 31 0 16.09 32 1 7.08 l 33 3 17.85 34 1 17.59 l 35 2 19.09 36 0 10.59 ) 37 1 15.51 l 19.09 1 38 1 39 3 17.09 40 2 2.91 41 0 14.51 42 0 1.12 43 4 16.09 44 2 18.09 ) 45 1 15.09 l 15.92 ! 46 2 47 0 13.76 ; 48 1 2.58 49 1 17.85 ( 50 0 11.59 l L ; Vol. 2. Part 2 G-15 NUREG/CR-6143
l LOSP Frequency Table G.1.5 Category IV Event Data Plant No. Events Site Years Plant No. Events Site Years 1 0 6.18 51 2 10.74 2 0 4.83 52 0 5.26 3 0 7.60 53 0 3.78 4 0 12.69 54 0 0.44 5 1 7.97 55 0 1.35 6 0 0.98 56 0 9.41 7 0 0.65 57 0 2.03 8 0 4.87 58 0 8.32 9 0 1.77 59 0 4.44 10 0 0.18 60 1 9.01 11 0 6.23 61 0 3.56 12 0 3.77 62 0 0.40 13 0 4.38 63 0 1.14 14 0 5.04 64 0 0.73 15 0 1.31 65 0 0.90 16 0 9.10 66 1 5.92 17 0 4.30 67 0 7.58 18 0 3.76 19 3 3.92 20 1 3.40 21 0 6.66 22 0 4.31 23 0 1.16 24 1 4.24 25 0 6.21 26 0 0.37 27 1 8.16 28 0 2.32 29 0 3.12 30 0 0.52 31 0 3.65 32 1 3.14 33 0 7.35 34 1 4.05 35 0 6.30 36 0 4.40 l 37 0 9.00 38 1 7.07 39 1 8.55 1 40 0 1.53 l 41 0 9.45 l 42 0 0.27 43 0 7.24 44 1 5.23 45 0 4.11 46 1 6.63 f 47 0 7.29 48 0 0.80 49 0 5.37 50 1 6.25 NUREG/CR-6143 G-16 Vol. 2, Part 1
LOSP Frequency . G.2 Determination of the Mean updated were P(l), a weighting function for each PC L SP category; S(l), a sample mean term for each PC i Probability of Recovery from LOSP category; and N(1), the number of events in each LOSP at Different T,meS i PC LOSP category. The values are different for each of ' the three PC LOSP types and, in the MODEL code, G.2.1 Process reside in different branches of an IF-THEN-ELSE statement (Statement 13). The variable NPC (just below G.2.1.1 Overview . Statement 12) wes changed to 62, the updated number of PC LOSP events. A copy of the MODEL.FOR code is This section contains a summary of the methodology used given in the Attchment G-37. to determine the times to recover from a LOSP event at the Grand Gulf Nuclear Station (GGNS) and the mean The P(N) and S(N) terms are statistical characteristics of probabilities of recovery at the different times. The the PC LOSP recovery time populations. They were report covers all LOSP events up to 1988 and includes determined using the program GAMM A. GAMM A is an Category IV (Shutdown) events summarized in Reference interactive program that prompts the user for an input l
- 2. He steps used to determine these recovery times and file which contains data for which the user requires the probabilities are given below. Maximum Likelihood Estimates of the Geometric and ,
Sample Means. The input files for the LOSP recovery G.2.1.2 Procedure analyses were the GGXXX.DAT files containing the : recovery times for the six types of LOSP events. The Step 1. The LOSP events listed in Reference 2 were output of the code is written to the file MLE.OUT. In categorized by type: Plant Centered (PC), Grid (G), and the case of the PC LOSP events,the output " Geometric Weather caused (W). Plant centered events are those in Mean" is the P(l) value for the corresponding , which the design and operational characteristics of the GGPCN.DAT data. The output " Sample Mean* is the plant played a role in the LOSP and its duration [3). S(l) value, and N(1)is the Sample Size. Copies of Grid caused events are those in which the design and GAMM A.FOR and MLE.OUT are given in Attachments operational characteristics of the power grid from which G-38 and G-39. the plant draws its off-site power are a factor. After the changes were incorporated into MODEL.FOR, Six data files (Attachments G G-36) were it was compiled and linked to two libraries, AMOSLIB constructed for the LOSP recovery times. One contained (see Attachment G-40) and IMSLIBS/ LIB [5] and run. the recovery times for grid events (GGGRID.DAT) and The MODEL output was written to the file GG.DAT another contained the recovery times for weather events (Attachment G-41). This file contained the probabilities (GGWEAT.DAT). The plant centered events were of recovery from LOSP at different times for the three subdivided into three subsets based on switchyard categories of LOSP events. j configuration classifications defined in NUREG-1032 [4]. The three data files for these three subsets were Step 3. He results of the MODEL calculations were GGPCI.DAT, GGPC2.DAT, and GGPC3.DAT. A plotted using the program MAPPER, a graphics routine. fourth PC file containing all of the recovery times of the The GG.DAT file was copied to a file for M APPER I first three was also established. This file was , input called M AP.DAT. The plot contained curves for l GGPC4.DAT. He recovery times are also summarized the fifth,50th and 9Sth percentiles of the recovery times. I in Table G.2.1. The plot is shown in Figure G.2-1. ! Step 2. The program MODEL was run to calculate the Step 4. The program COMMEAN was run using the ; probabilities of recovery from LOSP at different times M AP.DAT file a input. The program uses a lognormal from each of the three categories. MODEL is an distribution routine to calculate the error factor (EF) and int:ractive program that implements the mixture model the mean probability for recovery from LOSP at the for the distribution of the recovery from LOSP as different time steps in the MODEL output. The results developed in Reference 3. The program has a number of of the calculation are stored in LOGNORM AL.DAT. vclues hardwired into it. These values were updated to COMMEAN also creates a file called MEAN.DAT reflect the most recent data on the occurrence of and which is essentially LOGNORMAL.DAT without the recovery from LOSP events (including Category IV column headings. Listings of COMMEAN.FOR and events)in the United States as of 1988. The values LOGNORM AL.DAT are included in the Attachments G. Vol. 2, Part 2 G-17 NUREG/CR-6143
LOSP Frequency 42 and G 43. Step 5. Finally, the probability of recovery was plotted against the mean time to recover. This plot is given in Figure G.2.2. G.2.2 Results Using the process outlined above, the mean probability of recovery of LOSP versus time was determined and recorded in Table G.2.2 and plotted as shown in Figure G.2.2. l l i I i l NUREG/CR-6143 G 18 Vol. 2, Part 2 i
LOSP Frequency ' Table G.2.1 Time to Recover from LOSP through 1988 i i Plant Centered Plant Centered Plant Centered Grid Severe Switchyard Group 1 Switchyard Group 2 Switchyard Group 3 Recovery Weather Recovery Times (hrs) Recovery Recovery Times (hrs) Times (hrs) Recovery Times (hrs) Times (hrs)
.002 .070 1.970 .130 1.750
.003 1.480 .900 .180 2.670
.904 .280 2.740 .250 4.000
.033 .083 .900 .300 4.317
) .050 .500 .015 .330 5.000
.330 .670 1.753 .330 5.500
.367 .334 .500 .333* 8.900 1.000 .003 .930 .550 11.000*
.430 .130 .500 .920
.663 .020 7.430 1.030
.270 1.030 .400 1.500
.167 .250 .200 2.000
.080 .250 1.150 2.083
.250 .283 .570 6.470
.150 .417 .767
.013 4.000 1.667
.I83 .050 .004
.480 2.000 .067
.150 11.083
.017 .233 2.683 4.983
.I17
.717 Vol. 2. Part 2 G-19 NUREG/CR-6143
a s in R ECOV ERY CU RV E rO R GR A 4] GULF :.a
% 3 4
5 1-0.8 - m M Ai 0.6 - 0 W 2 0.4 - v 1 0.2-0 , i i i , i 0 5 10 15 20 25 30 TIME TO RECOVER LOSP b Figure G.2-1 Pn>bability of Recovery from LOSP vs Time for the Fifth, the Fiftieth and the Ninety-fifth Percentiles
; LOSP Frequency , Table G.2.2 Mean Probability of Recovery from LOSP at Different Times Time EF Mean Time EF Mean 0.00 1.0 1.000E + 00 2.50 1.8 8.706E-02 0.05 1.2 7.501E-01 2.75 1.9 8.010E-02 0.10 1.2 6.370E-01 3.00 1.9 7.453E-02 0.15 1.2 5.564E-01 3.17 1.9 7.066E-02 0.20 1.3 4.958E-01 3.50 2.0 6.528E-02 0.25 1.3 4.472E-01 3.75 2.1 6.247E-02 0.30 1.4 4.069E-01 4.00 2.1 5.898E-02 0.35 1.4 3.697E-01 4.25 2.2 5.575E-02 0.40 1.4 3.404E-01 4.50 2.2 5.284E-02 0.45 1.4 3.146E-01 4.75 2.3 5.054E-02 0.50 1.4 2.921E-01 5.00 2.3 4.828E-02 0.55 1.4 2.720E-01 5.25 2.4 4.652E-02 0 60 1.5 2.54BE-01 5.50 2.5 4.526E 02 0 65 1.5 2.396E-01 5.75 2.5 4.336E-02 0.70 1.5 2.266E-01 6.00 2.6 4.I41E-02 0.75 1.5 2.160E-01 6.25 2.6 3.970E-02 0.80 1.5 2.053E-01 6.50 2.7 3.840E-02 0.85 1.5 1.962E-01 6.75 2.8 3.725E-02 0.90 1.5 1.885E-01 7.00 2.8 3.603E-02 0.95 1.5 1.801E-01 7.25 2.9 3.474E-02 1.00 1.5 1.730E-01 7.50 3.0 3.346E-02 1.05 1.5 1.671E-01 7.75 3.1 3.242E-02 1.10 1.5 1.614E-01 8.00 3.2 3.151E-02 1.13 1.5 1.575E-01 8.25 3.2 3.022E-02 1.20 1.6 1.523E-01 8.50 3.3 2.910E-02 !
1.25 1.6 1.483E-01 8.75 3.4 2.798E-02 l 1.28 1.6 1.451E-01 9.00 3.5 2.708E-02 i 1.33 1.6 1.416E-01 9.25 3.6 2.640E-02 1.40 1.6 1.365E-01 9.50 3.7 2.559E-02 1.45 1.6 1.329E-01 9.75 3.8 2.503E 02 1.50 1.6 1.290E-01 10.00 3.9 2.430E-02 1.55 1.6 1.257E-01 13-30 6.2 1.970E-02 1.60 1.7 1.230E-01 15.00 7.7 1.780E-02 1.65 1.7 1.203E-01 16.00 8.8 1.682E-02 1.70 1.7 1.173E-01 18.00 11.5 1.597E-02 1.75 1.7 1.147E-01 23.00 22.1 1.476E-02 1.80 1.7 1.124E-01 27.00 32.8 1.328E-02 1.85 1.7 1.098E-01 1.90 1.7 1.077E-01 1.95 1.7 1.051E-01 2.00 1.7 1.032E-01 2.05 1.7 1.0llE-01 2.10 1.8 9.923E-02 x 2.15 1.8 9.724E-02 2.20 1.8 9.540E-02 2.25 1.8 9.410E-02 2.30 1.8 9.273E-02 2.35 1.8 9.120E-02 2.40 1.8 8.973E-02 2.45 1.8 8.832E-02 Vol. 2, Part 2 G-21 NUREG/CR-6143
E 5 a m l RECOVERY CURVE FOR GRAND GULF j' sm - 1-0.8 - C' y 0.6 - S w 2 E a. 0.4 - 0.2 - 0 i i i i i i 0 5 10 15 20 25 30 MEAN TIME TO RECOVER LOSP f 3 Figure G.2-2 Mean Prvbability of Recovery from LOSP vs Time at Grand Gulf _w
LOSP Frequency G.3 Determination of Recovery determination of an interpolating polynomial using Newton's Interpolatory Algorithm [4 Ws polynondal Values for LOSP/DG-Failure was of the form. Restorations: DG Fails to Start ' y(x) = E,.i Q,,If*.' (x-x,) l l G.3.1 Process G.3.1.1 Overview where: y= In(P,) The following process describes the steps carried out in x= In(1 + t) the calculation of the non-recovery probabilities for t= time at which LOSP occurs. LOSP accompanied by the failure of the diesel generators to start. The process assumes that the DGs The expression for x has a 1 in the in argument because were called for at the onset of LOSP. t may be set to zero. ,
%e calculations consider failure to start due to Step 2. Data for the probability of non-recovery of hardware failures and due to common mode failures. diesel generators after their failure to start were plotted .
j The results of the calculations are tables of non- [8]. Two cases were considered: a) failure to start due recovery probabilities vs. time after the DG(s) fail to to a hardware failure; and b) failure to start due to a f start. common mode failure. In both cases a linear fit was . made of In(P the log or the probability of non- I The correction factor (or recovery factor) for the recovery of tffe"b),G after failure to start vs. time fl recovery from LOSP and failure of diesel generators to the failure to start. Thus: stort at time T (CF,) is given by CFm(T) = P,,,(T) . Pa(T) P,,c, (T) - exp (m T) where: P ,(T) = probability of non-recovery of off. where: m = slope of the N? (T)J graph T = time since failure,to start. site power at time T after LOSP. P ,(T) = probability of non-recovery of DG Step 3. A table of values for CF,3 was formed from at time T after LOSP. the product: G.3.1.2 Procedure CF, = exp bn'.P ,(T)]} Un[P,(T)]} I l Step 1. Data for the probability of non-recovery of off-site power versus time were plotted. for values of T from 0 to 24 hours in half-hour time steps. The plot was in the form Analyses requiring a value between the half-hour in(P,) vs. T increments was either interpolated from the table or calculated directly from the equations (curve fits) for P, where: and P ,. P, = probability of non-recovery of off-site power. G.3.2 Results T= time required for recovery after which core The table of results is given in Table G.3.1. j damage is to be expected. A second treatment of the data involved the Vol. 2. Part 2 G-23 NUREG/CR-6143
)
l LOSP Frequency Table G.3.1 Correction /, Recovery Factors for DG Fails to Start (LOSP as Initiating Event) Time (hr.) Hardware Common Mode 0 1 1
.5 2.988E-1 2.945E-1 1.0 1.5298E-l 1.4861E-1 1.5 9.9556E-2 9.5127E-2 2.0 7.3188E-2 6.9064E-2 2.5 5.8076E-2 5.4015E-2 3.0 4.8821 E-2 4.4294E-2 3.5 4.1504E-2 3.7498E-2 4.0 3.6452E-2 3.2460E-2 4.5 3.2535E-2 2.8555E-2 5.0 2.9389E-2 2.5422E-2 5.5 2.6788E-2 2.2839E-2 i l
6.0 2.4589E-2 2.0662E-2 6.5 2.2695 E-2 1.8796E-2 7.0 2.1038E-2 1.7173E-2 7.5 1.9570E-2 1.5745E-2 8.0 1.8257E-2 1.4477E-2 8.5 1.7072E-2 1.3342E-2 9.0 1.5994E-2 1.2320E-2 9.5 1.5008E-2 1.1394E-2 10.0 1.4102E 2 1.0552E-2 10.5 1.3265E-2 9.7528E-3 11.0 1.2490U-2 9.0786E-3 11.5 1. I770E-2 8.4319E-3 12.0 1.1099E-2 7.8867E-3 l 12.5 1.0472E-2 7.2879E-3 NUREGICR-6143 G 24 Vol. 2 Part 2 i
LOSP Frequency Table G.3.1 Correction / Recovery Factors for DG Fails to Start (LOSP as Initiating Event) (Continued) Time (hr.) Hardware Conunon Mode 13.0 9.8859E-3 6.7809E-3 13.5 9.3367E-3 6.3120E-3 14.0 8.8215E-3 5.8778E-3 14.5 8.3374E-3 5.4754E-3 15.0 7.8823E-3 5.1019E-3 15.5 7.4539E-3 4.7552E-3 16.0 7.0504E-3 4.4330E-3 16.5 6.6701E-7 4.1335E-3 l 17.0 6.3114E-3 3.8550E-3 17.5 5.9730E-3 3.5957E-3 18.0 5.6535E-3 3.3544E-3 18.5 5.3517E-3 3.1297E-3 19.0 5.0667E-3 2.9203E-3 19.5 4.7973E-3 2.7253E-3 20.0 4.5427E-3 2.5435E-3 20.5 4.3020E-3 2.3740E-3 21.0 4.0743E-3 2.2160E-3 21.5 3.8590E-3 2.0687E-3 22.0 3.6552E-3 1.9312E-3 I 22.5 3.4625E-3 1.8031E-3 23.0 3.2801E-3 1.6835E-3 23.5 3.1075E-3 1.5719E-3 24.0 2.9441E-3 1.4678E-3 Vol. 2, Part 2 G-25 NUREG/CR-6143
LOSP Frequency I G.4 Determination of Recovery x , ,3, f,,7,,, ,,,, f,, og ,, ,,,. Values for LOSP/DG-Failure
'-,, - 24 hea.
Restorations: DG Fails To Run G.4.1 Process i For GGNS, P, = .047 and A = 2E-3/hr. ) G.4.1.1 Overview i This section describes the steps carried out in the Step 2. Determine P . The probability that the DG l calculation of the t.on-recovery probabilities for LOSP fails to run during the nussion time before offsite power i accompanied by the failure of diesel generators to run at is recovered is i nome time after LOSP. I The correction factor (or recovery factor) for the P , = [,A cxp(-1 t)P,(t + 7)dt (2) recovery from LOSP given that the DGs fail to run is given by P ,(D where CF,(T) = P, = non-recovery of offsite power in time t + Poon T after LOSP: t = time DG ran before failure: T= time ave.ilable to restore off-site power before core damage occurs. , where ' The integration of Equation (2) was performed using the P ,(T) = probability that the DG fails to run during MathCAD integration function [9]. In order to perform the mission time (t) before offsite power is the integration it was ne;essary to express P (t + T)in recovered, a form compatible with the integration schem,e. This P ,, = probability that DG will fail to run in any form was the polynomial described in the DG Fails to given 24 hour period (the mission time). Start case. (Section G.3.2) The result of the, calculations was a table of probabilit!es The integration provided a table of vale of P,(T) for of non-recovery of off-site power for times up to 24 values of T from 0 to 12 hours. ! hours after the DG failed to run. Step 3. Form the quotient Step 1. Determine Pp. The probability that the DG o ar @ will fail to run m any given 24 hour period is CF"F (T) = Poca given by s Poon = Acxp(- As) d' G.4.2 Results (1) The resulting values are given in Table G.4.1.
, j_exp(_1 ,, _ )
I where NUREG/CR-6143 G-26 Vol.1 Part 2
LOSP Frequency Table G.4.1 Correction / Recovery Factors for DG Fails to Run (LOSP as Initiating Event) Time (hr.) CF,(T) l 1 0 4.8211E-2 l 0.5 3.5676E-2 1.0 3.I17E-2 l
- 1. 5 2.8631E-2 2.0 2.6899E-2 2.5 2.5585E-2 3.0 2.4521E-2 3.5 2.3621E-2 4.0 2.2835E-2 4.5 2.2133E-2 5.0 2.1495E-2 i
5.5 2.0907E-2 l l 6.0 2.0360E-2 ] l 6.5 1.9846E-2 < 7.0 1.9360E-2 7.5 1.8899E-2 i 8.0 1.8458E-2 8.5 1.8036E 2 9.0 1.7630E-2 9.5 1.7239E-2 10.0 1.6862E-2 10.5 1.6497E-2 11.0 1.6143E-2 1 11.5 1.5799E-2 l l 12.0 1.5465E 2 1.5141E-2 ; 12.5 l Vol. 2. Part 2 G-27 NUREG/CR-6143
1 LOSP Frequency Table G.4.1 Correction / Recovery Facton for DG Fails to Run (LOSP as Imriating Event) (Continued Time (hr.) CF,(T) l 13.0 1.4825E-2 13.5 1.4517E-2 14.0 1.4218E-2 i 14.5 1.3925E-2 15.0 1.3640E-2 15.5 1.3362E-2 16.0 1.3090E-2 16.5 1.2925E-2 17.0 1.2566E-2 17.5 1.2312E-2 18.0 1.2065E-2 18.5 1. I823E-2 19.0 1.1586E-2 19.5 1.1355E-2 20.0 1.1128E-2 20.5 1.0907E-2 21.0 1.0690E-2 21.5 1.0479E-2 22.0 10271E-2 22.5 1.0068E-2 23.0 9.8698E-3 - 23.5 9.6755E-3 24.0 9.4953E-3 NUREG/CR-6143 G-28 Vol. 2, Part 2
LOSP Frequency G.5 Determination of Recovery polynomial fit. This double integral resulted in a set of numerat r values fmm T = t T = 24 hours in half- ' Values for LOSP/DG Failure hour increments. Restoration (LOSP Not an IE) : l DG Fails to Run Step 3. The product of the integrals in the denominator i gives a point value. With X, = 1.484E-5, A,, = i 2.0E-3 and T = 24 hours, t[se denominator was found G.5.1 Overview , to be 1.66891I-5. l l his section describes the calculation of the non-recovery i probabilities for'LOSP (LOSP not an IE) accompanied Step 4. CF(T) was determined by dividing each value of by failure of the diesel generators to run sometime after the numerator by the value determined in Step 3. In the LOSP. MathCAD calculation, these values were given the symbol CF (T).
%e correction factor for recovery from LOSP, with the i f:ilure of the DG to run at some time after LOSP, is G.5.3 Results ,
given by: i I The salues for CF(T) determined in Step 4 above are given in Table G.5.1 which follows.
'a CIU) = [, f,' Ag'~'s Ag #'dP yt-sp 7)d4dt i
f,'*k,e *6d$f,Ag ****'dt i where: [ l A,, = frequency of the loss of off-site power X ,, = 'requency of DG failure to run t == mission time (24 hrs.) 1(, = probability of non-recovery of off-site power in tinw t - t + T. t = time at which DG fails to run t, = time at which LOSP occurs
%e double integral in the numerator of CF(T) is the probability that (during the mission time t,) offsite power will be lost, the diesel generator will fail to run and offsite power cannot be recovered in time to prevent core damage at time t - t - T. The denominator is the probability that offs'ite power will be lost and the diesel generator will fail to run during the mission time.
G.5.2 Procedure Step 1. P,, was put into integrable fo'rm. Data for versus time was formed into a polynomial using [P ewton's interpolating algorithm. The form of the j polynomial is given in the earlier discussion of DG fails l to start with LOSP as an initiating event. Step 2. He double integral of the numerator was performed using MathCAD [9] The polynomial fit of P, was placed in the integrand in the form exp"{In[P,,(tt,)} to account for the logarithm fit of the Vol. 2, Part 2 G-29 NUREG/CR-6143
LOSP Frequency Table G.5.1 Correction / Recovery Factors for LOSP (not an IE) with DG Fails to Run Time (hr.) CF(T) 0 . 3.5746E-2 0.5 2.4606E-2 ! 1.0 2.0556E-2 1.5 1.8354E-2 2.0 1.6912E-2 i 2.5 1.5862E-2 3.0 1.5043E-2 3.5 1.4373E-2 , 4.0 1.3805E-2 4.5 1.3311E-2 5.0 1.2872E-2 ! 5.5 1.2476E-2 6.0 1.2113E-2 6.5 1.1778E-2 7.0 1.1465E-2 7.5 1. !!71E-2 l 8.0 1.0893E-2 I i 8.5 1.0630E-2 { 9.0 1.0378E-2 9.5 1.0137E-2 10.0 9.9060E-3 l l 10.5 9.6833E 3 11.0 9.4685E 3 11.5 9.2608E-3 12.0 9.0598 E-3 l 12.5 8.8649E-3 NUR EG/CR-6143 G-30 Vol. 2, Part 2
LOSP Frequency Table G.5.1 Correction / Recovery Factors for LOSP (not an IE) with DG Fails to Run (Continued) Time (hr.) CF(T) 13.0 8.6757E-3 13.5 8.491SE-3 ) I i 14.0 8.3130E-3 14.5 8.1390E-3 , 15.0 7.9694E 3 15.5 7.8042E-3 16.0 7.6431E-3 . l 16.5 7.4859E-3 17.0 7.3325E-3 l 17.5 7.1828E-3 j i 18.0 7.0365E-3 , t 18.5 6.8937E-3 I 19.0 6.7541E-3 I 19.5 6.6177E-3 20.0 6.4843E-3 20.5 6.3539E-3 , l 21.0 6.2264E-3 l 21.5 6.1017E 3 22.0 5.9798E-3 22.5 5.8605E-3 1 23.0 5.7438E-3 l 23.5 5.6296E-3 24.0 5.5179E-3 l Vol. 2, Part 2 G-31 NUREG/CR-6143 i 4- . . _ - _ - - .
LOSP Frequency G.6 Determination of Recovery G.7.1 LOSP as Initiating Event (CF,) Values for LOSP/DG Failure ne expression for this correction factor is
. i i
Restoration (LOSP not an IE): ( DG Falls to Start CF,(T) = Pw T ne diesel generator would be called for at the time off-site power is lost. His is the case whether the LOSP is random after ar, initiating event or it is itself an initiating where P~ = probability of not recovering off-site event, nus, the time available for recovery is the same power in i[me T. as for DG fails to start for LOSP as an initiating event and the results are the same. He probabilities of non. ne calculation of this CF distribution used only the left recovery from DG failure to start for either as a hardware branch of Figure 0.7-1. A data base of plant data for or common mode failure are given in Table G.3.1. P
" lye,(T)
MODEL versus T was code applies the used mixtureasmodelinput of to MODEL.FOR. Reference 3 to the plant input data. The result is a set of 500 P T) vs. T curves which reflect the uncertainty in G.7 Recovery / Correction Factors for the prNa(bility of recovery of off-site power. Each curve Uncertt.inty Analys.is is identified by a number (called a pointer). For the Grand Gulf analysis, T varied from .05 to 100 hours and This section describes the calculation of the offsite power each curve was constructed of 85 points. The time range recovery correction factors. The equations which form and number of points are user specified inputs to the basis for the calculation are given in Reference 10. MODEL. He curves are written 'o a curve file. For uncertainty analysis, the calculations must consider The 500 point distribution for P~ (T) at each of the the uncertainty in the inputs to these equations. To do seven time steps consists of the sef of values from each of thir distributions characterizing the uncertainty in the the 500 curves for the specified T. eq .*r.,ns were developed. Once the distributions for the input parameters were obtained, these distributions were G.7.2 LOSP as Initiating Event: DG Falls incorporated into the appropriate correction factor (CF) toRun expressions. The octput from this operation was a distribution of correction factors which reflected the The correction factor for this case is given by uncertainties m the inputs. e * * ** ' P#(T + ) de Distributions of correction factors for recovery from four cp (T) = [% 2 LOSP events were calculated: 1_, ~ Awa '-
- LOSP as an initiating event (CF )
- LOSP as an initiating event, diesel generator *
(DG) fails to run (CF,)
- LOSP as an initiating event, DG fails to start (Hardware failure)(CF )
- LOSP as an initiating ehent, DG fails to start
( t
=
=
DG run failure frequency of the DG mission tim: (24 hours) (Common Mode failure)(CF,) I.0, = value from non-recovery curve for off-site power T = time after which core damage occurs he process for the CF distribution calculations is given t = time at which DG fails to run in Figure G.7-1, The ouput of the process was a distribution of 500 values for CF hours)."(T) at 7 values Each distnbution reflectsof theTuncertainty (2, 3, 3.5, in 5, 6,11 and 14 CF,(T) at its particular value of T. NUREG/CR-6143 G-32 Vol. 2, Part 2
1,OSP Frequency Plant data Input Distribution t __ LHS MODEL.FOR 1r y . nce n ist Curve File Pointer, A RLOSP.FOR 1 V 1r i t ) CF Distributions i Figure G.7-1 CF Distribution Calculation '.8 Vol. 2, Part 2 G-33 NUREG/CR4143
__. . . _ - _ - . _ _ _ _ ~ . - LOSP Frequency ne determination of CF, required both branches of For each specified T, the mean value was selected from ! Figure G.7-1. He curves for P , were taken from the the mean non-recovery curve of Reference 10. The case. Using an input distribYtion of DG failure to upper value was set to 1.0 and the lower value was set an CF, run frequencies based on plant data, the LHS codeorder of magnitude below the mean. developed a 500 point distribution for A ,. This distribution is lognormal with a mean od.0E-3 and an IInving the 500 P , curves and pointers and the 500 error factor of 10. The LIIS step also writes a uniform point maximum e,tropy n distribution for P for a given distribution of the 500 points for the P,, curves. The time T, the RLOSP code samples both an8Eorms their input for LilS used to determine these and subsequent product as CF (T). He sampling and multiplication are distributions is given as Attachment G-44 to this performed 50d times to form a 500 point distribution for Appendix. CF 3(T) at each desired T. ne denominator of the CF,(T) expression is a point G.7.4 LOSP as Initiating Event: DG Falls value evaluated at the mean value for A,. This term to Start, Common Mode cancels out the existing event in the cut set which was quantified using the same A, value. The numerator of The correction factor for this event is given by CF,is calculated by the RLOSP code which samples A, and P** and performs the integral. First, RLOSP CF* = p,,.or(7) paroocu(7)
- seicues (at random) a value for A, from the 500 calculated by LIIS and a pointer corresponding to one of where P (T) is the probability of non-recovery at the 500 P,, curves. RLOSP then integrates the time T oYa3G that failed to start due to a common numerator over the mission time using a Runge-Kutta mode failure. P has the usual definition. A maximum solution technique. He sampling and integration are entropy distributY[n for P at each desired T was repeated a total of 500 times until the 500 values of P.,or determined in the same n$nir' as for P . The end 500 A, curves have been used, yielding 500 distribution inputs are given in Table GYl2 . Sampling numerators. Each numerator is divided by the point and the calculation of CFJT) was performed in the same value denominator yielding a distribution of 500 values of manner as for CF3 (T).
CF,(T). A listing of the RLOSP code is given in Attachment G-45 to this Appendix. l G.7.3 LOSP as Initiating Event: DG Fails to Start The correction factor for this event is given by CF,(7) = P ,(7)p-oo II) I where P,,, is the non-recovery probability for the diesel I generator at time T. Both offsite power and the DG are ' tcken to fail at time 0. Both P Values for P are obtained nfrYr'the and 5 curves P@. are sampled. l i calculated foNF,(T). A maximum entropy distribution was used to characterize P T 500 point distribution was calculate [fy. Each PLliS. 'I$(req)uired an input of the lower value, mean, and uppen value for the l desired distribution. These inputs for each of the seven I recovery times are given in Table G.7.1. j NUREG/CR-6143 G-34 Vol. 2, Part 2 1
LOSP Frequescy i Table G.7.1 DG Fail to Start non-Recovery Distributions i Distribution Time Available for Recovery , Parameters ! 2.0 3.0 3.5 5.0 6.0 11.0 14.0 { Distribution Type Max. Max. Max. Max. Max. Max. Max. Entropy Entropy Entropy Entropy Entropy Entropy Entropy Upper Value 1.0 1.0 1.0 1.0 1.0 1.0 1.0 l Mean 0.87 0.8 0.775 0.7 0.65 0.48 0.41 r I Lower Value 0.087 0.08 0.0775 0.07 0.065 0.048 0.041 f f Table G.7.2 DG Fail to Start Common Mode non-Recovery Distributions , Distribution Time Available for Recovery Parataeters 0.8 3.0 3.5 5.0 6.0 11.0 14.0 f Distribution Type Mss. Max. Max. Max. M ax. Max. Max. [ Entropy Entropy Entropy Entropy Entropy Entropy Entropy Upper Value 1.0 1.0 1.0 1.0 1.0 1.0 1.0 Mean 0.77 0.7 0.675 0.6 0.55 0.29 0.24 lower Value 0.077 0.07 0.0675 0.06 0.055 0.029 0.024 Vol. 2, Part 2 G-35 NUREG/CR 6143
LOSP Frequency , i G.8 IRRAS Histogram Development Step s. Several equations were copied into columns to track and fine-tune the calculation. "
%e uncertainty analysis was performed using the IRRAS code. De histograms are limited to 20 points. Bus, s. Column G, the bin midpoint column, had 0.0 ;
the 500 point CF distributions whose development was assigned to row 2. In row 3, the expression j described in SectIon G.7 had to be reduced to 20 bin + (D2 D3) /2 histograms for entrf into IRRAS. His binning was performed with the QUATRO PRO spread sheet software was inserted and copied into rows 4 through 22. AA I [11]. It was done using the following steps for each CF,. the expression is copied down the column, the indices on D are changed to reflect the new row ; Step 1. De seven columns corresponding to each Position so that the appropriate bin midpoint is
- recovery time (T) were read into a QUATTRO PRO calculated.
spread sheet and parsed into seven spread sheet columns. i Time headings for each T were assigned to row I of each b. Row 3 of column H was assigned the expression ; column. This first page in the spread sheet served as the E3 /500 100 l repository for the CF s as calculated by RLOSP in section G.7. The binfring for each time T was done on a separate page in the spread sheet. to calculate the bin probability density in percent. This expression was copied down to row 22. Row Step 2. On a separate spread sheet page, headings Step, 24 was assigned the sum of rows 3 through 22. CF Bin Bound, Frequency, Bin Mdpt, Prob. Density After each calculation, row 24 was checked for the and, Running Total were assigned to row 1 of columns A. value 100 to be sure all points were counted. B, D, E, G, H, and I respectively,
- c. A running total of the cummulative probability Step 3. Rows 2 through 502 of column A were filled density was kept in column 1. The expression with quantile values from 0.0 to 1.0 in .002 increments.
12 + //3 /100 Step 4. %e column of CFs to be binned for the time T ofinterest was copied from the first spread sheet page was assigned to row 3 of column I and copied into 4 into rows 3 through 502 of column B. The value 0.0E0 r ws 4 through 22. was assigned to row 2 of column B. Exponential format was used. Step 9. Using the frequency function from the Data menu in QUATTRO PRO, the CFs in column B were Step 5. Using the spread sheet sorting utility, the CFs in s rted according to the bin bounds of column D. The column B were s'orted in ascending order. The sorted frequency f CFs in each bin was entered into column E values remained in column B. by the software. The software also filled in columns G, 11, and I using the mathematical expressions defined in Step 6. %e values in column B and quantiles in column Step 8. A were plotted in a Cummutative Distribution Function (CDF). See Figure Attachment G-47-1 for an example. Step 10. Results of the calculation were compared to the CDF for the 500 points in Column B in the following Step 7. Bin bounds were estimated and filled into rows 2 manner. through 22 of column D. The bounds were estimated so as to: a. The frequency (COLUMN E) of the highest value bin was checked to ensure the high
- a. Preserve the high frequencies in the tail of the frequencies in the tail of the CDF were CDF at a high bin midpoint value. represented at a sufficiently high bin midpoint value.
- b. Match the frequency population of each bin as closely as possible to the CDF. b. Using the spread sheet plotting package, the running total (column I) was plotted twice against the bin midpoint column on the same NUREG/CR-6143 G-36 Vol. 2. Part 2
LOSP Frequency graph. One plot was of spread sheet elements 12 Statistically speaking, the step representation of the CDF to 120 vs. G3 to G21. The second was of13 to in Step 11 results from the histogram representation of I21 vs. G3 to G21. His results in a
- stair-step' the CF frequency distribution. He histogram (which is representation of the Cummutative Distribution our approximation of the CF probability density function)
Function plotted in Step 6. Figure Attachment is a series of delta functions at discrete points (the bin G-47 2 is an example of this type of plot. This midpoints). is discussed in greater detail in Step 12 and Step
- 13. One obtains the CDF for a continuous distribution by integrating over the population density. The result is the Step 11. He plot of 10b was overlaid on the CDF plot smooth CDF of Step 6. When integrating over a density of Step 6. He degree to which the CDF plot passed function represented by delta functions, the probability through the middle of the vertical part of each step of the density (integrated) is equal to zero where the delta Step 10 graph was assessed by engineering judgement. functions do not exist. The resulting CDF is then a ne closer the CDP is to the middle of the vertical step, series of steps (one step for each data function) located at the better the 20 bin approximation is to the CDF. the bin midpoints.
Step 12. Depending on the CDF-step fit of Step i1. the in order to assess the adequacy of the 20 bin histogram, bin bounds were adjusted and the process was repeated the bottom as well as the top of each step must be beginning at Step 9 until a satisfactory fit was obtained. defined. Dat is the purpose of the tw.s plots of Step An example of the spread sheet and graphs are given in 10b. One plot represents the top of each step, while the Attachments G-46 and G-47. other represents the bottom. Since the top of one step is the bottom of the next, the step bottoms in the histogram Step 13. He results were entered into the appropriate CDF are given by the 12 to 120 curve. The step tops are IRRAS data base as a percentage histogram: Bin given by the 13 to 121 curve. Midpoint (COLUMN G) and Probability Density in percent (COLUMN H). l l 1 Vol. 2, Part 2 G-37 NUREG/CR-6143
. _ _ _ _ _ _ _ _ _ _ _ _ _ _ . l
LOSP Frequency References for Appendix G [1] USNRC, " Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants," NUREG-1150, June,1989. [2] II. Wyckoff, ' Losses of Offsite Power at U.S. Nuclear Power Plants: All Years through 1988,' NSAC 144, April 1989. [3] R. Iman, "Modelling Time to Recover and Initiating Event Frequency for losses of Offsite Power Incidents at Nuclear Power Plants," NUREG/CR-5032, January 1988. [4] P.W.Baranowsky, " Evaluation of Station Blackout Accidents at Nuclear Power Plants: Technical Findings Related to Unresolved Safety Issue A-44," NUREG/CR-1032, May 1985. [5] IMSL, Inc. 'IMSL MATil/ LIBRARY Users Manual," Version 2.0, IMSL, Houston, TX 1991. [7] J.Darby, "SEACALC: Code Verification for the SEA Set of Numerical Analysis Algorithms for the IBM.PC," SEA C 90-662-04-A:1, February 1, 1990. [8] D.M.Erickson et al., " Analysis of Core Damage Frequency: Intemal Events Methodology," NUREG CR/4550, SAND-86-2084, Vol.1. Rev.1 January 1990. [9] MathSoft, Inc. MathCAD Version 2.5 Users Guide,1989 [11] Borland International, Inc., "QUATTRO PRO for Windows Users Guide,* 1992. i NUREG/CR-6143 G-38 Vol. 2, Part 2 l
i l LOSP Frequency 1 l P l Attachment G-1 i IE.BCK Vol. 2. Part 2 G-39 NUREG/CR-6143
LOSP Frequency 1 ARKANSAS NUCLEAR ONE ANO 1 9.81 0 14.09 0 6.18 2 BEAVER VALLEY BV 1 5.80 0 12.25 0 4.83 3 BIG ROCK POINT BRP O 14.64 0 25.85 0 7 60 4 BROWNS FERRY BF 0 10.52 0 14.42 0 12.69 5 BRUNSWICH BRU 1 8.5 0 13.17 1 7.97 6 BYRON BYR 0 1.31 0 3.33 0 0.98 l 7 CALLAWAY CAL 0 2.37 0 4.08 0 0.65 , 8 CALVERT CLIFFS CC 1 11.50 0 13.68 0 4.87 ) 9 CATAWABA CAT 0 2.17 0 3.58 0 1.77 1 10 CLINTON CLN 0 0.08 0 1.10 0 0.18 11 COOK COK 0 10.23 0 13.42 0 6.23 12 COOPER COP 0 7.92 0 14.51 0 3.77 13 CRYSTAL RIVER CR 0 6.21 0 11.48 0 4.38 14 DAVIS-BESSE DB 2 3.85 0 10.51 0 5.04 15 DIABLO CANYON DC 0 2.27 0 3.67 0 1.31 1 16 DRESDEN DR 1 13.89 1 18.59 0 9.10 17 DUANE ARNOLD DA 0 6.83 0 13.92 0 4.30 18 FARLEY FAR 2 8.60 0 11.09 0 3.76 19 FITZPATRICK FIT 0 8.01 0 13.51 3 3.92 20 FORT CLAHOUN FC 2 9.01 0 14.59 1 3.40 i 21 FORT ST. VRAIN FSV 0 1.11 1 9.51 0 6.66 ! 22 GINNA GIN 2 12.61 0 18.51 0 4.31 ! 23 GRAND GULF GG 0 1.45 0 3.50 0 1.16 l 24 HADDAM NECK llN 6 16.49 0 21.43 1 4.24 . 25 IIATCH liAT 0 9.10 0 13.09 0 6.21 l 26 HOPE CREEK HC 0 0.81 0 2.03 0 0.37 - 27 INDIAN POINT IP 2 10.40 3 14.42 1 8.16 28 KEWAUNEE KEW 0 10.89 0 14.59 0 2.32 29 LASALLE LAS 0 2.27 0 5.00 0 3.12 30 LIMERICK LIM 0 1.43 0 2.01 0 0.52 31 M AIN YANKEE MY 0 10.56 0 16.09 0 3.65 32 MCGUIRE MCG 1 4.47 0 7.08 1 3.14 33 MILLSTONE MIL 1 14.17 2 17.85 0 7.35 34 MONTICELLO MON 1 11.70 0 17.59 1 4.05 35 NINE MILE POINT NMP 1 11.I1 0 19.09 0 6.30 36 NORTH ANNA NA 0 7.91 0 10.59 0 4.40 37 OCONEE OCO 1 13.56 0 15.51 0 9.00 38 OYSTER CREEK OYC 1 9.75 0 19.09 1 7.07 39 PALISADES PAL 3 7.69 0 17.09 1 8.55 40 PALO VERDE PV 2 1.54 0 2.91 0 1.53 41 PEACil BOTTOM PB 0 11.00 0 14.51 0 9.45 42 PERRY PER 0 0.08 0 1.12 0 0.27 43 PILGRIM PIL 0 7.71 4 16.09 0 7.24 44 POINT BEACil PB 2 15.73 0 18.09 1 5.23 45 PRAIRIE ISLAND P1 1 13.38 0 15.09 0 4.11 46 QUAD CITIES QC 2 12.95 0 15.92 1 6.63 47 RANCHO SECO RS 0 5.230 1 3.76 0 7.29 48 RIVER BEND RB 1 1.04 0 2.58 0 0.80 49 ROBINSON ROB 1 10.78 0 17,85 0 5.37 1 50 SALEM SAL 0 7.15 0 11.59 1 6.25 51 SAN ONOFRE SO 2 12.13 0 21.01 2 10.74 ! j 52 SEQUOYAH SEQ 0 4.30 0 7.50 0 5.26 l 53 ST LUCIE STL 0 9.03 2 12.09 0 3.78 NUREG/CR-6143 G-40 Vol. 2, Part 2
LOSP Frequency 54 SHEARON liARRISON SH 0 0.49 0 1.69 0 0.44 55 SUMMER SUM 0 2.69 0 5.00 0 1.35 56 SURRY SUR 0 12.28 0 16.09 0 9.41 i 57 SUSQUEl{ ANNA SUS 1 3.81 0 5.59 0 2.03 58 TliREE MILE ISLAND TMI O 4.70 1 4.34 0 8.32 59 TROJAN TRO O 6.63 0 12.67 0 4.44 60 TURKEY POINT TP 2 13.05 7 16.09 1 9.01 61 VERMONT YANKEE VY 0 10.68 0 16.17 0 3.56 62 VOGTLE VOG 0 0.15 0 1.58 0 0.40 63 WASlilNGTON NUCLEAR WN O 1.57 0 4.08 0 1.14 64 WATERFORD WAT 0 1.75 0 2.33 0 0.73 ! 65 WOLF CREEK WC 0 1 84 0 3.33 0 0.90 66 YANKEE ROWE YR 0 20.11 1 28.18 1 5.92 67 ZION ZIO O 11.59 0 15.09 0 7.58 Vol. 2, Part 2 G-41 NUREG/CR-6143
LOSP Frequency 1 l l Attachment G-2
)
IE.BCK I I i l \ J NUREG/CR-6143 c.42 Vol. 2, Part 2
LOSP Frequency 1 1 14.09 0 6.I8 12.25 0 4.83 ! 2 1 3 1 25.85 0 7.60 4 0 14.42 0 12.69 ) 5 1 13.17 1 7.97
, I I
6 0 3.33 0 0.98 7 0 4.08 0 0.65 8 1 13.68 0 4.87 9 0 3.58 0 1.77 10 0 1.10 0 0.18 11 0 13.42 0 6.23 12 0 14.51 0 3.77 13 0 11.84 0 4.38 14 0 10.51 0 5.04 15 1 3.67 0 1.31 16 2 18.59 0 9.10 17 0 13.92 0 4.30 ) 18 0 11.09 0 3.76 19 0 13.51 3 3.92 20 2 14.59 1 3.40 21 1 9.51 0 6.66 22 2 18.51 0 4.31 23 0 3.50 0 1.16 24 6 21.43 1 4.24 25 0 13.09 0 6.21 26 0 2.03 0 0.37 27 5 14.42 1 8.16 28 0 14.59 0 2.32 29 0 5.00 0 3.12 30 0 2.92 0 0.52 31 0 16.09 0 3.65 1 32 1 7.08 1 3.14 33 3 17.85 0 7.35 34 1 17.59 1 4.05 l Vol. 2 Part 2 G-43 NUREG/CR-6143 l
LOSP Frequency 35 2 19.09 0 6.30 36 0 10.59 0 4.40 37 1 15.51 0 9.00 38 1 19.09 1 7.07 39 3 17.09 1 8.55 40 2 2.91 0 1.53 41 0 14.51 0 9.45 42 0 1.12 0 0.27 43 4 16.09 0 7.24 44 2 18.09 2 5.23 45 1 15.09 0 4.I1 46 2 15.92 1 6.63 47 0 13.76 0 7.29 48 1 2.58 0 0.80 49 1 17.85 0 5.37 50 0 11.59 1 6.25 51 2 21.01 2 10.74 52 0 7.50 0 5.26 l 53 2 12.09 0 3.78 54 0 1 69 0 0.44 55 0 5.00 0 1.35 56 0 16.09 0 9.41 57 1 5.59 0 2.03 58 0 14.34 0 8.32 I 59 0 12.67 0 4.44 60 9 16.'09 1 9.01 61 0 16.17 0 3.56 62 0 1.58 0 0.40 63 0 4.08 0 1.14 64 0 3.33 0 0.73 65 0 3.33 0 0.90 , l 66 1 28.I8 1 5.92 67 0 15.09 0 7.58 l NUREG/CR-6143 G-44 Vol. 2, Part 2
LOSP Frequency Attachment G-3 i LOSP_lE_PCGW.DAT Vol. 2. Part 2 G-45 NUREG/CR-6143
LOSP Frequency 1 1 14.09 2 1 12.25 3 1 25.85 4 0 14.42 5 1 13.17 6 0 3.33 7 0 4.08 8 1 13.68 9 0 3.58 10 0 1.10 11 0 13.42 12 0 14.51 13 0 11.84 14 0 13.51 15 1 3.67 16 2 18.59 17 0 13.92 18 0 11.09 19 0 13.51 20 2 14.59 21 1 9.51 22 2 18.51 23 0 3.50 24 6 21.43 25 0 13.09 26 0 2.03 27 5 14.42 28 0 14.59 29 0 5.00 30 0 2.92 31 0 16.09 32 1 7.08 33 3 17.85 34 1 17.59 NUREG/CR-61d3 G-46 Vol. 2, Part 2
LOSP Frequency 35 2 19.09 36 0 10.59 37 1 15.51 38 1 19.09 3 39 3 17.09 40 2 2.91 41 0 14.51 42 0 1.12 43 4 16.09 44 2 18.09 45 1 15.09 46 2 15.92 47 0 13.76 48 1 2.58 49 1 17.85 50 0 11.59 51 2 21.01 52 0 7.50 53 2 12.09 54 0 1,69 55 0 5.00 56 0 16.09 57 1 5.59 58 0 14.34 59 0 12.67 l 60 9 16.09 61 0 16.17 f 62 0 1,58 63 0 4.08 64 0 3.33 65 0 3.33 ) 66 1 28.18 67 0 15.09 Vol. 2, Part 2 G-47 NUREG/CR-6143 l l I i I I
LOSP Frequency Attachment G-4 LOSP_IE_IV.DAT l i l l l 1 l I i i l l NUREG/CR-6143 G-48 Vol. 2, Part 2 l
1 LOSP Frequency 1 0 6.18 2 0 4.83 3 0 7.60 1 4 0 12.69 i 5 1 7.97 ; 6 0 0.98 7 0 0.65 i 8 0 4.87 9 0 1.77 10 0 0.18 11 0 6.23 12 0 3.77 13 0 4.38 14 0 5.04 15 0 1.31 16 0 9.10 17 0 4.30 18 0 3.76 l 19 3 3.92 l 20 1 3.40 21 0 6.66 22 0 4.31 ; I 23 0 1.16 , 24 1 4.24 . i 25 0 6.21 1 26 0 0.37 1 27 1 8.16 i 28 0 2.32 ! 29 0 3.12 i 30 0 0.52 l 31 0 3.65 ; 32 1 3.14 l l 33 0 7.35 34 1 4.05 1 Vol. 2, Part 2 G-49 NUREGICR-6143 j l i
LOSP Frequency 35 0 6.30 36 0 4.40 37 0 9.00 38 1 7.07 39 1 8.55 40 0 1.53 41 0 9.45 42 0 0.27 43 0 7.24 44 1 5.23 45 0 4.11 46 1 6.63 47 0 7.29 48 0 0.80
}
49 0 5.37 I 50 1 6.25 l 51 2 10.74 52 0 5.26 53 0 3.78 54 0 0.44 55 0 1.35 56 0 9.41 57 0 2.03 58 0 8.32 59 0 4.44 60 1 9.01
)
61 0 3.56 ; l 62 0 0.40 ! ! 63 0 1.14 64 0 0.73 65 0 0.90 l 66 1 5.92 67 0 7.58 1 l l NUREGICR-6143 G 50 Vol. 2, Part 2
LOSP Frequency 1 Attachment G-5 IE.DAT Vol. 2, Part 2 G.51 NUREG/CR4143
i LOSP Frequency 1 i 14.09 2 1 12.25 3 1 25.85 4 0 14.42 5 1 13.17 6 0 3.33 7 0 4.08 8 1 13.68 9 0 3.58 10 0 1.10 11 0 13.42 12 0 14.51 13 0 11.84 14' 0 10.51 15 1 3.67 16 2 18.59 17 0 13.92 18 0 11.09 19 0 13.51 l 20 2 14.59 21 1 9.51 22 2 18.51 23 0 3.50 24 6 21.43 25 0 13.09 26 0 2.03 27 5 14.42 28 0 14.59 29 0 5.00 30 0 2.92 31 0 16.09 32 1 7.08 33 3 17.85 34 1 17.59 NUREO/CR-6143 G-52 Vol. 2, Part 2
LOSP Frequency 35 2 19.09 36 0 10.59 37 1 15.51 38 1 19.09 39 3 17.09 40 2 2.91 41 0 14.51 42 0 1.12 43 4 16.09 44 2 18.09 45 1 15.09 46 2 15.92 47 0 13.76 48 1 2.58 l 49 1 17.85 l 50 0 11.59 i 51 2 21.01 52 0 7.50 53 2 12.09 54 0 1.69 Sf 0 5.00 56 0 16.09 57 1 5.59 58 0 14.34 59 0 12.67 60 9 16.09 61 0 16.17 l 62 0 1.58 63 0 4.08 64 0 3.33 65 0 3.33 66 1 28.18 67 0 15.09 Vol. 2, Part 2 G.53 NUREG/CR-6143
LOSP Frequency $ RUN IEFREQI INPUT TiiE NAME OF THE DATA FILE (ENCLOSED IN TICK MARKS) 'IE.DAT' 12345678910111213 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 66 67 INPUT TiiE ID FOR THE PLANT OF INTEREST 23 PLANT ID = 23, NUMBER OF FAILURES - 0., NUMBER OF YEARS = 3.5 SUM OPER. YRS = 789.520000000000 IF YOU KNOW THE VALUE OF CONSTANT, TYPE 1;O.W. TYPE 2 2 INPUT Tile PAILURE FREQUENCY FOR PLANT LOSP FOR 23 15 PLEASE WAIT WHILE TiiE INTEGRATION IS PERFORMED CONSTK = 1.580239660651922E-095 Tile CUMULATIVE PROBABILITY FOR PLANT LOSP FOR A FAILURE FREQUENCY OF 0.415000 AT 23 IS 0.998994 IS TlilS VALUE SATISFACTORY? Y OR N N ! INPUT THE FAILURE FREQUENCY FOR PLANT LOSP l FOR 23 .45 PLEASE WAIT WillLE THE INTEGRATION IS PERFORMED CONSTK = 1.580239660651922E-095 E CUMULATIVE PROBABILITY FOR PLANT LOSP FOR A FAILURE FREQUENCY OF 0.450000 AT 23 IS 0.999392 IS Tills VALUE SATISFACTORY? Y OR N N INPUT TIIE FAILURE FREQUENCY FOR PLANT LOSP FOR 23 .44 PLEASE WAIT WHILE THE INTEGRATION IS PERFORMED CONSTK= 1.580239660651922E-095 THE CUMULATIVE PROBABILITY FOR PLANT LOSP FOR A FAILURE FREQUENCY OF 0.440000 23 IS 0.999304 IS THIS VALUE SATISFACTORY? Y OR N NUREG/CR-6143 G-54 Vol. 2, Part 2
LOSP Frequency N F INPUT THE FAILURE FREQUENCY FOR PLANT LOSP FOR 23
.43 PLEASL' W AIT WillLE THE INTEGRATION IS PERFORMED CONSTK- 1.580239660651922E-095 THE CUMULATIVE PROBABILITY FOR PLANT LOSP FOR A FAILURE FREQUENCY OF 0.430000 AT 23 0.999191 THIS VALUE SATISFACTORY? Y OR N N
INPUT TIIE PAILURE FREQUENCY FOR Plj.NT LOSP FOR 23
.42 PLEASE WAIT WHILE TiiE INTEGRATION IS PERFORMED CONSTK- 1.580239660651922E-095 TiiE CUMULATIVE PROBABILITY FOR PLANT LOSP FOR FAILURE FREQUENCY OF 0.420000 AT 23 IS0.999062 IS Tills VALUE SATISFACTORY 7 Y OR N N
INPUT TIIE FAILURE FREQUENCY FOR PLANT LOSP FOR 23
.418 PLEASE WAIT WlilLE Ti1E INTEGRATION IS PERFORMED CONSTK- 1.58,0239660651922E-095 THE CUMULATIVE PROBABILITY FOR PLANT LOSP FOR A FAILURE FREQUENCY OF 0.418000 AT 23 IS0.999030 IS THIS VALUE SATISFACTORY? Y OR N N
INPUT TiiE FAILURE FREQUENCY FOR PLANT LOSP FOR 23
.417 PLEASE WAIT WillLE THE INTEGRATION IS PERFORMED CONSTK= 1.580239660651922E-095 TIIE CUMULATIVE PROBABILITY FOR PLANT LOSP FOR /, FAILURE FREQUENCY OF 0.417000 AT 23 IS 0.999019 IS TIIIS VALUE SATISFACTORY 7 Y OR N G-55 NUREG/CR-6143 j Vol. 2. Part 2
LOSP Frequency INPUT THE FAILURE FREQUENCY FOR PLANT LOSP FOR 23 .416 PLEASE WAIT WHILE THE INTEGRATION IS PERFORMED CONSTK= 1.580239660651922E-095 THE CUMULATIVE PROBABILITY FOR PLANT LOSP FOR A FAILURE FREQUENCY OF 0.416000 AT 23 IS 0.999006 IS THIS VALUE SATISFACTORY? Y OR N Y FORTRAN STOP l l i l l NUREG/CR4143 G-56 Vol. 2, Part 2
LOSP Frequency I i l l i I f Attachment G4 LOSP_IE_PCGW.INP l I l Vol. 2. Part 2 G 57 NUREG/CR4143
I LOSP Frequency ;
'LOSP IE PCGW.DAT'23.416 30 1 i
l I i i F 1 l t l ! NUREG/CR-6143 c.58 Vol. 2. Part 2
I l i LOSP Frequency i i Attachment G-7 l IEBAT.COM l 1 i l l l l 1 1 Vol. 2 Part 2 G-59 NUREG/CR-6143 1
LOSP Frequency
$ SET VERJFY $ SET DEFAULT UD4:[BDSTAPL] $ RENAME LOSP_IE_PCGW.INP IEFREQ.INP $ RUN IEBATI $ RENAME IEFREQ.INP LOSP_IE PCGW.INP $ RENAME PLOT.DAT IE PCGW.DAT l
l i
)
i i NUREG/CR4143 G40 Vol. 2. Part 2
LOSP Frequency 1 I l l I i l i Attachment G-7a , IEBAT.COM (Slow Batch Mode) 4 ( 1 Vol. 2, Part 2 G41 NUREGICR4143 I i l I
i ISSP Frequency
$ SUBMIT /Q= SLOW $ BATCH / LOG _ FILE =IEBAT/NOPRINT/ CPU =1:30:001EBAT.COM
$ EXIT-~
l l l l l l NUREG/CR-6143 G-62 Vol. 2. Part 2
LOSP Frequency i l i i i l Attachment G-7b IEBAT.COM LOG FILE l l l l l l i Vol. 2, Part 2 G-63 NUREG/CR-6143
. - - = .
i l l l LOSP Frequency
$5et NoControl-Y
' $5et NoVerify
$ SET DEFAULT UD4:[BDSTAPL] $ RENAME LOSP_IE PCGW.INP IEFREQ,1NP $ RUN IEBATI i FORTRAN STOP $
t
$ RENAME IEFREQ.INP LOSP_IE_PCGW.INP $ RENAME PLOT.DAT IE_PCGW.DAT )
BDSTAPL job terminated at 34UN-1991 18:43:33.13 l Accounting information: Buffered 1/0 count: 129 Peak working set size: 1239 Direct I/O count: 100 Peak page file size: 4311 Page faults: 4276 Mounted volumes: 0 ) Charged CPU tirne: 0 00:05:32.22 Elapsed time: 0 01:15:18 51 ] 1 1 l I i l i I I t 4 i NUREG/CR4143 G44 Vol. 2, Part 2 i e
- _ - + , - .
.- -w -
LOSP Frequency i Attachment G-8 IE_PCGW.DAT (BEFORE UPDATE) l I
)
l I i l 1 l 1 i j l Vol. 2. Part 2 G-65 NUREG/CR-6143
1 i LOSP Frequency O.154074E 04 0.000978 0.123259E 03 0.003558 0.416000E-03 0.008215 0.986074E-03 0.015590 0.192593E-02 0.026452 , j 0.332800E 02 0.041697 0.528474E-02 0.062328 0.788859E 02 0.089409 ' O.112320E-01 0.124002 0.154074E-01 0.167035 0.205073E-01 0.219149 0.266240E-01 0.280514 0.338501E-01 0.350585 0.422779E-01 0.427906 ; 0.520000E-01 0.510082 0.631087E 01 0.593832 0.756%6E-01 0.675337 0.898560E-01 0.750074 9 0,105679E + 00 0.814062 O.123259E + 00 0.865966 0.142688E + 00 0.906261 0.164058E+00 0.936288 0.187462E + 00 0.957847 0.212992E + 00 0.972826 0.240741E + 00 0.982946 0.270801E + 00 0.989592 0.303264E + 00 0.993861 0.338223E + 00 0.996512 0.375771E+00 0.998145 0.416000E + 00 0.999006 NUREG/CR-6143 G-66 Vol. 2, Part 2 4
LOSP Frequency r i Attachment G-9 IE_PCGW.DAT (After Update) Vol. 2, Part 2 G-67 NUREG/CR-6143
LOSP Frequency 0.100000E-07 0.000000 0.154074E-04 0.000978 0.123259E-03 0.003558 0.416000E-03 0.008215 0.986074E-03 0.015590 0.192593E-02 0.026452 0.332800E-02 0.041697 0.528474E-02 0.062328 0.788859E-02 0.089409 0.I12320E-01 0.124002 0.154074E-01 0.167035 0.205073E-01 0.219149 0.266240E-01 0.280514 0.338501E 01 0.350585 0.422779E-01 0.427906 0.520000E-01 0.510082 0.631087E-01 0.593832 0.756966E-01 0.675337 0.898560E 01 0.750074 0.105679E + 00 0.814062 0.123259E + 00 0.865966 0.142688E +00 0.906261 0.164058E + 00 0.936288 0.187462E + 00 0.957847 0.212992E + 00 0.972826 0.240741E + 00 0.982946 0.270801E + 00 0.989$92 0.303264E +00 0.993861 0.338223E + 00 0.996512 0.375771E+00 0.998145 0.416000E + 00 0.999006 0.900000E + 00 1.000000 l ) NUREG/CR-6143 G-68 Vol. 2, Part 2 I l 1
i I LOSP Frequency l T L Attachment G-10 , IE.DAT for CATEGORY IV i I Vol. 2 Part 2 G49 NUREG/CR4143
LOSP Frequency ! 1 0 6.18 2 0 4.83 l 3 0 7.60
)
4 0 12.69 5 1 7.97 6 0 0.98 I 7 0 0.65 8 0 4.87 9 0 1.77 i l 10 0 0.18 l 11 0 6.23 I 12 0 3.77 , 1 13 0 4.38 i 14 0 5.04 15 0 1.31 16 0 9.10 17 0 4.30 i 18 0 3.76 19 3 3.92 20 1 3.40 - 21 0 6.66 22 0 4.31 23 0 1.16 24 1 4.24 25 0 6.21 26 0 0.37 27 1 8.16 28 0 2.32 29 0 3.12 30 0 0.52 31 0 3.65 i 32 1 3.14 33 0 7.35 34 1 4.05 NUREG/CR-6143 G-70 Vol. 2. Part 2 i
l 1 LOSP Frequency ! 35 0 6.30 36 0 4.40 37 0 9.00 38 1 7.07 39 1 8.55 40 0 1.53 41 0 9.45 42 0 0.27 43 0 7.24 44 1 5.23 45 0 4.11 46 1 6.63 47 0 7.29 48 0 0.80 49 0 5.37 50 1 6.25 51 2 10.74 52 0 5.26 53 0 3.78 54 0 0.44 55 0 1.35 56 0 9.41 57 0 2.03 58 0 8.32 59 0 4.44 60 1 9.01 61 0 3.56 62 0 0.40 63 0 1.14 64 0 0.73 65 0 0.90 66 1 5.92 67 0 7.58 Vol. 2, Part 2 G-71 NUREG/CR-6143 j l i l
I LOSP Frequency
-$RUNIEFREQ1 l INPUT THE NAME OF THE DATA FILE (ENCLOSED IN TICK MARKS) !
'IE.DAT* '
1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 ! 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 l 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 [ 61 62 63 64 65 66 67 ' INPUT THE ID FOR THE PLANT OF INTEREST 23 PLANTID = 23, NUMBER OF FAILURES = 0., NUMBER OF YEARS = 1.2 SUM OPER. YRS - 312.690000000000 IF YOU KNOW THE VALUE OF CONSTANT, TYPE 1;O.W. TYPE 2 2 l INPUT THE FAILURE FREQUENCY FOR PLANT LOSP FOR 23
'91 ;
PLEASE WAIT WIIILE THE INTEGRATION IS PERFORMED CONSTK= 5.158047635733690E 030 THE CUMULATIVE PROBABILITY FOR PLANT LOSP FOR A FAILURE FREQUENCY OF 0.291000 AT 23 IS 0.999005 IS THIS VALUE SATISFACTORY 7 Y OR N Y $ FORTRAN STOP l l t t 1 i f , [ l , f I f NUREGICR-6143 G-72 Vol. 2, Part 2 ! i r l l
- . . ~ _ . _ _ _ .
F l l LOSP Frequency i 1 t Attachment G-11 IEBAT.COM for CATEGORY IV t 4 f Vol. 2, Part 2 G-73 NUREG/CR-6143
.7 IDSP Frequency .
$ SET VERIFY
$ SET DEFAULT UD4:[BDSTAPL] !
$ RENAME LOSP,JE_IV.INP IEFREQ.INP - !
$ RUN IEBATI
$ RENAME IEFREQ.INP LOSP_IE IV.INP ;
$ RENAME PLOT.DATIE IV.DAT '
i e
)
i f y l
'I r
I 1 l i T 3 t i 1 r NUREGICR-6143 c.74 Vol. 2, Part 2 , l : 1 ; i 1 s l,_ . . . _ _ _ _ . , . . - _ - - - - . - - - - - - -
I I I LOSP Frequency I I l l > Attachment G-12 ; LOSP_IE_IV.INP r t r I ! I t Vol. 2, Part 2 G.75 NUREG/CR-6143
LOSP Frequency
'IDSP IE IV.DAT' 23 .29130 i
l l l l NUREG/CR4143 G-76 l Vol. 2. Part 2 l i }
i LOSP Frequency i l 1 l i Attachment G-13 IE_IV.DAT i l l l l l l l i I i Vol. 2, Part 2 G-77 NUREG/CR-6143 l
LOSP Frequency 0.107778E-04 0.000552 0.862222E-04 0.001262 0.291000E-03 0.002208 0.68977BE-03 0 003445 0.134722E-02 0.005048 0.232800E 02 0.007116 0.36%78E-02 0.009782 0.551822E 02 0.013229 0.785700E-02 0.017711 0.107778E 01 0.023589 0.143452E-01 0.031407 0186240E-01 0.042058 0.236788E-01 0.057274 0.295742E 01 0.085147 O.363750E-01 0.136164 0.441458E-01 0.238943 0.529512E-01 0.443061 0 628560E-01 0.695064 0.739248E-01 0.840654 0.862222E-01 0.925578 0.998130E 01 0.9606 % 0.114762E+00 0.977024 0.131133E + 00 0.985120 0.148992E + 00 0.990093 , 0.168403E + 00 0.993320 0.189430E+ 00 0.995462 0.212139E + 00 0.996903 0 236594E+00 0.997882 0.262859E + 00 0.998550 0' 291000E +00 0.999005 1 l i NUREG/CR4143 G-78 Vol. 2, Part 2
LOSP Frequency 4
)
I Attachment G-14 IE_IV.DAT l l Vol. 2. Part 2 G-79 NUREG/CR-6143
l LOSP Frequency O.100000E4'l 0.000000 0.107778E-04 0.000552 0.862222E-04 0.001262 0.291000E43 0.002208 0.689778E-03 0.003445 0.134722E-02 0.005048 0.232800E-02 0.007116 0.369678E-02 0.009782 0.551822E-02 0.013229 0.785700E-02 0.017711 0.107778E-01 0.023589 0.143452E-01 0.031407 0.186240E-01 0.042058 0.236788E-01 0.057274 0.295742E-01 0.085147 0.363750E-01 0.136164 0.441458E-01 0.238943 0.529512E-01 0.443061 0.628560E-01 0.695064 0.739248E-01 0.840654 0.862222E-01 0.925578 0.998130E-01 0.9606 % 0.I14762E + 00 0.977024 0.131133E+00 0.985120 0.148992E + 00 0.990093 0.168403E+00 0.993320 0.189430E + 00 0.995462 0.212139E + 00 0.996903 0.236594E + 00 0.997882 0.262859E +00 0.998550 0.291000E + 00 0.98005 0.850000E + 00 1.000000 G-80 Vol. 2, Part 2 NUREO/CR 6143 F
LOSP Frequency l l l l l t Attachment G-15 IEBAT. LOG for CATEGORY IV 1 l l
)
i I
= l 1
l 1 Vol. 2, Part 2 G-81 NUREG/CR-6143 !
LOSP Frequency $8st NoControl-Y $8st NoVerify $ SBT DEPAULT UD4:[BDSTAPL] $ RENAME LOSP_IE_IV.INP IEFREQ.INP $RUNIEBATI PORTRAN STOP $ RENAME IEFREQ.INP LOSP_IE_IV.INP $ RENAME PLOT.DAT IE_IV.DAT BDSTAPL job ternunated at 31-MAY-1991 13:57:27.78 Accounting information: Buffered I/O count:132 Peak working set sim:1199 Direct I/O count:102 Peak page file size:4274 I Page faults:4115 Mounted volumes:0 Charged CPU time:0 00:33:21.77 Elapsed time:0 00:36:17.30 NUREO/CR 6143 G-82 Vol. 2, Part 2
n-- 1 l LOSP Frequency l 1
)
i Attachment G-16 - l IE IV.DAT l 1 l l 4 l l l
)
l Vol. 2, Part 2 G-83 NUREG/CR-6143
LOSP Frequency 0.107778E-04 0.000552 0.862222E-04 0.001262 0.291000E-03 0.002208 0.689778E-03 0.003445 0.134722E-02 0.005048 0 232800E-02 0.007116 0.36%78E 02 0.009782 0.551822E-02 0.013229 0.785700E 02 0.017711 0107778E-01 0.023589 0.143452E 01 0.031407 0.186240E-01 0.042058 0.236788E-01 0.057274 0.295742E-01 0.085147 0.363750E-01 0.136164 1 0.441458E-01 0.238943 0.529512E-01 0.443061 0.628560E-01 0.695064 0.739248E-01 0.840654 , 0.862222E-01 0.925578 O.998130E-01 0.960696 0.114762E + 00 0.977024 0.131133E + 00 0.985120 0148992E +00 0.990093 0.168403E + 00 0.993320 0189430E +00 0.995462 l 0.212139E + 00 0.996903 0.236594E + 00 0.997882 0.262859E + 00 0.998550 0.291000E+00 0.999005 l I i I NUREG/CR-5143 G-84 Vol. 2. Part 2
LOSP Frequency ; I I I l l l
)
I I i l 1 Attachment G-17 IE_IV.DAT (Updated) Vol. 2, Part 2 G-85 NUREG/CR-6143
-,n. . . - -1, -
LOSP Frequency t 0.100000E-07 0.000000 0.107778E-04 0.000552 : 0 862222E44 0.001262 i 0.291000E-03 0.002208 0.689778E-03 0.003445 0.134722E-02 0.005048 ? O 96 E 0. 2 0.551822E-02 0.013229 i 0.785700E-02 0.017711 0.107778h-01 0.023589 , 0.143452E-01 0.031407 O.186240E-01 0.042058 0.236788E-01 0.057274
- 0.295742E-01 0.085147 I
0.363750E-01 0.136164 0.441458E41 0.238943 i 0.529512E 01 0.443061 0.628560E-01 0.695064 . r 0.739248E-01 0.840654 , O.862222E-01 0.925578 O.998130E-01 0.9606 % 0.114762E + 00 0.977024 0.131133E + 00 0.985120 i 0.148992E+00 0.990093 0.168403E +00 0.993320 0.189430E + 00 0.995462 0.212139E + 00 0.996903 1 0.236594E + 00 0.997882 1 0.262859E + 00 0.998550 i 0.291000E + 00 0.999005 0.850000E + 00 1.000000 I l NUREG/CR-6143 G-86 Vol. 2, Part 2 l l___________.___ --
1 LOSP Frequency Attachment G-18 LHS.COM Vol. 2. Part 2 G-87 NUREG/CR4143
,d}m Y '
LOSP Frequency
$ ASSIGN LHS.DAT FOR001 $ ASSIGN LHS.INP FOR005 $ ASSIGN LHS.OUT FOR006 $ RUN LHS $ DELETE FOR*.DAT;*
i i NUREG/CR4143 G-88 Vol. 2, Part 2 l l
LOSP Frequency T 7 f Attachment G-19 t L11S.INP 3 1 l l l l 1 i l Vol. 2, Part 2 G 89 NUREGICR4143
LOSP Frequency TITLE - LHS SAMPLE FOR LOSP INITIATING EVENT : RANDOM SEED 1787673089 NOBS 1000 RANDOM SAMPLE USER DISTRIBUTION IE_PCGW.DAT USER DISTRIBUTION IE_lV.DAT OUTPUT HIST t i l I NUREG/CR-6143 G-90 Vol. 2, Part 2
LOSP Frequency i Attachment G 20 Subroutine USRDST.FOR i i l 1 1 I G-91 NUREG/CR-6143 Vol. 2. Part 2
LOSP Frequency C**************************************************************** SUBROUTINE USRDST(J) C C MODIFIED BY G. WILKINSON (11/8/88) FOR ARTHUR PAYNE SAMPLE - C MODIFIED FOR LASALLE BY T. T. SYPE (6/15/89) C MODIFIED FOR GRAND GULF LOSP BY BEVAN STAPLE (5/31/91) C SUBROUTINE USRDST WILL GENERATE VALUES FROM A C 1) DISCRETE DISTRIBUTION (WITH AND WITHOUT INTERPOLATION); C C THE FOLLOWING SIX LINES OF CODE ARE REQUIRED BY USRDST: C C NMAX IS THE MAXIMUM NUMBER OF OBSERVATIONS. C NVAR IS THE MAXIMUM NUMBER OF VARIABLES. C LENT IS THE LENGTH OF THE TITLE. C PARAMETER (NMAX= 1000) PARAMETER (NVAR=200) ' PARAMETER (LENT = 125) COMMON /PARAMfrITLE(LENT),lSEED,N,NV,lRS ICM,NREP,lDATA,lHIST, 1 ICORR,IDIST(NVAR),IRP COMMON /SAMP/X(NMAX*NVAR) C C Tile FOLLOWING PARAMETERS ARS REQUIRED FOR THE DISCRETE PROBABILITY FUNCTION C PARAMETER (NCP= 100) DIMENSION XVAL(NCP), CP(NCP) C C Tile FOLLOWING PARAMETERS ARE REQUIRED FOR THE LOSP VARIABLES C
- C NP IS Tile NUMBER OF PAIRS OF IVAL AND FREQ C IVAI.(K)IS TIIE KTH UNIQUE VALUE OF Tile RANDOM VARIABLE C FREQ(K)IS THE PROBABILITY ASSOCIATED WITH THE KTH VALUE C
PARAMETER (M AXNP= 500) DIMENSION IVAL(MAXNP),FREQ(M AXNP),CDF(M AXNP + 1) C C THE FOLLOWING FUNCTION DEFINITION IS REQUIRED BY USRDST. C LOC (I,J) = (1-1)
- N + I C
C READ FROM LIIS INPUT FILES C IFLAG = IFLAG + 1 IF(J.EQ.1) THEN IF (IFLAG.EQ 1)OPEN(UNIT = 60, FILE = 'IE_PCG W.D AT*, STATUS = 'OLD') NP = 32 IF(IFLAG.EQ.1) WRITE (6,12) 12 FORMAT ('I',/,/,6X,' INPUT DATA FOR IE_PCGW',/,IlX,'XVAL',14X,'CP') DO 5 K-1,NP READ (60,*) XVAL(K), CP(K) IF(I FLAG . EQ.1) WRITE (6,14)X V A L(K),C P(K ) 14 FORMAT (6X,E13 7,3X,E13.7) 5 CONTINUE REWIND 60 NUREG/CR-6143 G-92 Vol. 2. Part 2
LOSP Frequency C ELSEIF (J.EQ.2) THEN IF(IFLAG EQ.2)OPEN(UNIT =61. FILE ='IE_IV.DAT', STATUS ='OLD') NP-32 IF (IFLAG.EQ 2) WRITE (6,16) 16 FORMAT ('I',/,/,6X,' INPUT DATA FOR IE_IV',/,IlX,'XVAL',14X,'CP') DO I K-1,NP READ (61,*) XVA14K), CP(K) IF(IFLAG.EQ 2) WRITE (6,18) XVAMK), CP(K) 18 FORMAT (6X,EI3.7,3X,E13.7) 1 CONTINUE ' REWIND 61 C ENDIF C C SET TIIE STARTING POINT (STRTPT) EQUAL TO ZERO AND TIIE PROBABILITY C INCREMENT (PROBINC) EQUAL TO 1/N FOR A LHS WIIERE N IS THE SAMPLE SIZE C STRTirT= 0.0 PROBINC-1.0/ FLOAT (N) IF(IRS EQ.1)PROBINC= 1.0 C C TIIIS LOOP WILL OBTAIN THE N SAMPLES C ITEMP=1 DO 4 I-1,N R-STRTPT + PROBINC*RAN(ISEED) C DO 3 K-ITEMP,NP-1 IF(R.GE.CP(K). AND.R.LT.CP(K + 1)) THEN IF(XVAL(K).EQ.XVAL(K + 1)) THEN C C DISCRETE PROBABILITY C X(LOC (I,J))=XVAL(K) j ELSE i C C INTERPOLATION C X(LOC (I,1)) = ((R-CP(K))/(CP(K+1)-CP(V.)))* 1 (XVAL(K +1).XVAL(K))+ XVA14K) ENDIF IF(IRS.NE.1) ITEMP = K
% TO 25 ENDIF 3 CONTINUE 25 CONTINUE IF(IRS.NE.1)STRTI'T=STRTPT + PROBINC 4 CONTINUE 00 TO 99 C
99 RETURN END Vol. 2. Ps.rt 2 G-93 NUREO/CR-6143
LOSP Frequency 1 i I
)
l Attachment G-21 l I LHS.OUT 1 I i NUREG/CR-6143 G-94 Vol. 2, Part 2
LOSP Frequency TITLE - LHS SAMPLE FOR LOSP INITIATING EVENT *** RANDOM SAMPLE *** RANDOM SEED - 1787673089 NUMBER OF VARIABLES - 2 NUMBER OF OBSERVATIONS - 1000 l l HISTOGRAMS OF THE ACTUAL SAMPLE WILL BE PLOTTED FOR EACH INPUT VARIABLE TITLE - LHS SAMPLE FOR LOSP INITIATING EVENT VARIABLE DISTRIBUTION RANGE LABEL 1 USER SUPPLIED DISTRIBUTION IE_PCGW.DAT 2 USER SUPPLIED DISTRIBUTION IE IV.DAT INPUT DATA FOR IE_PCGW XVAL CP 0.1000000E-07 0.0000000E + 00 0.1540740E-04 0.9780000E-03 0.1232590E-03 0.3558000E 02 0.4160000E-03 0.8215000E-02 0.9860740E-03 0.1559000E-01 0.1925930E 02 0.2645200E-01 0.3328000E-02 0.4169700E-01 0.5284740E42 0.6232800E-01 0.7888590E-02 0.8940900E 01 0.ll23200E-01 0.1240020E +00 0.1540740E 01 0.1670350E + 00 0.2050730E O1 0.2191490E + 00 0.2662400E-01 0.2805140E+ 00 0.3385010E-01 0.3505850E +00 0.4227790E-01 0.4279060E + 00 0.5200000E-01 0.5100820E+00 0.6310870E-01 0.5938320E + 00 0.7569660E OI 0.6753370E+ 00 0.8985600E-01 0.7500740E + 00 0.1056790E + 00 0.8140620E + 00 0.1232590E + 00 0.8659660E + 00 0.1426880E +00 0.9062610E + 00 0.4640580E + 00 0.9362880E + 00 0.1874620E + 00 0.9578470E + 00 0.2129920E + 00 0.9728260E + 00 0.2407410E + 00 0.9829460E + 00 0.2708010E +00 0.9895920E + 00 0.3032640E + 00 0.9938610E + 00 0.3382230E + 00 ' O.9965120E + 00 0.375771OE + 00 ' O.9981450E + 00 0.4160000E + 00 0.9990060E + 00 0.9000000E + 00 0.1000000E + 01 Vol. 2, Part 2 G-95 NUREG/CR-6143
LOSP Frequency INPUT DATA FOR IE_IV XVAL CP 0.1000000E-07 0.0000000E +00 l 0.1077780E-04 0.5520000E-03 0.8622220E-04 0.1262000E-02 0.2910000E-03 0.2208000E-02 0.6897780E 03 0.3445000E-02 0.1347220E-02 0.5048000E 02 0.2328000E 02 0.7116000E-02 0.36%780E-02 0.9782000E-02 ! 0.5518220E-02 0.I322900E-01 0.7857000E-02 0.1771100E-01 0.1077780E 01 0.2358900E 01 0.1434520E-01 0.3140700E-01 0.I862400E-01 0.4205800E-01 0.2367880E-01 0.5727400E-01 0.2957420E-01 0.8514700E-01 0.3637500E-01 0.1361640E + 00 0.4414580E-01 0.2389430E + 00 0.5295120E-01 0.4430610E + 00 0.6285600E-01 0.6950640E +00 0.7392480E-01 0.8406540E + 00 0.8622220E O1 0.9255780E + 00 0.9981300E-01 0.9606960E +00 0.I147620E + 00 0.9770240E + 00 0.1311330E + 00 0.9851200E + 00 0.1489920E + 00 0.9900930E + 00 0.1684030E + 00 0.9933200E + 00 0.1894300E + 00 0.9954620E + 00 0.2121390E+00 0.9969030E+ 00 0.2365940E +00 0.9978820E + 00 0.2628590E+ 00 0.9985500E + 00 0.2910000E + 00 0.99900.iOE + 00 0.8500000E + 00 0.1000000E + 01 TITLE - LIIS SAMPLE FOR LOSP INITIATING EVENT *** RANDOM SAMPLE *** lilSTOGRAM FOR VARIABLE NO. I USER SUPPLIED DISTRIBUTION MIDPOINT FREQ. 0.1050000E-01 237 0.3150000E O1 199 0.5250001E41 154 0.7350001E 01 116 0.9450002E-01 98 0.1155000 67 0.1365000 38 0.1575000 34 0.1785000 19 NUREG/CR-6143 G-96 Vol. 2, Part 2
LOSP Frequency 0.1995000 14 0.2205000 10 0.2415000 5 0.2625000 1 0.2835000 2 0.3045000 3 0.3255000 1 0.3465000 0 0.3675000 0 0.3885000 1 0.4095000 1 1000 MIN MAX RANGE MEAN MEDIAN VARIANCE 0.1252443E 05 0.4126163 0.4126150 0.6490128E-01 0.5088609E-01 0.3193550E-02 Vol. 2, Part 2 G-97 NUREG/CR-6143
I i i z TITLE - LHS SAMPLE FOR LOSP LNITIATING EVENT
- RANDOM SAMPLE ** t C v W M g HISTOGRAM FOR VARIABLE NO. 2 USER SUPPLIED DISTRIBUTION ]
a .I W MIDPOINT FREQ. E
& g b 0.2100000EOI 229 XXXXXXXX 0.6299999EOI 676 XXXXXXXXXXX 0.1050000 70 XXXXX 0.1470000 18 XXXXXXXXXXXXXXXXXX 0.1890000 3 XXX 0.2310000 0 0.2729999 2 XX 0.3149999 0 0.3569999 0 0.3989999 0 0.4409999 0 0.4829999 0 0.5249999 0 0
6 0.5669999 0 0.6089999 0 0.6509999 0 0.6929999 0 0.7349999 0 0.',769999 1 X 0.8189999 0 0.8609999 1 X 1000 MIN MAX RANGE MEAN MEDIAN VARIANCE 0.1395887E-03 0.8440393 0.8438997 0.5364298E-01 0.5470004E-01 0.1796476E-02 4 E' 2 N
LOSP Frequency l l Attachment G-22 LHS.DAT Vol. 2, Part 2 G-99 NUREG/CR-6143
l l LOSP Frequency I 1 2 9.5802836E-02 5.7157081E-02 54 2 6.3890698E-03 6.1642252E-02 2 2 5.0940670E-02 6.0416732E-02 55 2 1.1955368E-02 5.3150438E42 3 2 3.7110481E-02 5.8251712E-02 56 2 2 0493850E-02 0.1857526 l 4 2 0.3011881 5.3329077E-02 57 2 3.9378010E-02 3.7598554E-02 l 5 2 6.8660229E-02 5.5287939E-02 58 2 3.5381936E-02 4.7152728E-02 6 2 4.1418765E-02 5.6494150E-02 59 2 6 2365174E-02 7.5856574E-02 7 2 3.8164826E-03 6.1932772E-02 60 2 6.9060028E-02 8.9874759E-02 l 8 2 7.3756211E-02 9.4944753E 02 61 2 4.4734307E-02 5.6779027E-02 l 9 2 0.1116926 5.5104259E-02 62 2 4 3982375E-02 6.2561035E-02 10 2 8.3901752E-03 5.9206437E-02 63 2 6 0694963E-02 3.8645752E-02 l 11 2 2.1001803E-04 0.1903778 64 2 91746241E-02 0.1081921 ! 12 2 0.19843083.84 71486E-02 65 2 12195393E-02 0.1378729 13 2 6.1446220E-02 5.7531755E-02 66 2 9.7427778E-03 4.6029627E-02 14 2 1.3037866E-02 7.0953816E 02 67 2 1.9653393E-02 4.2656578E-02 15 2 8.6331956E-02 6.8710037E-02 68 2 3.1145809E-02 4.1980006E-02 16 2 .3.7155%7E-02 3.2672279E-02 69 2 7.1229465E-02 6.0362123E-02 17 2 3.2555930E-02 4.4575006E-02 70 2 5.5966739E-02 0.1215986 18 2 4.5071386E-02 3.1056585E-02 71 2 2.9009812E-02 6.5682463E-02 19 2 6.3797474E-02 4.6071306E-02 72 2 7.5244442E-02 5.8911454E-02 20 2 4.3774538E-02 3.0516183E-02 73 2 7.8743502E-02 5.4237224E-02 21 2 0.1065058 7.9281092E-02 74 2 5.0527163E-02 6.1270196E-02 22 2 5.5102311E-02 3.2996830E-02 75 2 3.1681322E-02 8.5060455E-02 23 2 3.5599325E-02 4.8942689E-02 76 2 5.1817849E-02 5.0090570E-02 24 2 2.0490789E-03 4.5054294E-02 77 2 5.08315ME-02 2.4951266E-02 25 2 2.5542006E-02 2.5336470E-02 78 2 0.1170508 6.8073846E-02 26 2 4.6561282E-02 7.3678486E-02 79 2 3.0360568E-02 4.9490560E-02 27 2 9.7525999E-02 7.1654484E-02 80 2 3.7065927E-02 5.0325025E-02 l 28 2 3.6980748E 02 6.9754799E-03 81 2 8.4724374E-02 3.4361262E-02 29 2 3.8461756E-02 2.1312614E-03 82 2 0.2172877 7.2943039E-02 l 30 2 0.1308402 4.2214524E-02 83 2 0.1707056 6.1654635E-02 31 2 1.5121906E-02 6.1416168E-02 84 2 4.1157823E-02 6.0433898E-02 l 32 2 0.1576969 4.6902116E-02 85 2 4.6242714E-02 5.8522064E-02 33 2 1.1520608E-02 6.0953710E-02 86 2 7.8710178E-03 6.0102671E-02 34 2 0.1065259 9.959001 IE-02 87 2 8.4139876E-02 7.9868220E-02 35 2 0.1838354 9.7384945E-02 88 2 9.9810176E-02 6.6642977E-02 36 2 2.3105722E-02 5.1488169E-02 89 2 5.6254819E-02 7.4072085E-02 37 2 7.8000881E-02 8.7991364E 02 90 2 4.5131359E-02 3.6564417E-02 38 2 8.4191918E-02 4.7253303E-02 91 2 0.1175776 6.0518596E-02 l 39 2 3.0882679E-02 3.7661687E-02 92 2 2.3901181E-02 5.5216696E-02 l 40 2 0.1 $ 68672 9.2032492E 02 93 2 6.8641901E-02 4.5617305E-02 41 2 6.9784876E-03 2.3598088E-02 94 2 8.4755734E-02 3.5917133E-02 42 2 2.8681975E-02 3.9681610E-02 95 2 4.7624674E-02 5.0922580E-02 43 2 2.7508037E-02 8.6506894E-03 96 2 7.6687358E-02 4.7751363E-02 44 2 5.7893977E 02 3.1828873E-02 97 2 6.1508259E-03 6.2739216E-02 45 2 8.7122709E 02 3.0945832E-02 98 2 6.9542497E-02 6.6954583E-02 46 2 4.0420175E-02 0.1134561 99 2 5.0025929E-02 7.1312711E-02 47 2 6.7433029E-02 4.9484331E-02 100 2 7.6181762E-02 0.1293133 48 2 3.1565614E 02 5.5348329E-02 101 2 4.7242548E-02 2.8N1681E-02 l 49 2 6.2981918E-02 4.5933411E-02 102 2 51474594E-02 4.7649670E-02 50 2 3.6439944E-02 6.5376133E-02 103 2 1.6576273E-02 8.9545082E-03 l 51 2 2 3256298E-03 61091572E-02 IN 2 3.3260591E-02 4.7793541E-02 52 2 3 7388284E-02 6.3234374E-02 105 2 5 7211630E-02 4.9049694E-02 53 2 4.9667925E-02 8.1571952E-02 106 2 9.6157566E-02 5.0513197E-02 NUREG/CR-6143 G-100 Vol. 2, Part 2 I
1 l LOSP Frequency 107 2 0.1619431 3.6086690E-02 160 2 0.1213369 6.8935312E-02 108 2 6.5522656E-02 5.0114769E-02 161 2 4.5888089E-03 8.6619906E-02 109 2 9.9551871E-02 5.3492881E-02 162 2 7.6253237E-03 7.2223626E 02 110 2 3.2978956E-02 8.2634754E-02 163 2 0.1213599 5.0378244E-02 111 2 5.2812852E-02 6.2103730E-02 164 2 5.0322939E-02 5.5347841E-02 112 2 4.1240700E-02 5.0557747E-02 165 2 5.3692952E-02 1.6964931E-02 113 2 7.0628084E-02 3.3015352E 02 166 2 6.8147582E-02 5.8529630E 02 114 2 3.2155325E-03 5.7052251E-02 167 2 0.3917790 4.3206576E-02 115 2 0.2955990 0.1668376 168 2 5.7127774E-02 1.4987160E-02 116 2 '0.1707724 1.8475348E-02 169 2 8.3935164E-02 8.4336311E-02 117 2 5.5750683E-02 5.8639225E-02 170 2 5.8236878E-02 5.1324982E-02 118 2 3.3989530E-02 5.5715863E-02 171 2 2.7824761E-02 5.8796186E-02 119 2 9.6589506E-02 6.0960405E-02 172 2 1.0342170E-02 6.6040970E-02 120 2 4.4756867E-02 2.0783002E-02 173 2 0.1130472 4.6403021E-02 121 2 7 3829912E-02 3.9646626E-02 174 2 1.9324374E-03 2.1041799E-02 122 2 0.12158771.57 97980E-02 175 2 2.1123756E-02 5.4619823E-02 123 2 8.4925257E-02 2.0765597E-02 176 2 7.3582875E-03 3.7066460E-02 124 2 5.1617451E-02 5.5218507E-02 177 2 8.1938533E-03 5.8557700E-02 125 2 1.6678156E-02 5.4130182E-02 178 2 3.8392141E-03 5.4025233E-02 126 2 1.7280921E-02 4 7160003E-02 179 2 0.1114586 4.5126867E-02 127 2 6.1498184E-02 5 8692340E-02 180 2 3.7242990E+ 6.1717805E-02 128 2 0.1538038 2.3057584E-02 181 2 1.9190241E-02 4.8077114E-02 129 2 7.0079938E-02 5.9342016E-02 182 2 2.3559626E-02 4.2224646E-02 130 2 4 6549104E-02 1.9712312E-02 183 2 6.7579068E-02 5.4060549E-02 131 2 8.5495159E-02 1.8631760E-02 184 2 0.I495474 0.1292609 132 2 2.9121149E-02 6.0043842E-02 185 2 8.7243997E-02 5.6941222E-02 133 2 5.2379847E-02 6.7772292E-02 186 2 3.9188843E-03 4.8121687E-02 134 2 2.2424161E-02 5.7133570E-02 187 2 2.0487398E-02 6.9975689E-02 135 2 1.4448942E-02 7.5433329E-02 188 2 0.1687348 5.1983319E-02 136 2 0.12594440 4.9683046E-02 189 2 1.9494988 E-02 3.7827380E-02 137 2 2.1840738E-02 3.7463218E-02 190 2 3.1080063E-02 2.2208920E-02 138 2 4.6944050E-03 6.5001808E-02 191 2 3.3260230E-02 3.4254942E-02 139 2 6.5334700E-02 3.5716325E-02 192 2 0.1394177 6.1570350E-02 140 2 0.1371943 1.9875966E-02 193 2 4.6089880E-02 8.3428882E-02 141 2 1.6964525E-02 8.1631653E-02 194 2 0.1716556 5.5070791E-02 142 2 0.1015151 2 9490849E-02 195 2 5.3486563E-02 7.9588860E-02 143 2 1.8315334E-02 4.D35792E-02 196 2 4.7258500E-02 0.1550756 144 2 3.3113606E-02 3.9712951E-02 197 2 3.3940416E-02 8.4298290E-02 145 2 0.1321511 6.5156333E-02 198 2 2.1830970E-02 5.5529773E-02 146 2 4.2373762E ^2 6.5489277E-02 199 2 4.0602647E 03 5.6944489E-02 147 2 7.2913952E-03 5.9004165E-02 200 2 1.0020436E-02 5.4907784E-02 148 2 6.3795552E-02 4.7587328E-02 201 2 3.7182402E-02 4.9482226E-02 149 2 0.2103213 8.3966292E-02 202 2 4.2706481 E-03 0.1606795 150 2 0.1109417 4.0622294E-02 203 2 3.1993993E-02 5.3374309E-02 151 2 0.1395433 5.4257885E-02 204 2 7.7867016E-02 2.8862229E-02 152 2 4.7899157E-02 0.1202568 205 2 4.5282654E-02 4.6392612E-02 153 2 6.8555456E-02 6.0329355E-02 206 2 2.3415735E-02 6.4310737E-02 154 2 4.7816616E-03 3.7393130E-02 207 2 0.2160491 5.5371974E-02 155 2 1.3575777E-02 2.2464391E-02 208 2 6.4673787E-03 0 7566715 156 2 3.7566062E-02 1.2979862E-02 209 2 1.7433336E-02 5.5316355E-02 157 2 9.9475965E-02 3.7282106E-02 210 2 2.2904482E-05 4.6597488E-02 158 2 0.1179500 4.4079732E-02 211 2 0.1147942 5.9636269E-02 159 2 0.1407464 8.6003169E-02 212 2 7.6124631E-02 7.3863171E-02 Vol. 2, Part 2 0-101 NUREG/CR-6143
,m
LOSP Frequency 213 2 5.3303089E-02 6.8604030E-02 266 2 0.1101487 5.3302426E-02 214 2 5.0968453E-02 3.0148089E-02 267 2 1.0786332E-02 6.1759170E 02 215 2 0.1519960 5.0956085E-02 268 2 0.1050531 6.6191122E-02 216 2 9.9529408E-02 5.1027179E-02 269 2 8.6179286E-02 3.9748408E-02 217 2 - 1.2661025E-O'2 3.2987788E-02 270 2 7.1867579E-03 4.2479008E-02 218 2 1.1452804E-02 1.9742427E-02 271 2 9.5057264E 02 5.1139485E-02 219 2 5.9550323E-02 8.1923068E-02 272 2 0.1684978 2.7940258E-02 220 2 8.4897578E-02 3.2943714E-02 273 2 1.2539796E-02 7.8760505E-02 221 2 0.1265632 4.4650719E-02 274 2 6.4291013E-03 4.0083379E-02 222 2 0.1636941 6.5610617E-02 275 2 7.7832922E-02 5.9734005E-02 223 2 7.2806217E-02 7.1486212E-02 276 2 0.1206533 4.1501082E-02 224 2 9.7682148E-02 0.1179187 277 2 5.6917291E-02 4.7410175E-02 225 2 4.3897450E 02 5.7352368E-02 278 2 3.6365487E-02 5.2262317E-02 226 2 5.3755235E-02 0.1008180 279 2 7.0993602E-02 4.4433460E-02 227 2 7.2366193E 02 0.1015658 280 2 4.3315183E-02 6.5824345E-02 l 228 2 0.2446719 3.0301256E-02 281 2 7.4349679E-02 0.1840891 I 229 2 8.7504514E-02 7. ll35163E-02 282 2 9.5265292E-02 8.2059130E 02 l 230 2 6.1651595E-02 7.9552941E 02 283 2 0.1238719 3.2222025E-02 l 231 2 0.12M444 5.2140828E-02 284 2 9.5689654E-02 8.1871301E-02 232 2 1.0141240E-02 4.9205273E-02 285 2 0.2603333 0.1265700 233 2 2.9848058E-02 5.8265250E-02 286 2 0.1145876 5.6587834E-02 234 2 9.4402153E-03 5.9602566E-02 287 2 6.2036499E-02 5.0692923E-02 235 2 4.3066703E-03 7.0935003 E-02 288 2 0.1287113 5.4666784E-02 236 2 8.8652149E-03 8.9759074E-02 289 2 7.6434948E-02 0.2836348 237 2 8.2147315E-02 3.4737453E-02 290 2 3.7384395E-02 5.1759280E-02 238 2 8.9766808E-02 2.2139974E-02 291 2 5.5710252E-02 7.9793416E-02 239 2 5.7522781E-02 8.4488504E-02 292 2 3.0785400E-02 6.5113649E-02 240 2 1.9196231E-02 7.9581648E-02 293 2 0.1471515 6.0857952E-02 241 2 3.2749761E-02 6.2474120E-02 294 2 1.6241783E-02 5.7650033E-02 242 2 7.4022703E-02 4.1953418E-02 295 2 5.5924322E-02 3.0042961 E-02 243 2 2.8199911E-02 5.1889852E-02 296 2 3.6231801E-02 4.6817876E-02 > 244 2 0.lM4558 6.7030467E-02 297 2 5.1834852E-02 7.3877349E-02 245 2 3.6798760E-02 8.6043261E-02 298 2 1.36161041E-02 4.0530287E-02 246 2 2.8888844E-02 3.2008789E-02 299 2 0.1356705 3.7863705E-02 247 2 0.1416059 4.2976875E-02 300 2 6.1036717E-02 5.6248203E-02 248 2 1.1433396E-02 4.2970411E 02 301 2 3.2080885E-02 8.4085375E-02 249 2 8.4602527E-02 4.8343554E-02 302 2 6.3935861E-02 5.3747039E-02 250 2 0.1223382 4.7623150E-02 303 2 8.4782112E-03 5.2066682E-02 251 2 5.3186379E-02 7.3586397E-02 304 2 0.1483902 3.3199754E-02 252 2 9.5278546E-03 7.3705859E-02 305 2 1.6334236E-02 4.4072583E-02 253 2 3.6003832E-02 6.3980505E 02 306 2 2.6464649E-02 6.5281264E-02 254 2 0.2368298 6.8291128E-02 307 2 3.3093113E-02 6.1957162E-02 255 2 9.8380804E-02 5.4853976E-02 308 2 0.1980580 6.3871555E-02 > 256 2 0.1627849 6.9135174E 02 309 2 3.2279663E-02 3.2386724E-02 257 2 4.3205872E-02 5.5737238E-02 310 2 7.2981618E-02 2.3961281E-02 258 2 7.7809721E-02 5.7787050E-02 311 2 1.0505857E-02 6.9583394E-02 259 2 9.2956319E-02 6.5993495E-02 312 2 2.7589556E-02 4.9572527E-02 l 260 2 0.1799912 5.1761754E-02 313 2 9.8100808E-03 4.5669530E-02 261 2 5.3744238E-02 0.1043923 314 2 0.1137452 6.7695037E-02 262 2 2.3056671E-02 5.9782274E-02 315 2 7.2744422E-02 8.2279146E-02 263 2 6.4727686E-02 7.6576352E-02 316 2 9.1899738E-02 5.7338905E-02 264 2 0.1216711 5.7241727E-02 317 2 3.0302284E-02 7.9181217E-02 265 2 0.3209038 7.3334612E-02 318 2 4.4912171E-02 5.0130807E-02 NUREG/CR-6143 G-102 Vol. 2, Part 2 1 1
l l LOSP Frequency 319 2 1.7556440E-02 4.8635080E-02 372 2 5.7035097E-04 5.1698089E-02 320 2 7.8613654E-02 7.7345565E-02 373 2 4.2432569E-02 7.5730167E-02 321 2 7.6832488E-02 6.1814152E-02 374 2 1.4777359E-02 4.6410918E-02 322 2 5.3756524E-02 3.1926371E-02 375 2 3.2787994E-02 6.7062199E-02 323 2 0.1039997 5.9751723E-02 376 2 5.1232055E-02 5.1038437E-02 324 2 5.1588386E-02 6.9555439E 02 377 2 5 4714889E-03 4.4249024E-02 325 2 4.1753639E-02 4.2831965E-02 378 2 2 0741522E-02 S.2121037E 02 326 2 9.4200537E-02 5.0937343E-02 379 2 8.3291810E-04 4.7168367E42 327 2 0.2072446 5.0402451E-02 380 2 9 0837017E-02 3.1095194E-02 328 2 1.9067375E-02 0.1326806 381 2 2 3047213E-02 7.5219192E-02 329 2 5.2268062E-02 4.6196971E-02 382 2 4.1621886E-02 7.2013229E-02 330 2 9.3951240E-02 5.7576288E-02 383 2 3.9833665E-02 5.4039750E-02 331 2 2.5747674E-02 4.7689557E-02 384 2 9.0728611E-02 5.1099844E-02 332 2 9.1002814E-02 5.8826875E-02 385 2 0.1397989 S.3080105E-02 333 2 5.2193556E 02 7.2790295E-02 386 2 4.4620942E-02 4.7020800E-02 334 2 1.3168592E-C2 6.9407247E-02 387 2 0.1943297 4.5590665E-02 335 2 7.8425752E-03 5.0967094E-02 388 2 3.5363667E-02 3.1711053E-02 336 2 2.4083138E42 0.1204861 389 2 6.8349316E-04 4.6826027E-02 337 2 2.9606896E-02 6.9861956E-02 390 2 0.1459142 1.5171967E-02 338 2 3.2791542E-03 8.4400952E-02 391 2 8.0266237E-02 6.2088851E-02 339 2 5.5754423E-02 7.2532296E-02 392 2 19203138E-02 5.7292338E-02 340 2 1.9297315E-02 0.1260565 393 2 7.1140945E-02 4.8464339E-02 341 2 0.1221153 0.1444877 394 2 5.2328020E-02 6.8254374E-02 342 2 0.I836627 7. I748078E-02 395 2 7.3376082E-02 5.7114784E-02 343 2 2.6211066E-02 1.8517802E-02 396 2 6.3577600E-02 4.6294525E-02 344 2 0.1165744 4.8370954E-02 397 2 1.2584946E-03 4.2093381E-02 345 2 7.7690028E-02 5.5468269E-02 398 2 1.5184088E-02 4.1216429E-02 346 2 8.6576715E-03 4.8304219E-02 399 2' 2.0581085E-02 4.8308022E-02 347 2 3.0842939E-02 5.0762452E-02 400 2 2.4160979E-02 6.1195992E-02 348 2 3.4306709E-02 7.1425423E-02 401 2 0.1186002 6.8436407E-02 349 2 8.0743775E-02 3.7325677E-02 402 2 6.6469684E-02 3.3913091E-02 350 2 1.8435411E-02 5.4139994E-02 403 2 3.7167817E-02 4.7778640E-02 351 2 3.2321534E-03 6.7153610E-02 404 2 0.1164t28 4.5537926E-02 352 2 4.0109031E-02 0.2683479 405 2 5.5276338E-02 8.6885706E-02 353 2 7.1211591E-02 9.8831236E-02 406 2 0.1067105 6.1804399E-02 354 2 4.9363904E-02 4.6027701E-02 407 2 6.9141306E-02 5.4143526E-02 355 2 3.8666770E-02 6.8053164E-02 408 2 8.5148111E-02 5.0867260E-02 356 2 5.1464181E-02 5.0975636E-02 409 2 1.0854620E-02 3.4957122E-02 357 2 2.9909359E-02 8.1957847E-02 410 2 7.3132701E-03 4.1457672E-02 358 2 8.5642956E-02 6.1596613E-02 411 2 3.9495885 E-02 6.5525882E-02 359 2 0.1428766 3. ll31679E-02 412 2 0.1621865 4.4940747E-03 360 2 6.8073608E-02 4.3255195E-02 413 2 2.7274314E-02 9.0562209E-02 361 2 3.6340430E-03 2.4262222E-02 414 2 9.4924212E-02 6.5175451E-02 362 2 9.6433230E-02 6.5032646E-02 415 2 7.8715859E-03 7.2900273E-02 333 2 0.1015370 5.0547209E-02 416 2 7.6369330E-02 0.1102054 364 2 4.2306870E-02 3.0492617E-02 417 2 1. ll59037E-02 4.9953319E-02 365 2 8.6678125E-02 2.2774333E-02 418 2 1.6781913E-02 5.9157480E-02 366 2 8.0561943E-02 4.8459731E-02 419 2 9.4187953E-02 3.6562186E-02 367 2 3.5065666E-02 0.1246275 420 2 1.5712211E-02 7.7645145E-02 368 2 5.6423653E-02 5.6726296E-02 421 2 0.1357202 4.8308227E-02 369 2 9.1383748 E-02 0.1002052 422 2 9.6314792E-03 5.2776337E-02 370 2 9 0465531E-02 6.9393113E-02 423 2 3.5887018E-02 4.6999138E-02 371 2 8.2488284E-02 6.2411986E-02 424 2 6.3044518E-02 2.9852998E-02 Vol. 2, Part 2 G-103 NUREG/CR-6143
LOSP Frequency 425 2 6.0450430E-03 5.4368593E-02 478 2 5.8667913E-02 1.1793434E-02 426 2 1.9245146E-02 0.8440393 479 2 8.5019536E-02 5.3816400E-02 427 2 7.1171016E-02 7.2131597E-02 480 2 3.2430448E-02 4.2968925E-02 ' 428 2 6.7888290E-02 7.7404454E 02 481 2 2.915131"lE-02 7.0211180E-02 429 2 5.5506688E-02 7.5137384E-02 482 2 2.0972826E-02 3.0125555E-02 430 2 0.2476660 1.9120978E-02 483 2 9.0942435E-02 6.9475524E-02 431 2 2.9247994E-02 6.0947556E-02 484 2 0.1594650 8.8435039E-02 432 2 6.4376746E-03 5.6334939E-02 485 2 0.1471007 3.7287861E-02 433 2 1.3259222E-02 3.8407531E-02 486 2 6.9947779E-02 6.6194192E-02 434 2 9.5137425E-02 5.0707649E 02 487 2 2.9659139E-03 3.6363807E-02 ! 435 2 1.6477322E 02 2.4710726E-02 488 2 0.1435275 6.4530842E-02 436 2 4.0688049E-02 4.2610008E-02 489 2 0.1113859 7.8945436E-02 437 2 2.2278026E-02 5.1053967E-02 490 2 3.9282557E-02 4.3159917E-02 438 2 2.4768834E-03 6.1949339E-02 491 2 6.1981261E 02 3.8630560E-02 439 2 1.9059179E-02 7.1737774E-02 492 2 1.9839078E-02 7.6724023E-02 440 2 4.2819299E-02 5.2731704E-02 493 2 5.7827588E-02 5.1710501E-02 441 2 9.5047787E-02 8.5911974E-02 494 2 2.5132930E-02 3.8794026E-02 442 2 2.2842348E-02 6.0070943E-02 495 2 4.0411420E-02 5.6560256E-02 443 2 8.9984555E-03 0.1145708 496 2 0.1284811 8.2200252E-02 444 2 4.0717803E-02 4.3459535E-02 497 2 8.3482713E-03 6.4073250E-02 445 2 1.8620146E-02 7.6C92447E-02 498 2 0.1010389 7.6155193E-02 446 2 5.5759195E-03 1.6390927E-02 499 2 1.0805682E-02 6.2696621E-02 447 2 5.9370346E-02 4.4554576E-02 500 2 6.1287235E-02 5.4863572E-02 448 2 1.4559478E-02 4.8129562E-02 501 2 4.9389787E-03 6.3365564E-02 449 2 2.1993279E-02 4.8157401E-02 502 2 5.8028206E-02 6.8783589E-02 450 2 3.4803309E-02 0.1230489 503 2 1.0797053E-02 4.3770362E-02 451 2 0.1713544 5.8508251E-02 504 2 6.0769171E-02 5.1254261 E-02 452 2 4.7787406E-02 5.6298438E-02 505 2 2.5214817E-02 4.5434184E-02 453 2 0.1166827 9.4757400E-02 506 2 1.1230638E-02 6.0345143E-02 454 2 0.1062214 4.4456623E-02 507 2 2.5707522E-02 4.3819964E-02 455 2 1.4152073E-02 3.3927958E-02 508 2 2.2795934E-02 4.3428607E-02 456 2 7.3292643E-02 2.9449234E-02 509 2 6.2227350E-02 5.0626360E-02 457 2 3.0571070E-02 6.2851891E-02 510 2 0.I672506 1.6204851E-02 458 2 0.1430519 1.2923073E-02 511 2 1.8789757E-02 5.9325770E-02 459 2 5.7888649E-02 4.0874809E-02 512 2 2.6002435E-02 4.6509504E-02 460 2 0.1176199 5.1488235E-02 513 2 8.3665326E-02 5.5244900E-02 461 2 8.8838212E-02 3.5273183E-02 514 2 3.0448386E-02 7.2145104E-02 462 2 8 3055459E-02 5.2958019E 02 515 2 0.2885319 6.7223296E-02 463 2 7.8486003 E-02 4.2060331 E-02 516 2 7.5610541E-02 5.3584695 E-02 464 2 3.7651348E-03 4.5594558E 02 517 2 0.1016252 5.0296757E-02 465 2 8.9207999E-02 4.9712803E 02 518 2 4.5112247E-04 3.4339830E-02 466 2 0.1019203 5.3399816E-02 519 2 3.3670895E-02 5.3941634E-02 467 2 3.8159367E 02 6.1574344E-02 520 2 5.0228938E-02 2.8962769E-02 1 468 2 7.2341422E-03 3.9367147E-02 521 2 6.2303629E-02 5.5208676E-02 l 469 2 2.1741793E-02 4.9255345E-02 522 2 1.5903739E-03 6.3049272E-02 470 2 1.7596968E-02 6.926082 t E-02 523 2 2.3061221E-02 3.7146755E-02 471 2 4.9762029E-02 5.0212156E-02 524 2 1.7828470E-02 2.2134250E-02 472 2 6.2078778E-02 4.3626074E-02 525 2 0.1489135 4.6703458E-02 473 2 0.1199143 6.5188862E-02 526 2 2.9991554E-02 5.4632392E-02 474 2 7.7847488E-02 4.6927504E-02 527 2 3.8592044E-02 6.0892493E-02 475 2 1.0528071E-02 3.3243977E-02 528 2 2.6665970E-03 4.0781397E-02 476 2 8.3635688E-02 6.8293311E-02 5'29 2 0.1594036 5.7811223E-02 477 2 0.2009909 5.2799009E 02 530 2 4.8654587E-03 6.7245990E-02 i NUREG/CR-6143 G-104 Vol. 2, Part 2
LOSP Frequency 531 2 4.ll76889E-02 2.3709267E-02 584 2 9.8734237E-02 5.2587286E-02 532 2 0.1111817 5.4197088E-02 585 2 1.3600629E-02 5.6890666E-02 533 2 3.2693163E 02 6.3513294E-02 586 2 5.8635902E 02 5.5508066E-02 534 2 2.7328093E-02 4.5014217E-02 587 2 0.1916036 6.0558066E-02 535 2 5.4314032E-02 6.1339408E-02 588 2 4.9487189E-03 3.9720256E-02 536 2 0.1534035 1.9215468E-02 589 2 1.2524434E-06 6.1670996E-02 537 2 0.1076253 2.8773729E-02 590 2 3.2651860E-02 6.2497389E-02 538 2 1.ll58386E-02 5.3947240E-02 591 2 0.1841026 2.5924018E-02 539 2 7.5296283E-02 5.1808033E-02 592 2 0.1599361 7.9104915E-02 540 2 9.0385396E-03 4.2649522E-02 593 2 5.8705285E-02 3.7483837E-02 541 2 1.8177083E-02 2.3263156E-02 594 2 6.6332571E-02 6.2288031E-02 542 2 3.4835618E-02 3.44%263E-02 595 2 2.1626830E-02 5.4086905E-02 543 2 0.2126295 7.1400881E-02 596 2 2.8318062E-02 5.9075210E-02 544 2 0.1055460 3.7581399E-02 597 2 1.58W639E-02 5.6085356E-02 545 2 1.6926570E-02 8.2580023E-02 598 2 3.4715347E-02 5.3803716E 02 546 2 9.7805411E-02 6.6657782E-02 599 2 4.7073562E-02 8.2605429E-02 547 2 2.4215424E-02 5.5337630E-02 600 2 5.9949227E-02 4.7632530E-02 548 2 4.6272218E-02 7.3172510E-02 601 2 4.5089148E-02 8.4848598E-02 549 2 0.1436211 2.3976738E-02 602 2 7.4199475E-02 6.5386884E-02 550 2 9.6115790E-02 5.8919404E-02 603 2 4.3561067E-02 5.8682919E-02 551 2 1.8233091E-02 5.0471243E-02 604 2 7.8390967E-03 4.0172376E-02 552 2 7.0725784E-02 4.9269639E-02 605 2 8.5252132E-03 5.8117419E-02 553 2 8.6573020E-02 3.0284656E-02 606 2 9.4841480E-02 5.9852250E-02 554 2 5.2638784E-02 7.0753917E-02 607 2 9.8654538E-02 3.0269235E-02 555 2 1.2816365E-02 5.8832102E-02 60S 2 8.2921065E-02 6.1462905E-02 556 2 9.5106354E-03 9.2986114E-02 609 2 0.1212057 4.6906881E-02 557 2 2.0517757E-02 9.1534806E-03 610 2 4.1389301E-02 7.1643874E-02 558 2 8.8717468E-02 5.4625418E-02 611 2 3.9176088E-02 5.8735572E-02 559 2 0.1110684 6.2296972E-02 612 2 3.6713161E-02 5.9419930E-02 560 2 0.1252603 3.7447959E-02 613 2 2.6123142E-02 4.9866855E-02 , 561 2 1.4984865E-02 4.1524138E-02 614 2 7.1415707E-02 9.7280517E-02 562 2 4.1367975E-03 7.9745278E-02 615 2 0.1111227 4.7417659E-02 563 2 0.1044355 4.48532%E-02 616 2 3.3226274E-02 0.1087197 564 2 0.1163967 4.7956627E-02 617 2 4.3823916E-02 5.3581931E-02 565 2 6.4864228E-03 5.0529066E-02 618 2 2.3118341E-02 2.6443675E-02 566 2 8.6171895E-02 5.2243385E-02 619 2 1.5971426E-02 5.5992521E-02 567 2 9.6399421E-03 3.5095360E-02 620 2 1.8822059E 02 6.8028539E-02 568 2 0.1216575 5.9582046E-03 621 2 5.8292266E-02 7.5867422E-02 569 2 7.5110182E 02 8.3018109E-02 622 2 5.7775807E-02 6.8557747E-02 570 2 9.4210796E-02 3.5506029E-02 623 2 3.5423137E-02 5.8446933E-02 571 2 0.1249922 2.4129305E-02 624 2 2.9857086E-02 3.0045392E-02 572 2 0.1011262 8.6357377E-02 625 2 0.1548729 7.3036246E-02 573 2 2.4293195E-02 1.3958868E-04 626 2 4.3557987E-02 5.5324331E 02 574 2 6.6678897E-03 6.0641464E-02 627 2 1.5834160E-02 3.4643687E-02 575 2 0.1111950 3.6001086E-02 628 2 3.0191801E-02 0.1435142 576 2 1.9772781E-02 3.8195383E-02 629 2 4.0227517E-02 4.2338185E-02 577 2 0.1155881 3.9210908E-02 630 2 6.4106800E-02 5.5072434E-02 578 2 0.1582730 6.9811329E-02 631 2 0.1264381 6.1384298E-02 579 2 0.1393309 4.6100881E-02 632 2 5.0514825E-03 8.6178847E-02 580 2 1.4094720E-02 3.6581177E-02 633 2 7.4786786E-03 4.3397933E-02 581 2 0.1499535 0.1384112 634 2 5.6379151E-02 3.2816466E-02 582 2 7.1544766E-02 3.3210576E-02 635 2 6.5043934E-02 2.6079575E-02 583 2 3.0904636E-02 5.6052897E-02 636 2 2.3314461E-02 3.8492594E-02 Vol. 2, Part 2 G 105 NUREG/CR-6143
LOSP Frequency 637 2 7.4765138E-02 3.5316885E-02 690 2 1.2667705E-02 3.7954487E-02 638 2 1.7438317E 02 6.0133357E-02 691 2 9.5690675E 03 4.6867296E-02 639 2 1.9293664E-02 4.6111993E 02 692 2 8.5062332E-02 6.7823358E-02 640 2 1.2643554E 02 2.4007510E-02 693 2 8.ll50882E-02 5.9913274E-02 641 2 6.2489253E-04 7.0830792E-02 694 2 1.4643470E-02 5.0341334E-02 642 2 7.2150782E-02 4.0100031E-02 695 2 8.3918739E-03 8.7849453E-02 643 2 8.0911592E-02 0.1194109 696 2 5.2297127E-02 3.3744439E-02 644 2 4.5478538E-02 7.1966670E-02 697 2 0.1712909 6.2485963E-02 645 2 0.1769705 6.1874941E-02 698 2 3.9250352E-03 6.0935359E-02 646 2 1.2616337E-02 2.7611544E-03 699 2 0.1462693 3.8154949E-02 647 2 7 2607398E-03 1.8355193E-02 700 2 6.3159265E-02 6.9870718E-02 648 2 4.3000471E-02 7.4872628E-02 701 2 6.3968100E-02 5.8013394E-02 649 2 0.2969601 1.4178558E 02 702 2 6.1579641E-02 4.4959161E-02 650 2 0.1011943 6.3337684E-02 703 2 3.1537369E-02 5.3400274E-02 651 2 4.0632688E-02 6.2715657E-02 704 2 0.1300344 3.3928584E-02 652 2 1.1991364E 02 5.5741306E-02 705 2 4.2458829E-02 5.9283480E-02 653 2 0.1659063 2.9904557E-02 706 2 6.8499178E-02 6.9322161E-02 654 2 6.7917205E-02 4.2753242E-02 707 2 5.0882958E-03 5.6380130E-02 655 2 2.9479271E-02 5.0045524E-02 708 2 0.1220675 7.6671772E-02 656 2 2.7579788E-02 4.5462053E-02 709 2 6.1601184E-02 5.8840957E-02 657 2 1.8036981E-04 8.4291220E-02 710 2 6.6456713E-02 5.7752959E-02 658 2 3.4363531E-02 5.3680379E-02 711 2 0.1217265 8.9464970E-02 659 2 7.1762465E-02 4.8111111E-02 712 2 4.7997069E-03 9.1979116E-02 660 2 0.1614968 8.2661159E-02 713 2 2 9600626E-02 4.9833305E-02 661 2 2.5125390E-02 5.7087846E 02 714 2 0.1141646 3.4966715E-02 662 2 3.1458316E-05 5.2861001E-02 715 2 7.1259312E-02 5.4746557E-02 663 2 0.1076581 6.9154672E-02 716 2 8.6525485E-02 5.2404400E-02 664 2 2.6002066E-02 8.3394058E-02 717 2 7.5258906E-03 0.1074915 665 2 0.1655387 5.6196619E-02 718 2 7.5813979E-02 7.3007323E-02 666 2 2.6791573E-02 6.6164300E-02 719 2 1.0426432E-04 3.1289287E-02 667 2 0.1573987 0.I171114 720 2 9.9009417E-02 8.5363977E-02 668 2 3 7749022E-02 5.5093467E 02 721 2 8.5491806E-02 6.5238811E-02 669 2 3.2987423E-02 8.3813868E-02 722 2 6.9037460E-02 5.1741201E-02 670 2 7.6349050E-02 4.0644743E-02 723 2 4.4828497E-02 5.3312019E-02 671 2 0.1368688 6.2713839E-02 724 2 7.9834806E-03 4.3321740E 02 672 2 1.0591272E-02 3.0946087E-02 725 2 4.4560567E-02 5.8733013E-02 673 2 5.0359242E-02 1.6257817E-02 726 2 6.5790229E-02 0.1134825 674 2 8.6674066E-03 6.6296309E-02 727 2 2.3019051E-02 5.6591086E-02 675 2 2.7813993E-02 8.4544651E-02 728 2 4.8554119E-02 5.5661380E-02 676 2 9.2147784E-06 4.8570462E-02 729 2 2.3537399E-02 4.0238518E-02 677 2 9.7445004E-02 6.9969364E-02 730 2 3.9333194E-02 5.5914365E-02 678 2 0.1148768 5.1222965E-02 731 2 6.6698194E 02 0.1130819 679 2 1.2202328E-02 9.6307933E-02 732 2 1.9953102E-02 8.5162811E-02 680 2 1.8492657E-03 6.1574437E-02 733 2 6.7289076E-03 4.5264572E-02 681 2 4.1577820E-02 5.2975034E-03 734 2 0.2049074 9.3866616E-02 682 2 0.1904121 6.1209939E-02 735 2 2.6612628E-02 6.4750165E-02 683 2 1.9257167E-02 5.7236783E-02 736 2 6.2301848E-02 6.2756054E-02 684 2 6.0050576E-03 4.2949833E-02 737 2 4.7661878E-02 8.2719140E-02 685 2 1.5237578E-02 6.6271603E-02 738 2 0.1032232 3.4457006E-02 686 2 0.1926419 6.1559569E-02 739 2 2.2303181E-02 4.6219658E-02 687 2 0.2087683 3.2510523E-02 740 2 2.3918238E-02 5.8558207E-02 688 2 0.1375539 7.4545696E-02 741 2 8.8102572E-02 4.6565115E-02 689 2 0.1049394 7.7320695E-02 742 2 1.0482088E-02 3.9032046E-02 NUREO/CR-6143 G-106 Vol. 2, Part 2
l ) LOSP Frequency 743 2 0.1262614 5.7312895E-02 796 2 7.3502332E-02 3.0958410E-02 744 2 5.1675425E 03 8.5691601E-02 797 2 1.98749NE-02 6.5839842E-02 745 2 0.2224558 6.0074564E-02 798 2 4.0966433E-02 6.1447807E-02 746 2 4.9047388E-02 8.3372809E-02 799 2 0.1398786 1.0918747E-02 747 2 4.1865766E-02 5.8311015E-02 800 2 0.1679944 6.4998902E-02 748 2 3.0313108E 02 5.0959568E-02 801 2 3.6314774E-02 6.1941538E-02 749 2 6.0838363E 03 5.0049245E-02 802 2 3.9298572E-02 2.6657805E-02 750 2 0.1005661 5.2472834E-02 803 2 0.1538339 5.7514656E-02 751 2 4.4937138E-02 5.8725663E 02 804 2 7.3337995E-02 4.7599960E 02 752 2 0.1633220 2.5648102E-02 805 2 3.2945636E 03 4.7168393E-02 753 2 4.3697253E-02 3.0470233E-02 806 2 7.4707083E-02 2.7054267E-02 754 2 3.1902997E-03 6.9020033E-02 807 2 3.7277136E-02 0.1055952 755 2 0.2287423 3.2850880E-02 808 2 2.3415873E 03 6.3766249E-02 756 2 3.0959342E-02 4.8091192E 02 809 2 0.1363300 5.8460943E-02 757 2 9.4964199E-02 5.4733302E-02 810 2 2.7190035E-02 4.6317127E-02 758 2 0.4126163 6.5297917E-02 811 2 6.1469404E-03 5.7112314E-02 759 2 6.2819786E-02 3.2475919E-02 812 2 4.8396634E 03 1.8904120E-02 760 2 4.520285] E-02 4.1657679E-02 813 2 6.1320782E-02 1.3836190E-02 761 2 1.2994861E-02 6.9093086E-02 814 2 5.1850434E-02 4.4858344E-02 762 2 5.1764749E-02 3.1948324E-02 815 2 2.9650316E-02 4.5002442E-02 763 2 0.1174101 3.8581774E-02 816 2 5.2909732E-02 5.2177414E-02 764 2 0.1159837 7.1235195E-02 817 2 7.2582185E-02 7.4897297E 02 765 2 0.1918874 3.1310797E-02 818 2 2.7631711E-02 6.0897086E-02 766 2 9.2250086E-02 2.7791988E 02 819 2 0.1479920 3.7642244E-02 767 2 0.1249470 6.7267433E-02 820 2 6.8155609E-02 0.1125266 768 2 9.5545508E-02 5.5780765E-02 821 2 4.8517105E-03 3.7218831E-02 769 2 1.9758463E-02 6.1134670E-02 822 2 1.0592137E-02 5.7463851E-02 770 2 6.9996879E-02 5.1670320E-02 823 2 8.4417984E-02 4.8830070E-02 771 2 8.20ll253E-02 3.5231430E-02 824 2 1.3834529E-02 5.6467827E-02 ' 772 2 9.7375i /7E-02 0.I671166 825 2 3.1368252E-02 5.5263419E-02 773 2 9.4023019E-02 3.9594948E-02 826 2 0.1733319 2.1836525E-02 774 2 0.1,476692 5.1349733E-02 827 2 0.1083883 7.8432508E-02 775 2 4.5043502E-02 5.9255589E-02 828 2 3.4713827E-02 5.4580510E-02 776 2 7.7810525E-03 3.5913724E-02 829 2 6.9029287E-02 4.9784124E-02 777 2 4.3228015E-02 5.2891221E-02 830 2 8.6368740E-02 0.1490737 778 2 4.5226362E-02 6.0764175E-02 831 2 1.0906375E-02 4.3313839E-02 779 2 1.ll31806E-02 4.4246893E42 832 2 2.3066474E-02 6.1758589E-02 780 2 7.1365029E-02 4.6598349E 02 833 2 0.1874645 0.1090954 781 2 0.1534233 3.6120445E-02 834 2 2.9084072E42 5.4830268E 02 782 2 4.5220446E-02 8.1419945E-02 835 2 3.2290604E-02 0.1488167 783 2 4.0321246E-02 4.4738114E-02 836 2 0.1759330 4.1155804E-02 j 784 2 9.2383265E-02 6.0023449E-02 837 2 1.4150621E-02 6.6617176E-02 785 2 0.1957802 3.8790107E-02 838 2 0.1159350 3.4868266E-02 786 2 6.2168173E-02 4.6073996E-02 839 2 4.2492867E-02 5.3134032E-02 787 2 0.1421046 4.9145039E-02 840 2 0.2267004 6.1173547E-02 788 2 4.6885949E-02 2.6521334E-02 841 2 0.1055374 4.8246101E-02 789 2 2.9114503E-02 5.4491013E-02 842 2 0.1955333 6.4037368E-02 790 2 9.4231784E-02 2.7507348E-02 843 2 2.6470978E-02 4.3714132E-02 791 2 3.5982575E 02 1.0827117E-02 844 2 6.8814188E-02 3.6620829E-02 792 2 0.2368337 6.6368714E-02 845 2 5.3744357E-02 5.1303342E-02 793 2 8.9359716E-02 4.3520104E-02 846 2 0.2325092 6.4085588E-02 794 2 1.8088779E-03 4.3661300E-02 847 2 6.0120583E-02 8.2462795E-02 795 2 0.1065253 6.1910994E-02 848 2 0.1314537 6.8409018E-02 Vol. 2, Part 2 G-107 NUREG/CR-6143
LOSP Frequency 849 2 0.1753536 7.1260124E-02 902 2 9.5153023E-03 0.1135739 850 2 7.0344500E-02 3.3605255E-02 903 2 1.3199417E-02 7.3137805E-02 851 2 1.9798214E-02 5.2160297E-02 904 2 0.1678364 1.6668446E-02 852 2 4.2904954E-02 8.3821729E-02 905 2 3.6986031E-02 6.3447930E-02 853 2 8.9058951E-02 4.7565345E-02 906 2 0.1057777 4.8246510E-02 854 2 0.1282351 5.6744356E-02 907 2 4.0126458E-04 5.1750962E 02 855 2 6.3481316E-02 9.3530454E-03 908 2 0.1166051 8.0631763E-02 856 2 5.8032546E-02 5.0135382E-02 909 2 9.2176422E 03 5.7477903E-02 857 2 4.0085889E-02 3.6050949E-02 910 2 0.1591447 4.3792546E-02 858 2 6.8856232E 02 5.4024547E-02 911 2 7.9803653E-02 4.5938723E-02 859 2 0.1148059 5.0873883 E-02 912 2 6.8583310E-02 4.3378543E-02 860 2 3.3868130E-02 6.0785957E-02 913 2 3.3945039E 02 3.2092944E-02 861 2 1.5916673E-02 6.5029919E-02 914 2 1.5667401E-02 7.0161469E-02 862 2 2.4237448E-02 5.5624705E-02 915 2 1.2216034E-02 3.7499879E-02 863 2 3.8375910E-02 5.2462641E-02 916 2 2.6205523E-02 0.1016790 864 2 7.1393445E-02 1.5578598E-02 917 2 0.1345783 5.8055867E-02 865 2 6.6492967E-02 1.9284455E-02 918 2 2.7402056E-02 2.1080213E-02 866 2 1.2682325E-02 5.7558499E-02 919 2 5.2395917E-02 0.1310989 867 2 2.5767982E-02 4.4060186E-02 920 2 9.7891323E-02 5.1882077E-02 868 2 1.9472765E-02 6.1348135E-02 921 2 8.9353189E-02 8.4825300E-02 869 2 1.3780744E-02 5.5703067E-04 922 2 2.7940512E-02 7.4167669E-02 870 2 7.0846647E-02 2.5572006E-02 923 2 5.0494056E-02 7.5886257E-02 871 2 3.2919362E-02 1.4207551E-02 924 2 9.0468293E-03 3.9250501 E-02 , 872 2 0.l M 1866 7.3884562E-02 925 2 0.2264951 0.1131693 ! 873 2 6.4161711E-04 3.8655475E-02 926 2 5.8889549E-02 6.8122149E-02 l 874 2 2.7,210578E-02 5.3686421E-02 927 2 1.8761925E-03 5.3185504E-02 875 2 5.0297618E-02 3.0133445 E-02 928 2 8.0460243E-02 6.2511340E-02 876 2 3.9070893E-02 3.9580315E-02 929 2 5.6212086E-02 4.4533499E-02 877 2 0.2120718 7.1436375E-02 930 2 0.1232555 4.9721505E-02 878 2 0.1207141 8.4866486E-02 931 2 1.7296594E-02 4.0684052E-02 879 2 7.0493244E-02 0.1654756 932 2 2.5122650E-02 5.3252496E-02 880 2 0.2736189 5.8602590E-02 933 2 2.4814460E-02 5.1550169E-02 881 2 0.1644907 3.9456370E-03 934 2 0.1282181 6.1518714E-02 882 2 0.1962140 5.2651335E-02 935 2 2.2284815E-02 7.6629288E-02 883 2 1.2658233E-03 5.1541779E-02 936 2 5.1063392E-02 9.5875099E 02 884 2 9.3008801E-03 5.8484331E-02 937 2 2.3033345E-02 7.2320491E 02 885 2 9.6362727E-03 1.4103325E-03 938 2 0.1255693 5.7018407E 02 886 2 0.1297920 5.3637575E-02 939 2 4.9152099E-02 4.2099785E-02 887 2 7.4851378E-03 5.6227304E-02 940 2 0.1012888 9.5059328E-02 888 2 7.1975842E-02 6.0246613E-02 941 2 3.2810923E-02 6.8614222E-02 889 2 3.9767893E-04 7.8546464E-02 942 2 5.5024467E-02 5.5538766E-02 890 2 0.1267434 4.3185066E-02 943 2 0.1023091 0.1114717 891 2 1.7169040E-02 3.8028657E-02 944 2 4.7409418E-03 6.2105045E-02 892 2 1.1717744E-02 6.0267188E-02 945 2 3.1449161E-02 7.2473414E-02 893 2 2.5022475E-03 7.1386263E-02 946 2 3.5321389E-03 0.1433671 894 2 2.8072709E-02 3.6606077E-02 947 2 2.1979650E-02 3.7572309E-02 l 895 2 8.4042564E-02 2.4940511E-02 948 2 3.2869723E-02 6.4480387E-02 l 896 2 3.6001012E-02 1.9995760E-02 949 2 1.6251069E-02 3.8868442E 02 l ! 897 2 4.6982206E-03 4.1722868E-02 950 2 9.9207006E-02 5.0651442E-02 I 898 2 1.1233456E-02 7.1409829E-02 951 2 0.1344099 ' 4.9624890E-02 899 2 4.3577466E-02 3.5525009E-02 952 2 1.4781847E-02 5.6478623E-02 900 2 7.6863907E-02 6.3962050E-02 953 2 7.0901610E-02 1.3658642E-02 901 2 4.2035021E-02 6.0748342E-02 954 2 1.0775675E-03 4.9721941E-02 NUREG/CR-6143 G-108 Vol. 2, Part 2
LOSP Frequency 935 2 2.9384814E-02 7.2166272E-02 956 2 9.1045044E-02 5.0976101E-02 957 2 2.7149079E-02 6.9073819E-02 958 2 0.1487750 4.9753133E-02 959 2 0.1281379 3.3494946E-02 960 2 0.2261254 4.8859332E-02
%1 2 7.0052288E-02 4.7748096E-02 %2 2 5.5682145E-02 5.8132105E-02 %3 2 0.1027336 4.9926355E-02 964 2 1.4832543E-02 5.5490620E 02 %5 2 5.5337563E-02 8.2520597E-02 966 2 6.2655270E-02 3.8574792E-02 %7 2 4.0548373E-02 6.3032411E-02 %8 2 6.2372845E-02 7.3105752E-02 %9 2 6.0694687E-02 6.0532637E-02 970 2 0.1315373 5.8275152E-02 971 2 5.6101017E-02 5.1635120E-02 972 2 0.1784956 4.4583969E-02 973 2 1.0766561E-02 6.2380012E-02 974 2 4.4256584E-03 3.2339543E-02 975 2 0.1317025 0.1138625 976 2 0.1184175 7.8903660E-02 977 2 8.3891869E-02 7.8740507E-02 978 2 1.3691519E-02 3.7798133E-02 979 2 0.1829110 4.55730llE-02 980 2 1.2218891E-02 3.7880022E-02 981 2 3.5861585E-02 5.3079080E-02 982 2 3.0800391E-03 5.3664945E-02 983 2 3.8509235E-02 4.5091420E-02 984 2 8.6480059E-02 3.8442094E-02 985 2 3.8517248E-02 6.3969307E-02 986 2 2.0938128E-02 6.4974770E-02 987 2 6.3549548E-02 8.5598998E-02 988 2 7.8335539E-02 3.6386952E-02 989 2 6.9398761E-02 5.0369952E-02 990 2 3.5620485E-02 5.3879078E-02 991 2 5.7140426E-03 7.6112233E-02 992 2 4.2732999E-02 4.7157414E-02 993 2 1.0141055E-02 5.9863053E-02 994 2 5.2287020E-02 5.2066594E-02 995 2 0.I110769 6. I749782 E-02 996 2 2.7594246E-02 5.7561927E-02 997 2 0.1713138 4.4933297E-02 998 2 2.2145273E-02 7.4739300E-02
, 999 2 0.1135392 3.7415762E-02 1000 2 4.1683346E-02 5.8121778E-02 Vol. 2, Part 2 G-109 NUREG/CR-6143
LOSP Frequency i l Attachment G-23 REMOVECOL2.FOR l { l ! l
\
I I I NUREG/CR-6143 G-il0 Vol. 2 Part 2
LOSP Frequency Character *25 remo CharacterHX)infile,outfile character *55 irse infile = 'ud4:[bdstapl]!hs.dat' outfile = 'ud4:[bdstapl]!hslosp.inp' open(unit - lo,name - infile, status = 'old') open(unit = 15,name = outfile, status = 'new') 25 rend (10,20,end=50)remo,inse 20 format (a,a) write (15,30)inse 30 format (s) goto 25 50 close(10) close(15) end Vol. 2, Part 2 G-111 NUREG/CR4143
LOSP Frequency 1 1 I l 1 l i I J Attachment G-24 LHSLOSP.INP f f l l l l i-NUREG/CR-6143 G-112 Vol. 2. Part 2
l 1 LOSP Frequency 9.5802836E-02 5.7157081E-02 6.3890698E-03 6.1642252E-02 0.1619431 3.6086690E42 5.0940670E-02 6.0416732E-02 1.1955368E-02 5.3150438E-02 6.5522656E-02 5.0114769E-02 3.7110481E-02 5.8251712E 02 2.0493850E-02 0.I857526 9.9551871E42 5.3492881E-02 0.3011881 5.3329077E-02 3.9378010E-02 3.7598554E42 3.2978956E-02 8.2634754E-02 6.8660229E-02 5.5287939E 02 3.5381936E 02 4.7152728E-02 5.2812852E-02 6.2103730E-02 4.1418765E42 5.6494150E 02 6.2365174E-02 7.5856574E-02 4.1240700E-02 5.0557747E-02 3.8164826E-03 6.1932772E-02 6.9060028E-02 8.9874759E-02 7.0628034E 02 3.3015352E-02 7.3756211E 02 9.4944753E42 4.4734307E-02 5.6779027E-02 3.21553252 03 5.7052251E-02 i 0.I116926 5.5104259E-02 4.3982375E 02 6.2561035E-02 0.2955990 0.1668376 ! 8.3901752E-03 5.9206437E 02 6.0694963E-02 3.8645752E-02 0.1707724 1.8475348E-02 2.1001803E-04 0.1903778 9.1746241E-02 0.1081921 5.5750683E-02 5.8619225E-02 0.1984308 3.8471486E 02 1.2195393E-02 0.1378729 3.3989530E-02 5.5715863E-02 6.1446220E-02 5.7531755E-02 9.7427778E-03 4.6029627E-02 9.6589506E-02 6.096M05E-02 1.3037866E 02 7.0953816E-02 1.%53393E-02 4.2656578E-02 4.4756867E-02 2.0783002E-02 8.6331956E-02 6.8710037E-02 3.I145809E-02 4.I980006E-02 7.3829912E 02 3.9646626E-02 3.7155967E-02 3.2672279E-02 7.1229465E-02 6.0362123E-02 0.1215877 1.5797980E-02 3.2555930E-02 4.4575006E-02 5.5966739E-02 0.1215986 8.4925257E-02 2.0765597E-02 4.5071386E-02 3.1056585E 02 2.9009812E-02 6.5682463E 02 5.1617451E-02 5.5218507E-02 6.3797474E-02 4.6071306E-02 7.5244442E-02 5.8911454E-02 1.6678156E-02 5.4130182E-02 4.3774538E 02 3.0516183E-02 7.8743502E-02 5.4237224E-02 1.7280921E-02 4.7160003E-02 O.1065058 7.9281092E 02 5.0527163E-02 6.1270196E-02 6.1498184E-02 5.8692340E-02 5.51023. lE-02 3.2996830E-02 3.1681322E-02 8.5060455E-02 0.1538038 2.3057584E-02 3.5599325E-02 4.8942689E-02 5.1817849E-02 5.0090570E-02 7.0079938E-02 5.9342016E-02 2.0490789E-03 .4.5054294E-02 5.0831504E 02 2.4951266E-02 4.6549104E-02 1.9712312E-02 2.5542006E-02 2.5336470E-02 0.1170508 6.8073846E-02 8.5495159E-02 1.8631760E 02 4.6561282E-02 7.3678486E-02 3.0360568E-02 4.9490560E-02 2.9121149E-02 6.0043842E-02 9.7525999E-02 7.1654484 E-02 3.7065927E-02 5.0325025E-02 5.2379847E-02 6.7772292E-02 3.698074SE-02 6.9754799E-03 8.4724374 E-02 3.4361262E-02 2.2424161E-02 5.7133570E-02 3.8461756E-02 2.1312614E-03 0.2172877 7.2943039E-02 1.4448942E-02 7.5433329E 02 0.1308402 4.2214524E-02 0.1707056 6.1654635E-02 0.1259440 4.9683046E-02 1.5121906E-02 6.1416168E-02 4.1157823E-02 6.0433898EA 2.1840738E-02 3.7463218E-02 0.1576 % 9 4.6902116E-02 4.6242714E-02 5.8522064E-02 4.6944050E-03 6.5001808E-02 1.1520608E-02 6.0953710E-02 7.8710178E-03 6.0102671E-02 6.5334700E-02 3.5716325E-02 0.1065259 9.95900llE-02 E.4139876E-02 7.9868220E 02 0.1371943 1.9875966E-02 [ 0.1838354 9.7384945E 02 9.9810176E-02 6.6642977E-02 1.6964525E-02 8.1631653E-02 2.3105722E-02 5.1488169E-02 5.6254819E-02 7.4072085E-02 0.1015151 2.9490849E-02 j 7.8000881 E-02 8.7991364E-02 4.5131359E-02 3.6564417E-02 1.8315334E-02 4.2935792E-02 l 8.4191918E-02 4.7253303E-02 0.1175776 6.0518596E-02 3.3113606E-02 3.9712951 E-02 , 3.0882679E-02 3.7661687E-02 2.3901181E-02 5.5216696E-02 0.1321511 6.5156333E-02 t 0.1168672 9.2032492E-02 6.8641901E-02 4.5617305E-02 4.2373762E-02 6.5489277E-02 ! 6.9784876E-03 2.3598091 G2 8.4 55734E-02 3.5917133E 02 7.2913952E-03 5.9004165E-02 ! 2.8681975E 02 3.968161 02 4.7624674E-02 5.0922580E-02 6.3795552E-02 4.7587328E-02 j 2.7508037E-02 8.6506 0 03 7.6687358E-02 4.7751363E-02 0.2103213 8.3966292E-02 l 5.7893977E-02 3.18288 */Jii-02 6.1508259E-03 6.2739216E-02 0.1109417 4.0622294E-02 8.7122709E-02 3.0945832E-02 6.9542497E-02 6.6954583E-02 0.1395433 5.4257885E-02 i 4.0420175E-02 0.1134561 5.0025929E42 7.1312711E-02 4.7899157E-02 0.1202568 6.7433029E-02 4.9484331E-02 7.6181762E-02 0.1293133 6.8555456E-03 6.0329355E-02 3.1565614E-02 5.5348329E-02 4.7242548E-02 2.8041681E-02 4.7816616E-03 3.7393130E-02 6.2981918E-02 4.5933411E-02 5.1474594E-02 4.7649670E-02 1.3575777E-02 2.2464391E-02 3.6439944E-02 6.5376133E-02 1.6576273E 02 8.9545082E-03 3.7566062E-02 1.2979862E-02 2.3256298E-0.1 6.1091572E-02 3.3260591E-02 4.7793541E-02 9.9475965E-02 3.7282106E-02 l 3.7388284E-02 6.3234374d-02 5.7211630E-02 4.9049694E-02 0.1179500 4.4079732E-02 4.9667925E-02 8.1571952E-02 9.6157566E-02 5.0513197E-02 0.1407464 8.6003169E-02 l Vol. 2, Part 2 G-113 NUREG/CR-6143
k LOSP Frequency 0.1213369 6.8935312E-02 5.3303089E-02 6.8604030E-02 0.1101487 5.3302426E42 4.5888089E 03 8.6619906E-02 5.0968453E 02 3.0148089E 02 1.0786332E-02 6.1759170E42 7.6253237E-03 7.2223626E-02 0.1519960 5.0956085E42 0.1050531 6.6191122E-02 0.1213599 5.0378244E-02 9.9529408E-02 5.1027179E-02 8.6179286E-02 3.974840SE-02 5.0322939E-02 5.5347841E-02 1.2661025E-02 3.2987788E42 7.1867579E-03 4.2479008E-02 5.3692952E-02 1.6964931E-02 1.1452804E-02 1.9742427E 02 9.5057264E-02 5.1139485E-02 6.8447582E-02 5.8529630E-02 5.9550323E-02 8.1923068E-02 0.1684978 2.7940258E-02 0.3917790 4.3206576E-02 8.4897578E-02 3.2943714E-02 1.2539796E-02 7.876050$ E-02 5.7127774E-02 1.4987160E-02 0.1265632 4.4650719E-02 6.4291013E-03 4.0083379E-02 8.3935164E-02 8.4336311E-02 0.1636941 6.5610617E-02 7.7832922E-02 5.9374005E-02 5.8236878E-02 5.1324982E-02 7.2806217E-02 7.1486212E-02 0.1206533 4.1501082E-02 2.7824761E-02 5.8796186E-02 9.768214SE-02 0,1179187 5.6917291E-02 4.7410175E-02 1.0342170E-02 6.6040970E-02 4.3897450E-02 5.7352368E-02 3.6365487E-02 5.2262317E-02 0.1130472 4.6403021E-02 5.3755235E-02 0.1008180 7.0993602E-03 4.4433460E-02 1.9324374E-03 2.1041799E-02 7.2366193E-02 0.1015658 4.3315183E-02 6.5824345E-02 2.ll23756E-02 5.4619823E-02 0.2446719 3.0301256E-02 7.434%79E-02 0.1840891 7.3582875 E-03 3.7066460E-02 8.7504514E-02 7.1135163E-02 9.5265292E-02 8.2059130E-02 3.1938533E-03 5.8557700E-02 6.1651595E-02 7.9552941E-02 0.1238719 3.2222025E-02 3.8392141E-03 5.4025233E-02 0.1204444 5.2140828E-02 9.5689654E-02 8.1871301E-02 0.1114586 4.5126867E-02 1.0141240E-02 4.9205273E-02 0.2603333 0.1265700 3.7242990E-02 6.1717805F-02 2.9848058E-02 5.8265250E-02 0.1145876 5.6587834E-02 1.9190241E-02 4.8077114E-02 9.4402153E-03 5.9602566E-02 6.2036499E-02 5.0692923E-02 2.3559626E-02 4.2224646E-02 4.3066703E-03 7.0935003E-02 0.1287113 5.4666784E-02 6.7579068E-02 5,4060549E-02 8.8652149E-03 8.9759074E42 7.6434948E-02 0.2836348 0.1495474 0.1292609 8.2147315E-02 3.4737453E-02 3.7384395E-02 5.1759280E-02 3.7243997E-02 5.6941222E-02 8.9766808E-02 2.2139974E-02 5.5710252E-02 7.9793416E-02 3.9188843E-03 4.8121687E-02 5.7522781E-02 8.4488504E-02 3.0785400E-02 6.5113649E-02 2.0487398E-02 6.9975689E-02 1.9196231E-02 7.9581648E-02 0.1471515 6.0857952E 02 O.1687348 5.1983319E-02 3.2749761E-02 6.2474120E-02 1.6241783E-02 5.7650033E-02 1.9494988E-02 3.7827380E-02 7.4022703E-02 4.1953418E-02 5.5924322E-02 3.0042961E-02 3.1080063E-02 2.2208920E-02 2.8199911E-02 5.1889852E-02 3.6231801E-02 4.6817876E-02 l 3.3260230E-02 3.4254942E-02 0.1044558 6.7030467E-02 5.1834852E-02 7.3877349E-02 0.1394177 6.1570350E 02 3.6798760E-02 8.6043261E-02 1.3616041E-02 4.0530287E42 4.6089880E-02 8.3428882E-02 2.8888844E-02 3.2008789E-02 0.1356705 3.7863705E-02 O.1716556 5.5070791E-02 0.1416059 4.2976875E-02 6.1036717E-02 5.6248203E-02 5.3486563E-02 7.9588860E-02 1.1433396E-02 4.2970411E-02 3.2080885E-02 8.4085375E-02 l 4.7258500E-02 0.1550756 8.4602527E-02 4.8343554E-02 6.3935861E-02 5.3747039E-02 3.394N16E-02 8.4298290E-02 0.1223382 4.7623150E-02 8.4782112E 03 5.1066682E42 2.1830970E-02 5.5529773E-02 5.3186379E-02 7.3586397E-02 0.1483902 3.3199754E-02 4.0602647E-03 5.6944489E-02 9.5278546E-03 7.3705859E-02 1.6334236E-02 4.4072583E-02 1.0020436E-02 5.4907784E-02 3.6003832E-02 6.3980505E-02 1.6464649E-02 6.5281264E-02 3.7182402E-02 4.9482226E-02 0.2368298 6.8291128E-02 3.3093113E-02 6.1957162E-02 4.2706481 E-03 0.1606795 9.8380804E-02 5.4853976E-02 0.1980580 6.3871555E-02 3.1993993E-02 5.3374309E-02 0.1627849 6.9135174E-02 3.2279663E-02 3.2386724E 02 7.7867016E-02 2.8862229E-02 4.3205872E-02 5.5737238E-02 7.2981618E-02 2.3%1281E-02 4.5282654E42 4.6392612E-02 7.7809721E-02 5.7787050E-02 1.0505857E-02 6.9583394E-02 2.3415735E-02 6.4310737E-02 9.2956319E-02 6.5993495E-02 2.7589556E-02 4.9572527E-02 0.2160491 5.5371974E-02 0.1799912 5.1761754E-02 9.8100808E 03 4.5669530E-02 l 6.4673787E-03 0.7566715 5.3744238E-02 0.1043923 0.1137452 6.7695037E-02 1.7433336E-02 5.5316355E 02 2.3056671E-02 5.9782274E-02 7.2744422E-02 8.2279146E-02 2.2904482E-05 4.6597488E-02 6.4727686E-02 7.6576352E-02 9.1899738E 02 5.7338905E-02 0.1147942 5.9636269E-02 0.1216711 5.7241727E-02 3.0302284E-02 7.9181217E-02 7.6124631E-02 7.3863171E-02 0.3209038 7.3334612E-02 4.4912171E-02 5.0130807E-02 NUREG/CR-6143 G-114 Vol. 2, Part 2
. . - . - - - = - . _- _
._. _ = ~ _ . - .
LOSP Frequency 1.7556440E-02 4.8635080E-02 5.7035097E-04 5.1698089E-02 6.0450430E-03 5.4368593E-02 i 7.8613654E-02 7.7345565E-02 4.2432569E-02 7.5730167E-02 1.9245146E-02 0.8440393 7.6832488E-02 6.1814152E-02 1.4777359E-02 4.6410918E-02 7. ll71016E-02 7.2131597E-02 5.3756524E-02 3.1926371E-02 3.2787994E-02 6.7062199E-02 6.7888290E-02 7.7404454E-02 0.1039997 5.9751723E-02 5.1232055E-02 5.1038437E-02 5.5506688E-02 7.5137384E-02 5.1588386E-02 6.9555439E-02 5.4714889E-03 4.4249024E-02 0.2476660 1.9120978E-02 4.1753639E-02 4.2831965E-02 2.0741522E-02 8.2121037E-02 2.9247994E-02 6.0947556E-02 9.4200537E-02 5.0937343E-02 8.3291810E-04 4.7168367E-02 6.4376746E-03 5.6334939E-02 0.2072446 5.0402451E-02 9.0837017E-02 3.1095194E-02 1.3259222E-02 3.8407531E-02 1.9067375E-02 0.1326806 2.3047213E-02 7.5219192E-02 9.5137425E-02 5.0707649E-02 5.2268062E-02 4.6196971E-02 4.1621886E-02 7.2013229E-02 1.6477322E-02 2.4710726E-02 > 9.3951240E-02 5.7576288E-02 3.9833665E-02 5.4039750E-02 4.0688049E-02 4.2610008E-02 l 2.5747674E-02 '4.7689557E-02 9.0728611E.02 5.1099844E-02 2.2278026E-02 5.1053967E-02 ; 9.1002814E-02 5.8826875E-02 0.1397989 8.3080105E-02 2.4768834E-03 6.1949339E 02 5.2193556E-02 7.2790295E-02 4.4670942E42 4.7020800E-02 1.9059179E-02 7.1737774E-02 1.3168592E-02 6.9407247E-02 0.1943297 4.5590665E-02 4.2819299E-02 5.2731704E-02 7.8425752E-03 5.0967094 E-02 3.5363667E-02 3.1711053E-02 9.5047787E42 8.5911974E-02 2.4083138E-02 0.1204861 6.8349316E-04 4.6826027E-02 2.2842348E-02 6.0070943E-02 2.9606896E-02 6.9861956E-02 9.1459142 1.5171967E-02 8.9984555 E-03 0.1145708 3.2791542E-03 8.4400952E-02 8.0266237E-02 6.2088851E-02 4.0717803E-02 4.3459535E-02 5.5754423E-02 7.'2532296E-02 1.9203138E-02 5.7292338E-02 1.8620146E-02 7.6692447E-02 l.9297315E-02 0.1260565 7.1140945E-02 4.8464339E-02 5.5759195E-03 1.6390927E-02 0.1221153 0.1444877 5.2328020E-02 6.8254374E-02 5.9370346E-02 4.4554576E-02 0.1836627 7.1748078E-02 7.3376082E-02 5.7114784E-02 1.4559478E-02 4.8129562E-02 6.3577600E-02 4.6294525E-02 2.1993279E-02 4.8157401E-02 ! 2.6211066E-02 1.8517802 E-02 1.2584946E-03 4.2093381E-02 3.4803309E-02 0.1230489 t 0.1165744 4.8370954E-02 7.7690028E-02 5.5468269E-02 1.5184088E-02 4.1216429E-02 0.1713544 5.8508251 E-02 ' 8.6576715E-03 4.8304219E-02 2.0581085E-02 4.8308022E-02 4.7787406E-02 5.6298438E-02 3.0842939E-02 5.0762452E-02 2.4160979E-02 6.1195992E-02 0.1166827 9.4757400E-02 [ 3.4306709E-02 7.1425423E-02 0.1186002 6.8436407E-02 0.1062214 4.4456623E-02
'3.0743775E-02 3.7325677E-02 6.6469684E-02 3.391.1091E-02 1.4152073E-02 3.3927958E-02 1.3435411E-02 5.4139994E-02 ?.7167817E 02 4.7778640E-02 7.3292643E 02 2.9449234E-02 3.2321534E-03 6.7153610E-02 0.1164728 4.5537926E-02 3.0571070E-02 6.2851891E-02 4.0109031E42 0.2683479 5.5276338E-02 8.6885706E-02 0.1430519 1.2923073E-02 7.1211591E-02 9.8831236E-02 0.1067105 6.1804399E-02 5.7888649E-02 4.0874809E-02 4.9363904E-02 4.6027701E-02 6.9141306E-02 5.4143526E-02 0.1176199 5.1488835E-02 3.0666770E-02 6.8053164E-02 8.5148111E-02 5.0867260E-02 8.8838212E-02 3.5273183E-02 5.1464181E-02 5.0975636E-02 1.0854620E-02 3.4957122E-02 8.3055459E-02 5.2958019E-02 2.9909359E-02 8. I957847E-02 7.3132701E-03 4. I457672E-02 7.8486003 E-02 4.2060331E-02 j 8.5642956E-02 6.1596613E-02 3.9495885E-02 6.5525882E-02 3.7651348E-03 4.5594558E-02 1 0.1428766 3.ll31679E-02 0.1621865 4.4940747E-03 8.9207999E-02 4.9712803E-02 6.3073608E-02 4.3255195E-02 2.7274314E-02 9.0562209E-02 0.1019203 5.3399816E-02 3.6340430E-03 2.4262222E-02 9.4924212E-02 6.5175451E-02 3.8159367E-02 6.1574344E-02 9.6433230E-02 6.5032646E-02 ?.8715859E-03 7.2900273E-02 7.2341422E-03 3.9367147E-02 0.1015370 5.0547209E-02 7.6369330E-02 0.1102054 ?.1741793E-02 4.9255345E-02 4.2306870E-02 3.0492617E-02 1.Il59037E-02 4.9953319E-02 1.7596968E-02 6.9260821E-02 8.6678125E-02 2.2774333E-02 1.6781913E-02 5.9157480E-02 4.9762029E-02 5.0212156E-02 8.0561943E-02 4.8459731E-02 9.4187953E-02 3.6562186E-02 6.2078778E-02 4.3626074E-02 3.5065666E-02 0.1246275 1.5712211E-02 7.7645145E-02 0.1199143 6.5188862E-02 5.6423653E-02 5.6726296E-02 0.1357202 4.8308227E-02 7.7847488E-02 4.6927504E-02 9.1383748E-02 0.1002052 9.6314792E-03 5.2776337E-02 1.052807] E-02 3.3243977E-02 ,
9.0465531E-02 6.9393113E-02 3.5887018E-02' 4.6999138E-02 8.3635688E-02 6.8293311E-02 i 8.2488284E-02 6.2411986E-02 6.3044518E-02 2.9852998E-02 0.2009909 5.2799009E-02 l W1. 2, Part 2 G-115 NUREG/CR-6143 l I I
LOSP Frequency 5.8667913E-02 1.1793434E-02 4.1176889E-02 2.3709267E-02 9.8734237E-02 5.2587286E 02 8.5019536E-02 5.3816400E-02 0.1111817 5.4197088E-02 1.3600629E-02 5.6890666E-02 3.2430448E 02 4.2968925E-02 3.2693163E-02 6.3513294E-02 5.8635902E-02 5.5508066E-02
.9151317E-02 7.0211180E-02 2.7328093E 02 4.5014217E 02 0.1916036 6.0558066E-02 2.0972826E-02 3.0125555E-02 7.4314032E-02 6.1339408E-02 4.9487189E-03 3.9720256E-02 9.0942435E 02 6.9475524E-02 0.1534035 1.9215468E-02 1.2524434E-06 6.1670996E-02 0.1594650 8.8435039E-02 0.1076253 2.3773729E-02 3.2651860E-02 6.2497389E-02 0.1471007 '3.7287861E-02 1.Il50386E-02 5.3947240E-02 0.1841026 2.5924018E-02 6.9947779E 02 6.6194192E-02 7.5293283E-02 5.1808033E-02 0.1599361 7.9104915E-02 2.9659139E-03 3.6363807E-02 9.038.'396E-03 4.2649522E-02 5.8705285E-02 3.7483837E-02 0.1435275 6.4530842E-02 1.8177083E-02 2.3263156E-02 6.6332571E-02 6.2288031E-02 0.1113859 7.8945436E-02 3.4835618E-02 3.4496263E-02 2.1626830E-02 5.4086905E.02 3.9282557E-02 4.3159917E 02 0.2126295 7.1400881E-02 2.8318052E-02 5.9075210E-02 6.1981261E-02 3.8630560E-02 0.1055460 3.7581399E-02 1.5888639E-02 5.6085356E-02 1.9839078E-02 7.6724023E-02 1.6926570E-02 3.2580023E-02 3.4715347E-02 5.3803716E-02 5.7827588E-02 5.1710501E-02 9.7805411E-02 6.6657782E-02 4.7073562E-02 8.2605429E-02 2.5132930E-02 3.8794026E-02 2.4215424E-02 5.5337630E-02 5.9949227E-02 4.7632530E-02
~.0411420E-02 5.6560256E-02 4.6272218E-02 7.3172510E-02 ?.5089148E-02 8.4848598E-02 0.1284811 8.2200252E-02 0.1436211 2.3976738E-02 7.4199475E-02 6.5386884E-02 8.3482713E-03 6.4073250E-02 9.6115790E-02 5.8919404E-02 4.3561067E-02 5.8682919E-02 0.1010389 7.6155193E-02 1.8233091E-02 5.0471243 E-02 7.8390967E-03 4.0172376E-02 1.0805682E-02 6.2696621E-02 7.0725784E-02 4.9269639E-02 8.5252132E-03 5.8117419E-02 6.1287235E-02 5.4863572E-02 8.6573020E-02 3.0284656E-02 9.4841480E-02 5.9852250E-02 4.9389787E-03 6.3365564E-02 5.2638784E-02 7.0753917E 02 9.8654538E-02 3.0269235E-02 5.8028206E-02 6.8783589E-02 1.2816365E-02 5.8832102E-02 8.2921065E-02 6.1462905E-02 1.0797053E-02 4.3770362E-02 9.5106354E-03 9.2986114E-02 0.1212057 4.6906881E-02 6.0769171E-02 5.1254261E-02 2.0517757E-02 9.1534806E-03 4.1389301E-02 7.1643874E-02 2.5214817E-02 4.5434184E-02 8.8717468E-02 5.4625418E-02 3.9176088E-02 5.8735572E-02 l 1.1230638E-02 6.0345143E-02 0.1110684 6.2296972E-02 3.6713161E-02 5.9419930E-02 l'
2.5707522E-02 4.3819964E-02 0.1252603 3.7447959E-02 2.6123142E-02 4.9866855E-02 2.2795934E-02 4.3428607E-02 1.4984865E-02 4.1524138E-02 7.1415707E-02 9.7280517E-02 6.2227350E-02 5.0626360E-02 4.1367975E-03 7.9745278E-02 0.1111227 4.7417659E-02 0.1672506 1.62(M851E-02 0.1044355 4.4853296E-02 3.3226274E-02 0.1087197 1.8789757E 02 5.9325770E-02 0.1163967 4.7956627E-02 4.3823916E-02 5.3581931E-02 2.6002435E-02 4.6509504E-02 6.4864228E-03 5.0529066E-02 2.3118341E-02 2.6443675E-02 8.3665326E 02 5.5244900E-02 8.6171895E-02 5.2243385E-02 1.5971426E-02 5.5992521E-02 3.0448386E-02 7.2145104E-02 9.6399421E-03 3.5095360E-02 1.8822059E-02 6.8028539E-02 0.2885319 6.7223296E-02 0.1216575 5.9582046E-03 5.8292266E-02 7.5867422E-02 7.5610541E-02 5.3584695E-02 7.5110182E-02 8.3018109E-02 5.7775807E-02 6.8557747E-02 , i 0.1016252 5.0296757E-02 9.4210796E-02 3.5506029E-02 3.5423137E-02 5.8446933E-02 ; 4.5112247E-04 3.4339830E-02 0.1249922 2.4129305E-02 2.9857086E-02 3.0045392E-02 ! 3.3670895E-02 5.3941634E-02 0.1011262 8.6357377E-02 0.1548729 7.3036246E-02 5.0228938E-02 2.8962769E-02 2.4293195E-02 1.3958868E 04 4.3557987E-02 5.5324331E-02 6.2303629E-02 5.5208676E-02 6.6678897E-03 6.0641464E-02 1.5834160E-02 3.4643687E-02 1.5903739E-03 6.3049272E-02 0.1111950 3.6001086E-02 3.0191801E-02 0.1435142 3 2.3061221E-02 3.7146755E-02 1.9772781E-02 3.8195383 E-02 4.0227517E-02 4.2338185E-02 l 1.7828470E-02 2.2134250E-02 0.1155881 3.9210908E-02 6.4106800E-02 5.5072434E-02 l 0.1489135 4.6703458E-02 0.1582730 6.9811329E-02 0.1264381 6.1384298E-02 2.9991554E-02 5.4632392E-02 0.1393309 4.6100881E-02 5.0514825E-03 8.6178847E-02 3.8592044E-02 6.0892493E 02 1.4094720E-02 3.6581177E-02 7.4786786E-03 4.3397933E-02 t 2.6665970E-03 4.0781397E-02 0.1499535 0.1384112 5.6379151E-02 3.2816466E-02 0.1594036 i l 5.7811223E-02 7.1544766E-02 3.3210576E-02 6.5043934E-02 2.6079575E-02 , l 4.8654587E-03 6.7245990E-02 3.0904636E 02 5.6052897E-02 2.3314461E-02 3.8492594E-02 i NUREGICR-6143 G 116 Vol. 2, Put 2
LOSP Frequency 7.4765138E-02 3.5316885E 02 1.2667705E-02 3.7954487E-02 0.1262614 5.7312895E-02 1.7438317E-02 6.0133357E-02 9.5690675E-03 4.6867296E-02 5.1675425E-03 8.5691601E-02 1.9293664E-02 4.6Ii 1993E-02 8.5062332E-02 6.7823358E-02 1.2224558 6.0074564E-02 1.2643554E-02 2.4007510E-02 8.ll50882E-02 5.9913274E-02 7.9047388E-02 8.3372809E-02 6.2489253E 04 7.0830792E-02 1.4643470E-02 5.0341334E-02 4.1865766E-02 5.8311015E-02 7.2150782E-02 4.0100031E-02 8.3918739E-03 8.7849453E-02 3.0313108E-02 5.0959568E-02 8.0911592E-02 0.1194109 5.2297127E 02 3.3744439E-02 6.0838363E-03 5.0049245E-02 4.5478538E-02 7.1966670E-02 0.1712909 6.2485963E-02 0.1005661 5.2472834E-02 0.1769705 6.1874941E-02 3.9250352E-03 6.0935359E-02 4.4937138E-02 5.8725663E-02 1.2616337E-02 2.7611544E-03 0.1462693 3.8154949E-02 0.1633220 2.5648102E-02 7.2607398E-03 1.8355193E-02 6.3159265E-02 6.9870718E 02 4.3697253E-02 3.0470233E-02 4.3000471E-02 7.4872628E 02 6.3968100E-02 5 8013394E-02 3.1902997E-03 6.9020033E-02 0.2 % 9601 1.4178558E-02 6.1579641E-02 4.4959161E-02 0.2287423 3.2850880E-02 0.1011943 6.3337684E-02 3.1537369E-02 5.3400274E-02 3.0959342E-02 4.8091192E-02 4.0632688E-02 6.2715657E-02 0.1300344 3.3928584E-02 9.4964199E-02 5.4733302E-02 1.1991364E-02 5.5741306E-02 4.2458829E-02 5.9283480E-02 0.4126163 6.5297917E-02 0.1659063 2.9904557E-02 6.8499178E-02 6.9322161E-02 6.2819786E-02 3.2475919E-02 6.7917205E-02 4.2753242E-02 5.0882958E-03 5.6380130E-02 4.5202851 E-02 4.1657679E-02 2.947927IE 02 5.0045524E-02 0.1220675 7.6671772E-02 1.2994861 E-02 6.9093086E-02 2.7579788E-02 4.5462053E-02 6.160ll84E-02 5.8840957E-02 5.1764749E-02 3.1948324E-02 1.8036981E 04 8.4291220E-02 6.6456713E-02 5.7752959E-02 0.1174101 3.8581774E-02 3.4363531E-02 5.3680379E-02 0.1217265 8.9464970E-02 0.1159837 7.1235195E-02 7.1762465E-02 4.811III1E-02 4.7997069E-03 9.1979116E-02 0.1918874 3.1310797E-02 0.1614968 8.2661159E-02 2.9600626E-02 4.9833305E-02 9.2250086E-02 2.7791988E-02 l 2.5125390E-02 5.7087846E-02 0.1141646 3.4966715E-02 0.1249470 6.7267433E-02 3.1458316E-05 5.2861001E-02 7.1259312E-02 5.4746557E-02 9.5545508E-02 5.5780765E-02 0.1076581 6.9154672E-02 8.6525485E-02 5.2404400E-02 1.9758463E-02 6.1134670E-02 2.6002066E-02 8.3394058E-02 7.5258906E-03 0.1074915 6.9996879E-02 5.1670320E-O'2 0.1655387 5.6196619E-02 7.5813979E-02 7.3007323E-02 8.20ll253E-02 3.5231430E-02 2.6791573E-02 6.6164300E-02 1.0426432E-04 3.1289287E-02 9.7375177E-02 0.1671166
?.1573987 0.I171114 9.9009417E-02 8.5363977E-02 9.4023019E-02 3.9594948E-02 3.7749022E-02 5.5093467E-02 8.5491806E-02 6.5238811E-02 0.1476692 5.1349733E-02 3.2987423E-02 8.3813868E-02 6.9037460E-02 5.1741201E-02 4.5043502E-02 5.9255589E-02 7.6349050E-02 4.0644743E-02 4.4828497E-02' 5.3312019E-02 7.7810525E-03 3.5913724E-02 0.1368688 6.2713839E-02 7.9834806E-03 4.3321740E-02 4.3228015E-02 5.2891221E-02 ,
1.0591272E-02 3.0946087E-02 4.4560567E-02 5.8733013E-02 4.5226362E-02 6.0764175E-02 5.0359242E-02 1.6257817E-02 6.5790224E-02 0.1134825 1.ll31806E-02 4.4246893E-02 8.6674066E-03 6.6296309E-02 2.3019051E-02 5.6591086E-02 7.1365029E-02 4.6598349E 02 2.7813993E-02 8.4544651E-02 4.8554119E-02 5.5661380E-02 0.1534233 3.6120445E-02 l 9.2147784E-06 4.8570462E-02 2.3537399E-02 4.0238518E-02 4.5220446E-02 8.1419945E-02 9.7445004E-02 6.9969364E-02 3.9333194E-02 5.5914365E-02 4.0321246E-02 4.4738114E-02 0.1148768 5.1222965E-02 6.6698194E-02 0.1130819 9.2383265E-02 6.0023449E-02 l 1.2202328E-02 9.6307933E-02 1.9953102E-02 8.5162811E-02 0.1957802 3.8790107E-02 1.8492657E-03 6.1574437E-02 ?.7289076E-03 4.5264572E-02 8.2168173E-02 4.6073996E-02 4.1577820E-02 5.2975034E-03 0.2049074 9.3866616E-02 0.1421046 4.9145039E-02 0.1904121 6.1209939E-02 2.6612628E-02 6.4750165E-02 4.6885949E-02 2.6521334E-02 1.9257167E-02 5.7236783E-02 6.2301848E-02 6.2756054E-02 2.9114503E-02 5.4491013E-02 6.0050576E-03 4.2949833E-02 4.7661878E-02 8.2719140E-02 9.4231784E-02 2.7507348E-02 1.5237578E-02 6.6271603E-02 0.1032232 3.4457006E-02 3.5982575E-02 1.0827117E-02 0.1926419 6.1559569E-02 2.230318 t E-02 4.6219658E-02 0.2368337 6.6368714E 02 0.2087683 3.2510523E-02 2.3918238E-02 5.8558207E-02 8.9359716E-02 4.3520104E-02 . 0.1375539 7.4545696E 02 8.8102572E-02 4.6565115E-02 1.8088779E-03 4.3661300E-02 I 0.1049394 7.7320695E-02 1.0482088E-02 3.9032046E-02 0.1065253 6.1910994E-02 ) l l Vol. 2, Part 2 G-il7 NUREG/CR-6143 j i i l 1
LOSP Frequency 7.3502332E-02 3.0958410E 02 0.1753536 7.1260124E-02 9.5153023E-03 0.1135739 1.9874904E-02 6.5839842E-02 7.0344500E-02 3.3605255E-02 1.3199417E-02 7.3137805E-02 4.0966433E-02 6.1447807E-02 1.9798214E-02 5.2160297E-02 0.1678364 1.6663446E-02 7.1398786 1.0918747E-02 4.2904954E-02 8.3821729E-02 3.698603 t E-02 6.3447930E-02 0.1679944 6.4998902E-02 8.9058951E-02 4.7565345E-02 0.1057777 4.8246510E-02 3.6314774E-02 6.1941538E-02 0.1282351 5.6744356E-02 4.0126458E-04 5.1750962E-02 3.9298572E-02 2.6657805E-02 6.3481316E-02 9.3530454E-03 0.1166051 8.0631763E-02 0.1538339 5.7514656E-02 5.8032546E-02 5.0135382E-02 9.2176422E-03 5.7477903E-02 7.3337995E-02 4.7599960E-02 4.0085889E-02 3.6050949E-02 0.1591447 4.3792546E-02 l 3.2945636E-03 4.7168393E-02 6 8856232E-02 5.4024547E-02 7.9803653E-02 4.5938723 E-02 7.4707083E42 2.7054267E-02 0.1148059 5.0873883E-02 6.8583310E-02 4.3378543E-02 3.7277136E-02 0.1055952 3.3868130E-02 6.0785957E-O'2 3.3945039E-02 3.2092944E-02 2.3415873E-03 6.3766249E-02 1.5916673E-02 6.5029919E-02 1.5667401E-02 7.0161469E-02 i 0.1363300 5.8460943E-02 2.4237448E-02 5.5624705E-02 1.2216034E-02 3.7499879E-02 l 2.7190035E-02 4.6317127E-02 3.8375910E-02 5.2462641E-02 2.6205523E-02 0.1016790 , i 7.1469404E-03 5.7112314E-02 7.1393445E-02 1.5578598E-02 0.1345783 5.8055867E-02 ) 4 F796634E-03 1.8904120E-02 ?.6492967E-02 1.9284455E-02 2.7402056E-02 2.1080213E-02 l 6.1320782E-02 1.3836190E 02 1.2682325E-02 5.7558499E-02 5.2395917E-02 0.1310989 ) 5.1850434E-02 4.4858344E-02 2.5767982E-02 4.4060186E-02 9.7891323E-02 5.1882077E-02 ; 2.9650316E-02 4.5002442E-02 1.9472765E-02 6.1348185E-02 8.9353189E-02 8.4825300E-02 l 5.2909732E-02 5.2177414E-02 1.3780744E-02 5.5703067E-04 2.7940512E-02 7.4167669E 02 7.2582185E-02 7.4897297E-02 7.0846647E-02 2.5572006E-02 5.0494056E-02 7.5886257E 02 l 2.7631711E-02 6.0897086E-02 3.2919362E-02 1.4207551E-02 9.0468293E-03 3.9250501E-02 0.1479920 3.7642244 E-02 0.1041866 7.3 884562E-02 0.2264951 0.I131693 6.8155609E-02 0.1125266 6.4161711E-04 3.8655475E-02 5.8889549E-02 6.8122149E-02 , I 4.8517105E-03 3.7218831E-02 2.7210578E-02 5.368642 t E-02 1.8761925E-03 5.3185504E-02 1.0592137E-02 5.7463851E-02 5.0297618E-02 3.0133445E-02 8.0460243E-02 6.2511340E-02 8.4417984E-02 4.8830070E-02 3.9070893E-02 3.9580315E-02 5.6212086E-02 4.4533499E-02 1.3834529E-02 5.6467827E-02 7.2120718 7.1436375E-02 0.1232555 4.9721505E-02 3.1368252E-02 5.5263419E-02 0.1207141 8.4866486E-02 L.7296594E-02 4.0684052E-02 0.1733319 2.1836525E-02 7.0493244 E-02 0.1654756 2.5122650E-02 5.3252496E-02 l 0.1083883 7.8432508E-02 0.2736189 5.8602590E-02 2.4814460E-02 5.1550169E-02 l 3.4713827E-02 5.4580510E-02 0.1644907 3.9456370E-03 0.1282181 6.1518714E-02 6.9029287E-02 4.9784124E-02 0.1962140 5.2651335E-02 2.2284815E-02 7.6629288E-02 ! 8.6368740E-02 0.1490737 1.2658233 E-03 5.1541779E-02 5.1063392E-02 9.5875099E-02 l 1.0906375E-02 4.3313839E-02 9.3008301 E-03 5.8484331 E-02 2.3033345 E-02 7.2320491E-02 l 2.3066474E-02 6.1758589E-02 9.6362727E-03 1.4103325E-03 0.1255693 5.7018407E-02 0.1874645 0.1090954 0.1297920 5.3637575E-02 4.9152099E-02 4.2099785E-02 l 2.9084072E-02 5.4830268E-02 7.4851378E-03 5.6227304E-02 0.1012888 9.5059328E-02 l 3.2290604E-02 0.1488167 7. I975842E-02 6.0246613E-02 3.2810923E-02 6.8614222E-02 1 0.1759330 4.1155804 E-02 3.9767893E-04 7.8546464E-02 5.5024467E-02 5.5538766E-02 1.4150621E-02 6.6617176E-02 0.1267434 4.3185066E-02 0.1023091 0.1114717 0.1159350 3.4868266E-02 1.7169040E-02 3.8028657E-02 4.7409418E-03 6.2105045E-02 4.2492867E-02 5.3134032E-02 1.1717744 E-02 6.0267188E-02 3.1449161E-02 7.2473414E-02 0.2267004 6. l l73547E-02 2.5022475E-03 7.1386263E-02 3.5321389E-03 0.1433671 0.1055374 4.8246101 E-02 2.8072709E-02 3.6606077E-02 2.1979650E-02 3.7572309E-02 0.1955333 6.4037368E-02 8.4042564E-02 2.494051 IE-02 3.2869723E-02 6.4480387E-02 2.6470978E-02 4.3714132E-02 3.6001012E-02 1.9995760E-02 1.6251069E-02 3.8868442E-02 6.8814188E-02 3.6620829E-02 4.6982206E-03 4.1722868E-02 9.9207006E-02 5.0651442E-02 5.3744357E-02 5.1303342E-02 1.1233456E-02 7.1409829E-02 0.1344099 4.9624890E-02 0.2325092 6.4085588E-02 4.3577466E-02 3.5525009E-02 1.4781847E-02 5.6478623E-02 6.0120583E-02 8.2462795E-02 7.6863907E-02 6.3962050E-02 7.0901610E-02 1.365864?E-02 0.1314537 6.8409018E-02 4.2035021E-02 6.0748342E-02 I m75675E-03 4.9721941 E-02 NUREG/CR-6143 G-118 Vol. 2, Part 2
l l LOSP Frequency 2.9384814E-02 7.2166272E42 9.1045044E-02 5.0976101E-02 2.7149079E-02 6.9073819E-02 0.1487750 4.9753133E-02 0.1281379 3.3494946E-02 0.2261254 4.8859332E-02 7.0052288E-02 4.7748096E 02 5.5682145E-02 5.8132105E-02 0.1027336 4.9926355E-02 1.4832543E-02 5.5490620E-02 5.5337563E-02 8.2520597E-02 6.2655270E-02 3.8574792E-02 , 4.0548373E-02 6.3032411E 02 l 6.2372845E-02 7.3105752E-02 6.0694687E 02 6.0532637E-02 0.1315373 5.8275152E-02 5.6101017E-02 5.1635120E-02 0.1784956 4.4583969E-02 1.0766561E-02 6.2380012E-02 4.4256584E-03 3.2339543E-02 0.1317025 0.1138625 0.I184175 7.8903660E-02 8.3891869E-02 7.8740507E-02 1.3691519E-02 3.7798133E-02 0.1829110 4.5573011E-02 1.2218891E-02 3.7880022E-02 3.5861585E-02 5.3079080E-02 3.0800391E-03 5.3664945 E-02 3.8509235E-02 4.5091420E-02 8.6480059E-02 3.8442094E-02 ' 3.8517248E42 6.3969307E-02 2.0938128E42 6.4974770E-02 6.3549548E-02 8.5598993E 02 7.8335539E 02 3.6386952E-02 6.9398761E-02 5.0369952E-02 3.5620485E-02 5.3879078E 02 5.7140426E-03 7.6112233E-02 4.2732999E-02 4.7157414E-02 1.0141055E-02 5.9863053E-02 5.2287020E-02 5.2066594E-02 0.Ii10769 6.1749782E-02 ! 2.7594246E-02 5.7561927E-02 0.1713138 4.4933297E-02 2.2145273E-02 7.4739300E-02 0.I135392 3.7415762E-02 4.1683346E-02 5.8121778E-02 l Vol. 2. Part 2 G-Il9 NUREG/CR-6143 l 1 w
LOSP Frequency 1 l Attachment G-25 LHSADDITION.FOR I
\
I l
)
1 1 1 NUREG/CR-6143 c.120 Vol. 2 Part 2
1 1 LOSP Frequency C C THIS PROGRAM READS IN TWO VALUES FROM LHSLOSP.INP, ADDS C THEM AND OUTPUTS TO LHSLOSP.DAT. C l PROGRAM ADDITION i DIMENSION X1(1000),X2(1000),Y(1000) ) OPEN(UNIT-62, FILE = 'LHSLOSP.INP', STATUS = 'OLD') OPEN(UNIT = 63, FILE = 'LHSLOSP.DAT', STATUS = 'NEW') NP = 1000 DO 5 K-1,NP READ (62,*)XI(K), X2(K) Y(K)=XI(K) + X2(K) 5 CONTINUE DO 15 K-1,NP WRITE (63,10)Y(K) 10 FORMAT (4X,F13.7) 15 CONTINUE END l l l 1 l I l Vol. 2, Part 2 G-121 NUREG/CR-6143
LOSP Frequency i l l l l I i l Attachment G-26 LHSLOSP.DATC 1 NUREGICR-6143 G-122 Vol. 2, Part 2
LOSP Frequency , 0.1529599 L 1680313 0.1980298 0.1902722 0.1219071 , 0.1113574 0.0651058 0.1156374 0.0912087 0.0811165 l 0.0953622 0.2062465 0.1530448 0.0798490 0.2029521 ! 0.3545172 0.0769766 0.1156137 0.1717381 0.1505566 0.1239482 0.0825347 0.1149166 0.1056708 0.0456488 0.0979129 0.1382218 0.0917984 0.0706579 0.0311952 O.0657493 0.1589348 0.1036434 0.1269772 0.1414734 ' 0.1687010 0.1015133 0.0602678 0.4349856 0.1178413 O.1667 % 9 0.1065434 0.4624366 0.0721149 0.1712139 , 0.0675966 0.0993407 0.1892478 0.1682715 0.2293047 I 0.1905878 0.1999383 0.1143899 0.1095619 0.1442924 l 0.2369023 0.1500683 0.0897054 0.0866209 0.2156008 ! 0.1189780 0.0557724 0.1575499 0.0763831 0.1012498 l 0.0623100 0.0655399 0.1594502 0.1545732 !' 0.0839917 0.1550420 0.0731258 0.1134765 0.0229742 0.1739320 O.0698282 0.1315916 0.1373857 0.0757436 0.2749732 1 0.0771309 0.1775653 0.1056909 0.0444247 0.1586397 0.0761280 0.0946923 0.1068360 0.0667516 0.1412045 0.1098688 0.1341559 0.0708083 0.0578644 0.1725852 0.0742907 0.1329807 0.0644409 0.1565855 0.0593465 0.1857869 0.1117974 0.1201905 0.0989608 0.0881133 0.0880991 0.1167418 0.1768614 0.0672674 0.0690428 . 0.0845420 0.1019084 0.1294219 U.0657843 0.0752417 0.0471034 0.0757828 0.0662614 0.1216396 0.0986243 - 0.2788083 0.1168848 i 0.0508785 0.1851247 0.1041269 O.1202398 0.0798511 0.0891650 0.1441852 0.1119068 r 0.1691805 0.0873910 0.1201521 0.0520406 0.1420113 0.0439562 0.1190856 0.0795577 0.0904631 0.0987779 , 0.0405930 0.2902308 0.0898823 0.2207181 0.0952239 > 0.1730547 0.2323602 0.1756271 0.0573224 0.1159761 ! 0.0765381 0.1015917 0.0593040 0.0532890 0.0800898 0.2045990 0.1047648 0.0696 % 2 0.0675152 0.1714863 0.0724743 0.0679737 0.1010510 0.2009880 0.1228420 0.2061159 0.1640081 0.1570703 0.1295188 0.0608976 0.2812203 0.1664532 0.0985962 0.2267264 0.1845828 0.0745939 0.1303269 0.1310059 0.1330754 0.0544038 0.1659922 0.0816958 0.0612511 0.2023341 0.1329461 0.1314452 0.1780962 0.0728266 0.1182387 0.169 % 13 0.0685444 0.0791179 0.1973074 0.0773607 0.1267728 0.2088997 0.1142592 0.1078630 0.0610048 0.0832337 0.0305766 0.1206729 0.0662956 0.0649282 0.0999843 0.0683636 0.0985473 0.1113829 0.0866646 0.3051209 0.0361587 0.1244387 0.2942876 0.1649501 0.1532348 0.0897228 0.0688900 0.1515640 0.0853683 0.2319201 O.1364971 0.1938012 0.1067292 0.0989431 0.1180685 0.1213386 0.1681560 0.0916753 0.1355 % 8 0.1538763 0.1169174 0.2054951 0.0671849 0.0877265 0.1589498 0.0869139 0.0752842 0.0421748 0.2714211 0.2317530 0.1089153 0.0991243 0.0360402 0.7631389 0.1581365 ! 0.0255303 0.0505459 0.0727497 0.0828389 0.1018161 0.0634172 0.0810541 0.1367581 0.0466204 0.1413040 ; 0.1062613 0.1620297 0,1744305 0.1789128 0.1006227 O.1312399 0.1466708 0.2267496 0.1499878 0.3942384 Vol. 2, Part 2 G-123 NUREG/CR-6143
LOSP Frequency O.I634511 0.0661915 0.0522684 0.0604136 0.0704613 0.0725455 0.1559592 0.1181627 0.8632845 0.1388359 0.1712442 0.1386466 0.0611883 0.1433026 0.0753994 0.1259277 0.0856829 0.0998502 0.1452927 0.0993625 0.0496658 0.1637514 0.1022705 O.I306441 0.0510984 0.1461 % 8 0.1211438 0.0497205 0.2667870 0.I604180 0,1964381 0.0845856 0.1028626 0.0901956 0.2479000 ; 0.0913003 0.1451379 0.0480013 0.0627726 0.1843886 l 0.0465125 0.2576471 0.1219322 0.0516668 0.1361420 l 0.1372069 0.1517480 0.0982664 0.1458451 0.0393297 l 0.1621544 0.0984650 0.1136351 0.0411881 0.2080583 0.1043275 0.1515275 0.0938734 0.0832981 0.1903313 0.0886278 0.0734372 0.1418285 0.0733320 0.0824425 0.0515328 0.1498297 0.2228790 0.0644262 0.1006118 0.1091395 0.1249839 0.0916417 0.0907970 0.0965631 0.2584388 0.0825758 0.2399204 0.0955510 0.1095381 0.1773244 0.0588097 0.0670747 0.1809598 0.0639270 0.1560939 0.1445692 0.0475095 0.0829133 0.0969717 0.1775610 0.0994688 0.1610862 0.1235693 0.2106814 0.3869033 0.0876801 0.1423551 0.0841773 0.0724215 O.1711754 0.1282867 0.0764955 0.0953126 0.1771941 0.I127294 0,1453538 0.I196053 0.0219668 0.0735023 0.I833781 0.2666030 0.1205824 0.1039249 0.I161508 0.3600698 0.2554108 0.1304909 0.0626890 0.0683045 0.0891437 0.0447289 0.1098721 0.0701507 0.1268118 l 0.1355037 0.1649453 0.0433519 0.1578522 0.0545674 0.0958991 0.1331583 0.0564005 0.2298626 0.1120234 0.2080095 0.0569619 0.0688891 0.1040858 0.0706490 0.0738918 0.0816054 0.0853570 0.2114401 0.0715758 0.0859673 0.1057321 0.1870366 0.1506780 0.0695275 0.0830497 0.1180695 0.1003828 0.0480800 0.0662245 0.1257122 0.0725754 0.0849465 0.1027419 0.1128537 0.0541463 0.0703858 0.1620107 0.0934230 0.1834555 0.1735342 0.3084569 0.1421620 0.1559750 0.0781155 O.I172849 0.1700428 0.1685149 0.0987635 0.0725119 0.1161663 0.0953916 0.1232848 0.1691087 0.1389102 0.1176829 0.1067199 0.1360154 0.1241114 0.1025935 0.0595449 0.1024398 0.0458117 0.1360135 0.3557552 0.I815900 0.I118672 0.0487709 0.1205463 0.1291952 0.0604068 0.1472396 0.1050218 0.0493597 0.1519220 0.0817459 0.1740083 0.1666806 0.1389208 0.0347910 0.0950503 0.1113288 0.1178365 0.1553201 0.0876125 0.2619295 0.0278963 0.1600997 0.0997337 0.0791917 0.0646664 0.I614659 0.0807719 0.0466013 0.I175123 0.0969429 0.1520842 0.I865747 0.0709971 0.0646396 0.0800892 0.0727995 0.0611124 0.0868578 0.0602080 0.0771621 0.1094525 0.0759394 0.0999742 0.0399627 0.0554796 0.1290217 0.I307501 0.1057049 0.I956170 0.I814402 0.1596932 0.0933574 0.I851032 0.0846239 0.1550236 0.I131499 0.1S40284 0.1247750 0.0994845 0.1492386 0.1915890 0.0624078 0.0437720 0.0434480 0.1094835 0.1598586 0.0828862 0.1519290 0.2172148 l 0.095N30 0.1449003 0.0928975 0.2537899 t 0.0721115 i NUREG/CR 6143 G-124 Vol. 2, Part 2 l I l
i LOSP Frequency i 0.0648862 0.1513215 0.1100820 0.0506222 0.1835743 0.1653788 0.0704913 0.0775717 0.0564364 0.0908591 0.0962065 0.1141440 0.0654057 0.1528857 0.2825304 0.0723423 0.2521617 0.0366511 0.1410642 0.1324202 l 0.I156534 0.0446690 0.0714557 0.0649848 0.1001768 0.1726190 0.0616722 0.I122508 0.0962413 0.0812727 0.1363990 0.0951492 0.2003225 0.0860416 0.0561331 ' O.0651056 0.2100266 0.1174452 0.2337769 0.1530389 0.1271043 0.2390410 0.2388454 0.0648604 0.1036628 0.0516881 0.0961891 0.0153775 0.1844243 0.1889701 0.0414402 0.1286206 0.0256159 0.1330300 0.0741675 0.0693319 0.0757137 0.1178731 0.1219815 0.0722103 . 0.2840304 0.0873933 0.3111386 0.1065388 0.2615932 l 0.1431274 0.0719740 0.1645320 0.0849376 0.0790505 i 0.0995066 0.0885191 0.1033483 0.1639630 0.14 % 975 0.1644632 0.12 % 790 0.0677327 0.1017423 0.4779142 0.0795531 0.1075818 0.1958109 0.1378213 0.0952957 0.1194447 0.1299378 0.!!06704 0.0614684 0.0868605 ! 0.1675978 0.1395864 0.0795248 0.1987393 0.0820879 O.1550352 0.1022440 0.0730418 0.1204421 0.0837131 l 0.0687043 0.0480115 0.0844716 0.1242097 0.1559919 ; 0.I199954 0.0666426 0.0880439 0.2111915 0.I872189 O.1I68577 0.1546937 0.1198736 0.0967788 0.2231982 j 0.1233927 0.1289238 0.2441580 0.0794339 0.1200421 O.0716485 0.1443840 0.0822132 0.1491313 0.1922144 ! 0.1024968 0.1681126 0.0528925 0.1260059 0.1513263 l 0.02 % 712 0.1130332 0.1768128 0.1389299 0.0808931 0.I433429 0.0979II7 0.1093961 0.I150174 0.1216672 0.1733654 0.0961331 0.2217353 0.1488213 0.1172427 0.1627083 0.0759900 0.0929559 0.0313936 0.2644918 0.0565090 0.1686 % 2 0.2745101 0.1843734 0.1336180 0.0838821 0.1585404 0.0928425 0.1507306 0.1990189 0.1492888 0.1419460 0.1168013 0.1207787 0.1042991 0.1643533 0.0974059 0.1169938 0.0981405 0.0436948 0.0570155 0.0495620 0.1995827 0.0513052 0.0961192 0.1384153 0.071 % 40 0.0415374 0.1032936 0.1059905 0.0447353 0.0868506 0.0666171 0.1792727 0.0553787 0.1276157 0.1341597 0.0749637 0.0796101 0.1179634 l 0.1581283 0.1263335 0.1123586 0.1042155 0.1895437 i 0.1297168 0.0938701 0.0485797 0.0637759 0.1266404 ) 0.1491215 0.0599025 0.1674144 0.0952476 0.0850594 ! 0.1874836 0.2279091 0.1660998 0.1797801 0.1524067 i 0.0244328 0.0988823 0.1085103 0.1051159 0.2345703 0.0673094 0.0504778 0.0634237 0.0519935 0.1082422 0.1471 % 1 0.1737060 0.0468753 0.2987740 0.19124 % 0.0579682 0.0825657 0.2516221 0.0913628 0.0734073 0.1547990 0.I191792 0.0764939 0.1250579 0.0836055 0.2280843 0.1878224 0.0489549 0.1303810 0.1217391 0.1854318 0.0912303 0.0815092 0.1376802 0.0468097 0.0506759 0.0508766 0.2542015 0.0685228 0.3032024 0.2883647 0.0891956 0.2412788 0.0824764 0.1328798 0.1047553 0.0911235 0.2120996 0.1346677 0.0454702 0.0869575 0.0618071 0.I822601 0.0495141 0.I684363 Vol. 2, Part 2 G-125 NUREGICR-6143 o ._. ,_
LOSP Frequency 0.1044607 0.2466137 0.1230892 0.1015511 0.0857147 0.1039498 0.0863372 0.1420211 0.1024142 0.0719585 0.I845049 0.0962229 0.1507974 0.1267267 0.1004340 0.1985281 0.2329933 0.1366243 0.1540242 0.1616329 0.0982563 0.1849795 0.0521522 0.2749847 0.0659564 0.0728344 0.1972369 0.1178004 0.2113485 0.1081679 0.0666955 0.1138142 0.1209380 0.0761368 0.2029372 0.1526600 l 0.0504630 0.1228808 0.1257424 0.0703232 0.1017613 0.1656798 0.1119619 0.1378582 0.1428723 0.0946541 0.0660380 0.1012301 0.0661078 0.0809466 0.0858289 0.1035808 l 0.1947909 0.0798622 0.0497159 0.1354786 l 0.0735072 0.0908386 0.1278845 0.1212273 l 0.0632593 0.0869720 0.1926342 0.1898125 0.0237438 0.0857774 0.0484823 0.1077361 l 0.0751570 0.0702408 0.1834948 0.2230796 0.0967088 0.0698282 0.1497734 0.0731466 0.0746528 0.0808209 0.1741785 0.0367652 0.1050871 0.0143378 0.1021082 0.2455550 l 0.1474795 0.0964187 0.1263803 0.1973212 0.0885288 0.0471269 0.0482973 0.1626324 0.1856342 0.1780712 0.3396644 0.0514897 0.1806822 0.0392971 0.1270117 0.2284840 0.0420705 0.0808970 0.0550617 0.0500989 0.0680560 0.0804311 0.1429716 0.0889407 0.1332481 0.0786512 0.1007456 0.0567450 0.0703024 0.2835082 0.1729770 0.0836007 0.0866317 0.2055806 0.0579806 0.1249222 0.1951684 0.2359689 0.0783751 0.1024866 , 0.1868208 0.3322215 0.0763646 0.0859129 0.0892943 0.1684363 0.1897368 0.1491486 0.I188134 0.2488653 0.0989141 0.I147225 0.2354424 0.0528076 0.1469385 0.I197687 0.0542202 0.0677852 0.0953538 0.0894996 0.0848251 0.0110466 0.I825877 0.0818263 0.2 % 5599 0.1834296 0.0912519 0.0898904 0.9839143 0.0637124 0.1963481 0.0700041 0.1811073 0.1322225 0.1014251 0.1043536 0.2170888 0.0789441 0.I105632 0.1728267 0.0807678 0.1699285 0.2137808 0.0851562 0.1508033 0.0551977 0.0668460 0.2162471 0.0956269 0.0719849 0.1039226 0.0968846 0.2878740 0.0738885 0.1468992 0.1509550 0.1537835 0.0646788 0.0595520 0.0998051 0.2595707 0.1089831 0.0973501 0.0701851 0.0559968 0.0551195 O.1054350 0.0464211 0.1498584 0.1050477 0.0826433 0.I840348 0.2 % 5948 0.0791025 0.0712605 l 0.1425834 0.1408260 0.0845603 0.1998627 0.1027834 0.0507995 NUREG/CR-6143 G-126 Vol. 2, Part 2
LOSP Frequency Attachment G27 REMOVECOL.FOR Vol. 2 Part 2 G-127 NUREG/CR-6143
LOSP Frequency Character *64 remo Character *60 infile,outfile character *16 inse infile = 'ud4:[bdstapl]!hslosp.inp' outfile = 'ud4:[bdstapl]pegwlosp.dat' open(unit = lO,name = inflie, status = 'old') open(unit = 15,name- outfile, status = 'new') 25 read (10,20,end = f Wnse,remo 20 format (a,a) write (15,30)inse 30 format (s) goto 25 50 close(10 close(15 end l l 1 l l NUREG/CR-6143 G-128 Vol. 2, Part 2
1 LOSP Frequency b Attachment G-28 PCGWLOSP.DAT l l l l l l Vol. 2. Part 2 G-129 NUREG/CR-6143
LOSP Frequency 9.5802836E-02 6.3890698E-03 0.1619431 0.1213369 5.3303089E-02 i 5.0940670E-02 1.1955368E-02 6.5522656E-02 4.5888089E-03 5.0968453E 02 3.7110481E-02 2.0493850E-02 9.9551871E-02 7.6253237E-03 0.1519960 0.3011881 3.9378010E-02 3.2978956E-02 0.1213599 9.9529408E-02
. 6.8660229E-02 3.5381936E-02 5.2812852E-02 5.0322939E-02 1.2661025E 02 4.1418765E-02 6.2365174E-02 4.1240700E-02 5.3692952E-02 1.1452804E-02 3.8164826E-03 6.9060028E-02 7.0628084E-02 6.8447582E-02 5.9550323E-02 7.3756211E-02 4.4734307E 02 3.2155325E-03 0.3917790 8.4897578E-02 0.1116926 4.3982375E-02 0.2955990 5.7127774E-02 0.1265632 8.3901752E-03 6.0694963E-02 0.1707724 8.3935164E-02 0.1636941 2.1001803E-04 9.1746241E-02 5.5750683E-02 5.C236878E-02 7.2806217E-02 0.1984308 1.2195393E-02 3.3989530E-02 2.7824761E 02 9.7682148E-02 6.1446220E-02 9.7427778E-03 9.6589506E-02 1.0342170E-02 4.3897450E-02 1.3037866E-02 1.9653393E-02 4.4756867E-02 0.1130472 5.3755235E-02 .
0.6331956E-02 3.1145809E-02 7.3829912E-02 1.9324374E 03 7.2366193E-02 3.7155967E-02 7.1229465E-02 0.1215877 2.1123756E-02 0.2446719 3.2555930E-02 5.5966739E-02 8.4925257E-02 7.3582875E-03 8.7504514E-02 4.5071386E-02 2.9009812E-02 5.1617451E 02 8.1938533E-03 6.1651595E-02 6.3797474E-02 7.5244442E-02 1.6678156E-02 3.8392141E-03 0.1204444 4.3774538E-02 7.8743502E-02 1.7280921 E-02 0.1114586 1.0141240E-02 0.1065058 5.0527163E-02 6.1498184E-02 3.7242990E-02 2.9848058E-02 5.510231 I E-02 3.1681322E-02 0.1538038 1.9190241E-02 9.4402153E-03 3.5599325E-02 5.1817849E-02 7.0079938E 02 2.3559626E-02 4.3066703E-03 2.0490789E-03 5.0831504E-02 4.6549104E-02 6.7579068E-02 8.8652149E-03 2.5542006E-02 0.1170508 8.5495159E-02 0.1495474 8.2147315E-02 4.6561282E-02 3.0360568E-02 2.9121149E-02 8.7243997E-02 8.9766808E-02 9.7525999E-02 3.7065927E-02 5.2379847E-02 3.9188843E-03 5.7522781E-02 3.6980748E-02 8.4724374E-02 2.2424161E-02 2.0487398E-02 1.9196231E-02 3.8461756E-02 0.2172877 1.4448942E-02 0.1687348 3.2749761E-02 0.1308402 0.1707056 0.1259440 1.9494988E-02 7.4022703E-02 1.5121906E-02 4. ll57823 E-02 2.1840738E-02 3.1080063 E-02 2.8199911 E-02 0.1576969 4.6242714E-02 4.6944050E-03 3.3260230E-02 0.1044558 1.1520608E-02 7.8710178E-03 6.5334700E-02 0.1394177 3.6798760E-02 0.1065259 8.4139876E-02 0.1371043 4.6089880E-02 2.8888844E-02 0.1838354 9.9810176E-02 1.6964525E-02 0.1716556 0.1416059 2.3105722E-02 5.6254819E-02 0.1015151 5.3486563E-02 1.1433396E 02 7.8000881E-02 4.5131359E-02 1.8315334E-02 4.7258500E-02 8.4602527E-02 0.4191918E-02 0.1175776 3.3113606E-02 3.3940416E-02 0.1223382 3.0882679E-02 2.3901181E-02 0.1321511 2.1830970E-02 5.3186379E-02 0.1168672 6.8641901 E-02 4.2373762E-02 4.0602647E-03 9.5278546E-03 6.9784876E-03 8.4755734E-02 7.2913952E-03 1.0020436E-02 3.6003832E-02 2.8681975E-02 4.7624674E-02 6.3795552E-02 3.7182402E-02 0.2368298 2.7508037E-02 7.6687358E-02 0.2103213 4.2706481 E-03 9.8380804E-02 5.7893977E-02 6.1508259E-03 0.1109417 3.1993993E-02 0.1627849 8.7122709E-02 6.9542497E-02 0.1395433 7.7867016E-02 4.3205872E-02 4.0420175E-02 5.0025929E-02 4.7899157E-02 4.5282654E-02 7.7809721E-02 l 6.7433029E-02 7.6181762E-02 6.8555456E-03 2.3415735E 02 9.2956319E-02 3.1565614E-02 4.7242548E-02 4.7816616E-03 0.2160491 0.1799912 6.2981918E-02 5.1474594E-02 1.3575777E-02 6.4673787E-03 5.3744238E-02 3.6439944E-02 1.6576273E-02 3.7566062E-02 1.7433336E-02 2.3056671E 02 2.3256298E-03 3.3260591E-02 9.9475965E-02 2.2904482E-05 6.4727686E-02 3.7388284E-02 5.7211630E-02 0.1179500 0.1147942 0.1216711 4.9667925E-02 9.6157566E-02 0.1407464 7.6124631E-02 0.3209038 NUREG/CR-6143 G-130 Vol. 2 Part 2
i l l LOSP Frequency 0.1101487 1.7556440E-02 5.7035097E 04 6.0450430E-03 5.8667913E-02 1.0786332E-02 7.8613654E-02 4.2432569E-02 1.9245146E-02 8.5019536E-02 0.1050531 7.6832488E-02 1.4777359E-02 7.1171016E-02 3.2430448E-02 8.6179286E-02 5.3756524E-02 3.2787994E-02 6.7888290E-02 2.9151317E42 7.1867579E-03 0.1039997 5.1232055E-02 5.5506688E 02 2.0972826E-02 9.5057264E-02 5.1588386E-02 5.4714889E-03 0.2476660 9.0942435E-02 0.1684978 4.1753639E-02 2.0141522E-02 2.9247994E-02 0.1594650 1.25397%E-02 9.4200537E-02 8.3291810E-04 6.4376746E-03 0.1471007 6.4291013E-03 0.2072446 9.0837017E-02 1.3259222E-02 6.9947779E-02 7.7832922E-02 1.9067375E-02 2.3047213E-02 9.5137425E-02 2.9659139E-03 0.1206533 5.2268062E-02 4.1621886E-02 1.6477322E-02 0.1435275 5.6917291E-02 9.3951240E-02 3.9833665E-02 4.0688049E-02 0.1113859 3.6365487E-02 2.5747674E-02 9.0728611E-02 2.2278026E-02 3.9282557E-02 7.0993602E-03 9.1002814E-02 0.1397989 2.4768834E-03 6.1981261E42 i 4.3315183E-02 5.2193556E-02 4.4620942E-02 1.9059179E-02 1.9839078E-02 l 7.4349679E-02 1.3168592E-02 0.1943297 4.2819299E-02 5.7827588E-02 9.5265292E-02 7.8425752E-03 3.5363667E-02 9.5047787E-02 2.5132930E-02 0.1238719 2.4083138E-02 6.8349316E-04 2.2842348E-02 4.0411420E-02 9.5689654E-02 2.9606896E-02 0.1459142 8.9984555E-03 0.1284811 0.2603333 3.2791542E-03 8.0266237E-02 4.0717803E-02 8.3482713E-03 0.1145876 5.5754423E-02 1.9203138E-02 1.8620146E-02 0.1010389 6.2036499E-02 1.9297315E-02 7. ll40945E-02 5.5759195E-03 1.0805682E-02 0.1287113 0.1221153 5.2328020E-02 5.9370346E-02 6.1287235E 02 7.6434948E-02 0.1836627 7.3376082E-02 1.4559478E-02 4.9389787E-03 3.7384395E-02 2.6211066E-02 6.3577600E-02 2.1993279E-02 5.8028206E-02 5.5710252E-02 0.1165744 1.2584946E-03 3.4803309E-02 1.0797053E-02 3.0785400E-02 7.7690028E-02 1.5184088E-02 0.1713544 6.0769171E-02 0.I471515 8.6576715E-03 2.0581085E-02 4.7787406E-02 2.5214817E-02 1.6241783E-02 3.0842939E-02 2.4160979E-02 0.1166827 1.1230638E-02 5.5924322E-02 3.4306709E-02 0.!!86002 0.1062214 2.5707522E-02 3.6231801E-02 8.0743775E-02 6.6469684E-02 1.4152073E-02 2.2795934E-02 5.1834b52E-02 1.8435411E-02 3.7167817E-02 7.3292643E-02 6.2227350E-02 1.3616041E-02 3.2321534E-03 0.I164728 3.05 1070E-02 0.I672506 0.1356705 4.0109031E-02 5.5276338E-02 0.1430519 1.8789757E-02 6.1036717E-02 7.1211591E-02 0.1067105 5.7888649E-02 2.6002435E-02 3.2080885E-02 4.9363904E 02 6.9141306E-02 0.1176199 8.3665326E-02 6.3935861E-02 3.8666770E-02 8.5148111E-02 8.8838212E 02 3.0448386E-02 8.4782112E-03 5.146418 t E-02 1.0854620E-02 8.3055459E-02 0.2885319 0.I483902 2.9909359E-02 7.3132701E 03 7.8486003E-02 7.5610541E-02 1.6334236E-02 8.5642956E-02 3.9495885E-02 3.7651348E-03 0.1016252 1.6464649E-02 0.1428766 0.1621865 8.9207999E-02 4.5112247E-04 3.3093113E-02 6.8073608E-02 2.7274314E-02 0.1019203 3.3670895E-02 O.1980580 3.6340430E-03 9.4924212E-02 3.8159367E-02 5.0228938E-02 3.2279663E-02 9.6433230E-02 7.8715859E-03 7.2341422E-03 6.2303629E-02 7.2981618E-02 0.1015370 7.6369330E-02 2.1741793E-02 1.5903739E-03 1.0505857E-02 4.2306870E-02 1.Il59037E-02 1.7596968E-02 2.3061221E-02 i 2.7589556E-02 8.6678125E-02 1.6781913E-02 4.9762029E-02 1.7828470E 02 9.8100808E-03 8.0561943E-02 9.4187953E-02 6.2078778E-02 0.1489135 0.I137452 3.5065666E-02 1.5712211E-02 0.I199143 2.9991554E-02 7.2744422E-02 5.6423653E-02 0.1357202 7.7847488E-02 3.8592044E-02 9.1899738E-02 9.1383748 E-02 9.6314792E-03 1.0528071E-02 2.6665970E-03 3.0302284E-02 9.0465531E-02 3.5887018E-02 8.363568dd-02 0.1594036 4.4912171E-02 8.2488284 E-02 6.3044518E-02 0.2009909 4.8654587E 03 Vol. 2, Part 2 G-131 NUREGICR-6143 i 1
LOSP Fmquency 4.ll76889E 02 9.8734237E-02 7.4'/65138E-02 1.2667705E-02 0.1262614 0.1111817 1.3600629E-02 1.7438317E-02 9.5690675E-03 5.1675425E-03 3.2693163E-02 5.8635902E-02 1.9293664E-02 8.5062332E-02 0.2224558 2.7328093E-02 0.1916036 1.2643554E-02 8.1150882E-02 4.9047388E-02 5.4314032E 02 4.9487189E-03 6.2489253E-04 1.4643470E-02 4.1865766E-02 0.1534035 1.2524434E-06 7.2150782E-02 8.3918739E-03 3.0313108E-02 0.1076253 3.2651860E-02 8.0911592E-02 5.2297127E-02 6.0838363E-03 1.I158386E-02 0,1841026 4.5478538E-02 0.1712909 0.1005661 7.5296283E 02 0.1599361 0.1769705 3.9250352E-03 4.4937138E-02 9.0385396E 03 5.8705285E-02 1.2616337E-02 0.1462693 0.1633220 1.8177083E-02 6.6332571E-02 7.2607398E-03 6.3159265E-02 4.3697253E-02 3.4835618E-02 2.1626830E-02 4.3000471E-02 6.3968100E-02 3.1902997E-03 0.2126295 2.8318062E-02 0.2969601 6.1579641E-02 0.2287423 0.1055460 1.5888639E-02 0.1011943 3.1537369E-02 3.0959342E-02 1.6926570E-02 3.4715347E-02 4.0632688E-02 0.1300344 9.4964199E-02 9.7805411E-02 4.7073562E-02 1.1991364E-02 4.2458829E 02 0.4126163 2.4215424E 02 5.9949227E-02 0.1659063 6.8499178E-02 6.2819786E-02 4.6272218E-02 4.5089148E-02 6.7917205E-02 5.0882958E-03 4.5202851E-02 0.1436211 7.4199475E-02 2.9479271E-02 0.1220675 1.2994861E-02 9.6115790E-02 4.3561067E-02 2.7579788E-02 6.1601184E-02 5.1764749E-02 1.823309 t E-02 7.8390967E-03 1.8036981E-04 6.6456713E-02 0.1174101 7.0725784E-02 8.5252132E-03 3 4363531E-02 0.1217265 0.1159837 8.6573020E-02 9.4841480E-02 7.1762465E-02 4.799706?E-03 0.1918874 5.2638784E-02 9.8654538E-02 0.1614968 2.9600626E-02 9.2250086E-02 1.2816365E-02 8.2921065E-02 2.5125390E-02 0.1141646 0.1249470 9.5106354E-03 0.1212057 3.1458316E-05 7.1259312E-02 9.5545508E-02 2.0517757E-02 4.1389301E-02 0.1076581 8.6525485E-02 1.9758463E-02 8.8717468E-02 3.9176088E-02 2.6002066E-02 7.5258906E 03 6.9996879E-02 0.1110684 3.6713161E-02 0.1655387 7.5813979E-02 8.2011253E-02 0.1252603 2.6123142E-02 2.6791573E-02 1.0426432E-04 9.7375177E-02 1.4984865E-02 7.1415707E-02 0.1573987 9.9009417E-02 9.4023019E-02 4.1367975E-03 0.1111227 3.7749022E-02 8.5491806E-02 0.1476692 0.1044355 3.3226274E-02 3.2987423E-02 6.9037460E-02 4.5043502E-02 0.1163967 4.3823916E-02 7.6349050E-02 4.4828497E-02 7.7810525E-03 6.4864228E 03 2.3118341E-02 0.1368688 7.9834806E-03 4.3228015E-02 8.6171895E-02 1.5971426E-02 1.0591272E-02 4.4560567E-02 4,5226362E-02 9.6399421E-03 1.8822059E-02 5.0359242E-02 6.5790229E-02 1 ll31806E-02 0.1216575 5.8292266E-02 8.6674066E-03 2.3019051E-02 7.1365029E-02 7.5110182E-02 5.7775807E 02 2.7813993E-02 4.8554119E-02 0.1534233 9.42107%E 02 3.5423137E 42 9.2147784E-06 2.3537399E-02 4.5220446E 02 0.1249922 2.9857086E-02 9.7445004E-02 3.9333194E-02 4.0321246E-02 0.1011262 0.1548729 0.1148768 6.6698194E-02 9.2383265E-02 2.4293195E 02 4.3557987E-02 1.2202328E-02 1.9953102E-02 0.1957802 6.f578897E-03 1.5834160E-02 1.8492657E-03 6.7289076E-03 6.2168173E-02 . O.Ii11950 3.0191801E-02 4.1577820E-02 0.2049074 0.1421046 l.9772781E 02 4.0227517E-02 0.1904121 2.6612628E-02 4.6885949E-02 0.1155881 6.4106800E-02 1.9257167E-02 6.2301848E-02 2.9114503E-02 0.1582730 0.1264381 6.0050576E-03 4.7661878E-02 9.4231784E-02 0.1393309 5.0514825E-03 1.5237578E-02 0.1032232 3.5982575E-02 1.4094720E-02 7.4786786E-03 0.1926419 2.2303181E-02 0.2368337 0.1499535 5.6379151E-02 0.2087683 2.3918238E-02 8.9359716E-02 7.1544766E-02 6.5043934E-02 0.1375539 8.8102572E-02 1.8088779E-03 3.0904636E-02 2.3314461E-02 0.1049394 1.0482088E-02 0.1065253 NUREG/CR-6143 G-132 Vol. 2, Part 2
LOSP Frequency 7.3502332E 02 0.1753536 9.5153023E 03 2.9384814E-02 1.9874904E42 7.0344500E-02 1.3199417E-02 9.1045044E-02 4.0966433E-02 1.9798214E-02 0.1678364 2.7149079E-02 0.1398786 4.2904954E-02 3.6986031E-02 0.1487750 0.1679944 8.9058951E-02 0.1057777 0.1281379 3.6314774E42 0.1282351 4.0126458E-04 0.2261254 3.9298572E-02 6.3481316E-02 0.I166051 7.0052288E42 0.1538339 5.8032546E-02 9.2176422E-03 5.5682145E-02 7.3337995E-02 4.0085889E-02 0.1591447 0.1027336 3.2945636E-03 6.8856232E 02 7.9803653E-02 1.4832543E 02 7.4707083E-02 0.1148059 6.8583310E-02 5.5337563E-02 3.7277136E-02 3.3868130E-02 3.3945039E-02 6.2655270E-02 2.3415873E-03 1.5916673E-02 1.5667401E42 4.0548373E-02 0.1363300 2.4237448E-02 1.2216034E-02 6.2372845E-02 2.7190035E-02 3.8375910E-02 2.6205523E-02 6.0694687E-02 6.1469404E-03 7.1393445E 02 0.1345783 0.1315373 4.8396634E-03 6.6492967E-02 2.7402056E-02 5.6101017E-02 6.1320782E42 1.2682325E-02 5.2395917E-02 0.1784956 5.1850434E 02 2.5767982E-02 9.7891323E-02 1.0766561E-02 2.%50316E-02 1.9472765E-02 8.9353189E-02 4.4256584E-03 5.2909732E-02 1.3780744E 02 2.7940512E-02 0.1317025 7.2582185E-02 7.0846647E-02 5.0494056E-02 0.I184175 2.7631711E-02 3.2919362E-02 9.0468293E-03 8.3891869E-02 0.1479920 0.1041866 0.2264951 1.3691519E-02 6.8155609E-02 6.4161711E-04 5.8889549E-02 0,1829110 4.8517105E-03 2.7210578E-02 1.8761925E-03 1.2218891E-02 1.0592137E-02 5.0297618E-02 8.0460243E-02 3.5861585E-02 8.4417984E-02 3.9070893E-M. 5.6212086E-02 3.0800391E 03 1.3834529E-02 0.2120718 0.1232555 3.8509235E 02 3.1368252E-02 0.1207141 1.7296594E-02 8.6480059E-02 0.1733319 7.0493244E 02 2.5122650E-02 3.8517248E-02 0.1083883 0.2736189 2.4814460E-02 2.0938128E-02 3.4713827E-02 0.1644907 0.12821,81 6.3549548E-02 6.9029287E-02 0.1962140 2.2284815E-02 7.8335539E 02
)
8.6368740E-02 1.2658233E-03 5.1063392E-02 6.9398761E42 ! 1.0906375E-02 9.3008801E-03 2.3033345E-02 3.5620485E-02 l 2.3066474E-02 9.6362727E-03 0.1255693 5.7140426E-03 0.I874645 0.I297920 4.9152099E-02 4.2732999E-02 2.9084072E-02 7.4851378E-03 0.1012888 1.0141055E-02 3.2290604E-02 7.1975842E-02 3.2810923E-02 5.2287020E-02 0.1759330 3.9767893E-04 5.5024467E-02 0.1110769 1.4150621E42 0.1267434 0.10230 0 2.7594246E-02 O. 1159350 1.7169040E-02 4.7409418E-03 0.1713138 j 4.2492867E-02 1.1717744E-02 3.1449161E-02 2.2145273E-02 O.2267004 2.5022475E-03 3.5321389E-03 0.1135392 ! 0.1055374 2.8072709E-02 2.1979650E-02 4.1683346E-02 ; 0.1955333 8.4042564E-02 3.2869723E-02 3.6470978E-02 3.6001012E-02 1.6251069E-02 6.8814188E-02 4.6982206E-03 9.9207006E-02 1 5.3744357E-02 1.1233456E-02 0.1344099 O.2325092 4.3577 66E-02 1.4781847E-02 ; 6.0120583E-02 7.6863907E-02 7.0901610E-02 0.1314537 4.2035021E-02 1.0775675E-03 Vol. 2, Part 2 G-133 NUREG/CR-6143
I I LOSP Frequency r i t t l I e l ! i i 1 i I Attachment G-29 l STAT-SAS i I { i i t l l i k i t t t i NUREG/CR-6143 G-134 Vol. 2, Part 2 l l, h
LOSP Frequency OPTIONE LINESIZE=79; DATA DATAl; INFILE PCGWLOSP INPUT X; PROC UNIVARIATE; TITLE 'PC/GW DATA'; VAR X; DATA DATA 2; INFILE LHSLOSP; INPUT X; PROC UNIVARIATE; TITLE ' CAT IV DATA'; VAR X; t i i l 1 i l 1 I l l Vol. 2, Pan 2 G-135 NUREG/CR-6143
LOSP Frequency i i l l i 1 i i Attachment G-30 l STAT.LIS P' k NUREG/CR-6143 G-136 Vol. 2, Part 2 ,
LOSP Frequency PC/GW DATA 14:17 TUESDAY, JUNE 4,1991 UNIVARIATE VARIABLE =X MOMENTS N 1000 SUM WGTS 1000 MEAN 0.0649013 SUM 64.9013 , STD DEV 0.0565115 VARIANCE 0.00319355 SKEWNESS 1.592 % KURTOSIS 3.86073 USS 7.40253 CSS 3.19036 CV 87.073 STD MEAN 0.00178705 T:MEAN=0 36.3175 PROB > l T l 0.0001 SGN RANK 250250 PROB > l S l 0.0001 NUM = 0 1000 QUANTILES(DEF=4) EXTREMES 300% MAX 0.412616 99 % 0.247636 LOWEST HIGHEST 75% Q3 0.09235 95 % 0.171641 1.252E-06 0.29696 50% MED 0.0508861 90 % 0.14066 9.215E-06 0.301188 25% Ql 0.0228075 10 % 0.00840051 .000022904 0.320904 0% MIN 1.252E-06 5% 0.0046946 .000031458 0.391779 1% .000452315 .000104264 0.412616 RANGE 0.412615 Q3-Q1 0.0695424 MODE 1.252E-06 I i Vol. 2, Part 2 ' G-137 NUREG/CR-6143 1
LOSP Frequency CAT IV DATA 14:17 TUESDAY, JUNE 4,19912 UNIVARIA'll VARIABLE-X MOMENTS N 1000 SUM WGTS 1000 MEAN 0.123544 SUM 123.544 STD DEV 0.0698132 VARIANCE 0.00487388 SKEWNESS 2.93389 KURTOSI! 20.8052 USS 20.1322 CSS 4.86901 CV 56.5087 STD MEAN 0.00220769 T:MEAN-0 55. % 09 PROB > l T l 0.0001 SGN RANK 250250 PROB > l S l 00001 NUM ^= 0 1000 QUANTILES(DEF=4) EXTREMES 100% MAX 0.863285 99 % 0.354369 LOWEST lilGIIEST 75% Q3 0.154967 95 % 0.244014 0.0110466 0.434986 50% MED 0.1078 90 % 0.199931 0.0143378 0.462437 25% Q1 0.0765061 10 % 0.0565326 0.0153775 0.477914 l 0% MIN 0.0110466 5% 0.0480018 0.0219668 0 763139 1% 0.02919 0.0229742 0.863285 RANGE 0.852238 Q3-Ql 0.0784613 MODE 0.0698282 I l NUR2G/CR-6143 G-138 Vol. 2 Part 2
LOSP Frequency l Attachment G-31 i GGGRID.DAT i l i i I 1 1 l i Vol. 2, Part 2 G-139 NUREG/CR-6143
LOSP Prequency .13 .18 .25 , .3 .33 .33 .333 .55 .92 1.03 1.5 3.0 2.083 6.470 P i i NUREO/CR 6143 G 140 Vol. 2, Part 2
LOSP Frequency , P i 1 Attachment G-32 s GGWEAT.DAT Vol. 2, Part 2 G-14i NUREGICR-6143
i l I ii J - l LOSP Frequency
- 1.75 i 2.67 l
4.0 t 4.317 5.0 i 5.5 I 8.9 11. t l e i l r I
- l j
r f l l l i 1 I l NUREG/CR-6]43 G-142 Vol. 2, Pan 2
LOSP Frequency Attachment G-33 GGPCI.DAT l l l l i l Vol. 2, Part 2 0 143 NUREG/CR-6143
IDSP Frequency
.002
.003
.004
.033
.05
.33
.367 1.
.43
.633
.27
.167
.08
.25
.15
.013
.I83
.48
.15
.017 I
l i l i 1 i I I
- i l
l NUREG/CR-6143 G-144 Vol. 2, Part 2 i l l
LOSP Frequency Attachment G-34 i l GGPC2.DAT l i 1 I l Vol. 2, Part 2 G-145 NUREG/CR-6143
i LOSP Frequency
.07 1.48
.28
.083
.5
.67
.334
.003
.13
.02 1.03
.25
.25 ,
.283
.417 4.0
.050 2.
NUREG/CR-6143 G-146 Vol. 2, Part 2
i LOSP Frequency 1 4 i l 1 Attachment G-35 GGPC3.DAT Vol. 2. Part 2 G-147 NUREG/CR-6143
I LOSP frequency 1.97 l
.9 2.75 ' .9 .015 1.75 .5 , .93 .5 7.43 .4 .2 1.15 .57 .767 1.667 .004 .067 11.083 .233 2.683 4.983 .I17 .717 5
I t i 1 l ( i NUREG/CR4143 c.14g Vol. 2. Part 2 l l l
i l l LOSP Frequency l l Attachment 0 37 f MODELFOR I 1 l I Vol. 2. Part 2 G-151 NUREG/CR4143
LOSP Frequency C AN INTERACTIVE PROGRAM TO IMPLEMENT THE MIXTURE MODEL FOR THE DISTRIBUTION C OF TIME TO RECOVERY OF LOSP AS DEVELOPED IN NUREGICR-5032, SAND 87-2428, C JANUARY 1988: C C 'MODELING TIME TO RECOVERY AND INITIATING EVENT FREQUENCY FOR LOSS OF C OI F-SITE POWER INCIDENTS AT NUCLEAR POWER PLANTS
- C BY RONALD L. IMAN AND STEPHEN C. HORA C THE MIXTURE MODEL MODEL AS GIVEN IN EQUATION (23) OF THAT REPORT IS C OF THE FORM:
C C G(x) - Pl*Gl(x) + P2*G2(x) + P3*G3(x) C WifERE TIIE G(x)'s REPRESENT THE FITTED GAMMA DISTRIBUTIONS C AND THE P's ARE WEIGHTS THAT ARE TREATED WITH A DIRICHLET DISTRIBUTION C C ADDITIONAL INFORMATION CAN BE FOUND IN THE FOLLOWING
REFERENCE:
C C RONALD L. IMAN AND STEPHEN C. HORA (1989). ' BAYESIAN METHODS FOR C MODELING RECOVERY TIMES WitH AN APPLICATION TO Tile LOSS OF OFF-SITE C POWER AT NUCLEAR POWER PLANTS," RISK ANALYSIS, VOL. 9, NO.1,25-36. C NOTE TIIAT ERRATA FOR THIS ARTICLE APPEARS IN VOL. 9, NO. 3. C C TO RUN USE LINK RECOVERY,AMOSLIB,lMSLIBS/ LIB C C NREP = NUMBER OF REPLICATIONS TO BE USED IN THE MONTE CARLO C NPLANT = NUMBER OF PLANTS IN TIIE DATA BASE CONTAINED IN FILE " REC.DAT* C C 'NX* TIME STEPS ARE USED TO GENERATE A GRAPH OF THE RECOVERY CURVE. C Tile *NX" TIME STEPS CORRESPOND TO TIMES IN llOURS OF .05, .10, .15 C 1.30,1.33,1.40,1.45,... , 2.50, 2.75, 3.00, 3.167, 3.25,3.50, C 10.00, 13.3, 15, 16, 18, 23, 27 C C THE VECTOR IDT IS USED TO SPECIFY 'NTIME' TIMES AT WillCH THE UNCERTAINTY C DISTRIBUTION WILL BE SAVED IN AN OUTPUT FILE NAMED "XX.D AT,' WilERE XX IS C ABDREVIATION OF THE PLANT NAME THAT APPEARS IN FILE REC.DAT. THE EXACT C TIMES SPECIFIED WILL VARY FROM ONE PLANT ANALYSIS TO THE NEXT. THE C DIMENSIONS OF THE MATRIX "XX.DAT* ARE *NREP" x 'NTIME
- C C FOR EXAMPLE, IF THE DISTRIBUTION OF TIME TO RECOVERY OF LOSP FOR A C PARTICULAR PLANT IS DESIRED FOR THE FOLLOWING 'NTIME=20" TIMES (IN HOURS):
C .5,.8, 1, 1.133, 1.283, 1.33, 2.5, 3, 3.167, 5, 7, 8, 9, 10, 13.3, C 15,16,18,23,27 C C TIIEN THE VECTOR IDT MUST SPECIFY TO SAVE *NTIME' RESULTS. IN PARTICULAR, C SAVE THE RESULTS OF Tile 10th,16th,20th, OUT OF THE *NX' TIMES FOR C WillCli Ti!E DISTRIBUTION OF RECOVERY TIMES IS GENERATED AS SPECIFIED A'BOVE. C FOR THIS EXAMPLE THE VALUES STORED IN THE VECTOR IDX ARE : 10,16,20,23, C 26, 27, 50, 52, 53. 50, 68, 72, 76, 80, 81, 82, 83, 84, 85, S6. C PROGRAM MODEL PARAM ETER(NREP = 500,NPLANT = 70,K = 3,NX - 86,NTIM E = 20) DIMENSION RESULTS(NREP,NX),X(NX), OUTPUT (K,NX),FM AX(K),IDT(NTIME) 1 ,lSWITCH(N P LANT), P(K),S(K),CU M PRO B(K), PD(K),B(K),1COM P(K) CHARACTER *1 CANS NUREG/CR-6143 G-152 Vol. 2, Part 2
i i l LOSP Frequency i l l 1 I i 1 l I Attachment G-36 GGPC4.DAT l l l 1 i i Vol. 2, Part 2 G 149 NUREG/CR-6143
l i LOSP Frequency i
.002
.003-
.004
.033 i
.05
.33
.367 )
- l. '
.43 i
.633
- l
.27
.167 ;
.08 ;
.25 :
.15
.013 )
i
.183 l
.48
.15
.017
.07 1.48
.28 i
.083
.5
.67
.334 ,
.003
.13 i
.02 1.03
.25
.25 i
.283
.417 4.0 l t
.050
- 2. i' 1.97
.9 2.75 .
.9
.015
- 1.75 y
.5
.93
.5 j 7.43
.4 I
.2 ,
1.15
.57 ;
.767 i 1.667 [
r
.004
.067 .
I1.083 ;
.233 :
2.683 4.983 j
.I17 "
.717
, f l NUREG/CR-6143 G-150 Vol. 2, Part 2 t
,r, - - - - . - _ . . . . __ _ __ - _ ,__ ___ _ _________ _ __
l LOSP Frequency CHARACTER *3 IP CHARACTER *21 IPLANT(NPLANT) CHARACTER *3 NAME(NPLANT) j CHARACTER *80 CFILE EXTERNAL G AM IC,G AM M AM A, QUANT, SIFT COMMON A(3),N(3),NN COMMON ISEED,AA DATA IDT/10,16,20,23,26,27,50,52,53,60,68,72,76,80,81,82,83,84, 1 85,86/ CALL ERXSET(100,1) C READ IN THE PLANT DATA FILE OPEN(UNIT = 10, FILE = ' REC', STAT}JS = 'OLD')
!=1 9 READ (10,100,END-5)lPLANT(I),NAME(I),lSWITCH(I) 100 FORMAT (2A,I4)
I-I+1 GO TO 9 , S NP = I - I CLOSE(10) C SELECT THE PLANT WHOSE INITIATING EVENT FREQUENCY IS DESIRED C DO 10 I = 1,21 WRITE (*,101) NAM E(I),IPLANT(I), NAM E(I + 22),IPLANT(1 + 22), INAME(I+ 43),lPLANT(I & 43) 10 CONTINUE WRITE (*,101)NAME(22),1 PLANT (22) 101 FORMAT (IX,A,' ',A19,2X,A,' ',A19,2X,A,* ',A19) PRINT *,' INPUT THE ABBREVIATION FOR THE PLANT OF INTEREST' READ '(A)',lP DO 11 I = 1,NP IF(IP.EQ.NAME(1))THEN ID=ISWITCH(I) LAST =I GO TO 12 ENDIF 11 CONTINUE 12 CONTINUE i NPC = 62 l C IDENTIFY THE COMPONENTS TO BE USED IN THE COMPOSITE MODEL C C 1 - PLANT CENTERED COMPONENT C 2 - GRID COMPONENT C 3 - WEATHER COMPONENT C 1 PRINT *,'IS THE PLANT CENTERED COMPONENT TO BE USED IN THE' PRINT 105,IPLANT(LAST) ; 105 FORMAT (IX,' COMPOSITE MODEL FOR 'A,'?') PRINT *,'Y OR N' READ *(A)', CANS ICOMP(l)=1 IF(CANS.EQ.'N')lCOMP(l)=0 PRINT *,'IS THE GRID COMPONENT TO BE USED IN THE' PRINT 105,lPLANT(LAST) Vol. 2, Part 2 G-153 NUREG/CR-6143
LOSP Prequency PRINT *,'Y OR N' READ '(A)', CANS ICOMP(2)= 1 IP(CANS.EQ.'N')! COMP (2)=0 PRINT *,'IS THE WEATHER COMPONENT TO BE USED IN THE' PRINT 105,IPLANT(LAST) PRINT *,'Y OR N' READ '(A)', CANS ICOMP(3)= 1 IF(CANS.EQ.'N')lCOMP(3)=0 ISUM = ICOMP(l) + ICOMP(2) + ICOMP(3) IF(ISUM.EQ.0)THEN PRINT *,'NO COMPONENTS WERE SELECTED' GO TO 1 ENDIF C C INPIJT SECTION FOR THE GAMMA DISTRIBUTIONS, G(x)'s C CALCULATE THE PRODUCT, P. OF THE Xs FROM THE GEOMETRIC MEAN C CALCULATE THE SUM, S, OF THE Xs FROM THE ARITHMETIC MEAN IF(ICOMP(l).EQ.0)GO TO 2 C C INPUT THE FLAG FOR SWITCHYARD CONFIGURATION AS DEFINED IN NUREG-1032 C 1 = 11 C 2 - 12 C 3 = 13 C 4 - ALL PLANT CENTERED DATA USED C PRINT *,'THE SWITCHYARD CONFIGURATION PER NUREG-1032 FOR' PRINT 106,IPLANT(LAST),lD 106 FORMAT (IX,A,*IS ',11) PRINT *,'DO YOU WISH TO CHANGE THIS VALUE7 Y OR N' READ *(A)', CANS IF(CANS.EQ.'N')GO TO 13 PRINT *,' INPUT NUMBER FOR SWITCHYARD CONFIGURATION PER NUREG-1032' PRINT *,' ENTER 1 FOR 11 SWITCHYARD' PRINT *,' ENTER 2 FOR 12 SWITCHYARD' PRINT *,' ENTER 3 FOR 13 SWITCHYARD' PRINT *,' ENTER 4 IF CONFIGURATION IS UNKNOWN' READ *,ID 13 IF(ID.EQ.1)THEN P(l)=.08621**20 S(1)=.2306*20 N(1)=20 ELSE IF(ID.EQ.2)THEN P(l)=.23882**18 S(l)=.6583 *18 l N(1)= 18 ELSE IF(ID.EQ.3)THEN P(l)=.61987**24 S(1)= 1.76192*24 N(1)=24 ELSE l P(l) = .2487 * *62 NUREG/CR-6143 G 154 Vol. 2. Part 2
LOSP Frequency S(l)=.94755*62 N(1)= 62 ENDIF 2 CONTINUE IF(ICOMP(2).EQ.0)GO TO 3 C SET THE PARAMETERS FOR GRID E C P(2)=.62347**14
- S(2)= 1.17186*14 N(2)= 14 3 CONTINUE IF(ICOMP(3).EQ.0)GO TO 4 C
C SET THE PARAMETERS FOR WEATilER C P(3)=4.6464**8 S(3)=5.392*8 N(3)= 8 4 CONTINUE C - C INPUT SECTION FOR THE DIRICHLET DISTRIBUTIONS, P's C INPUT Tile WEATilER llAZARD RATIO FOR THE SPECIFIC PLANT C RATIO - 1. IF(ICOM P(3).EQ. l. AND. IS UM .GT.1)TH EN PRINT *,' Tile GENERIC WEATHER RATIO FOR' PRINT 107,IPLANT(LAST) 107 FORMAT (IX,A,'IS l') PRINT *,'DO YOU WISH TO CHANGE THIS VALUE7 Y OR N' READ '(A)', CANS IF(CANS.EQ.'N')GO TO 14 PRINT *,' INPUT THE PLANT SPECIFIC WEATHER HAZARD RATIO' READ *, RATIO 14 CONTINUE ENDIF l Rl=ICOMP(l)*NPC R2=lCOMP(2)*N(2) R3 =ICOMP(3)*N(3) j C l C GENERATE TifE TIME IN STEPS OF .05 FROM .05 TO 2.5 FOR Tile RECOVERY CURVE I C WITil EXCEPTIONS FOR 1.133,1.283 AND 1.33 C DO 15 I= 1,50 X(I)= .05 *1 C PATCH TO GENERATE A TIME OF 1.133,1.283 AND 1.33 IlOURS IF (1.EQ. 23) X(I) = 1.133 IF (1.EQ. 26) X(1) = 1.283 IF (I .EQ. 27) X(I) = 1.333 15 CONTINUE C GENERATE THE TIME IN STEPS OF .25 FROM 2.75 TO 10 FOR THE RECOVERY CURVE C WITH ONE EXCEPTION AT 3.167 Vol. 2, Part 2 G-155 NUREG/CR-6143
LOSP Frequency C DO 16 I-51,80 ' I X(I) = 0.25
- I- 10.0 IF (I .EQ. 53) XG) = 3.167 16 CONTINUE C SET THE LAST SIX Til*E STEPS X(81) = 13.3 X(82) = 15.
X(83) = 16. X(84) = 18. X(85) = 23. X(86) = 27. ISEED = 327251 C l C SETUP l C DO501-1,K IFGCOMP(I).EQ.0)GO TO 50 C FIND TIIE MAXIMUM VALUE OF THE VARIABLE THAT MAXIMIZES THE MARGINAL j C DENSITY OF ALPHA (EQUATION 18 OF THE LOSP REPORT) ! CALL RMAX(XMAX,S(I),PG),NO)) C FIND THE MAXIMUM VALUE OF THE MARGINAL DENSITY OF ALPHA FMAX(I)= F(XMAX,N(I),P(I),S(I)) 50 CONTINUE DO 6 I = 1,K 6 PD(I) = 1. PRINT *,' ' PRINT *,'PLEASE WAIT WillLE THE MONTE CARLO IS BEING PERFORMED' PRINT
- IPC =0 )
DO 500 J-1, NREP 300 DO 70 !=1,K l IF(ICOMP(I).EQ.0)GO TO 70 NN=N(I) C C OBTAIN A VALUE OF BETA FROM THE CONDITIONAL DENSITY GIVEN BY C EQUATION 17 OF Tile LOSP REPORT C CALL CAM PARAM(A(1),BG),S(I),P(I),FM AX(I)) 70 CONTINUE C C ARG4 =.001 IARGl=1 IFOSUM.EQ.1)GO TO 7 IF(ISUM.EQ.3)TilEN CALL DIRICHLET(R1,R2,R3,PD(1),PD(2)) PD(3)= 1.-PD(1)-PD(2) EI.SE IF(ICOMP(l)+1 COMP (2).EQ.2)THEN CALL DIRICHLET2(RI,R2,PD(1)) PD(2)= 1.-PD(1) ELSE IF(ICOM P(l) + ICOM P(3).EQ.2)THEN CALL DIRICHLET?(RI,R3,PD(1)) NUREG/CR-6143 G-156 Vol. 2, Part 2 i
LOSP Frequency PD(3)= 1.-PD(1) ELSE IF(ICOM P(2) +1 COMP (3).EQ.2)THEN CALL DIRICHLET2(R2,R3,PD(2)) PD(3)= 1.-PD(2) ENDIF 7 CONTINUE TOT =0. PD(3) - PD(3)* RATIO DO 8 I = 1,K TOT = TOT + PD(I)
- ICOMP(I) 8 CONTINUE C WRITE (99,*)' J, TOT ',J. TOT DO 4101-1,NX DO 450 IC-1,K IF(ICOMP(IC).EQ.0)GO TO 450 Y= x(I)*B(Ic)
IF(Y.GT.200.) 00 TO 300 CALL GAMIC (Y, A(IC), ARG4,IARGI,CUMPROB(IC),NZ) 450 CONTINUE C WRITE (99,*)' I,X(I), CUM ',1,X(I),(CUM PROB (IC),IC = 1,3) RESULTS(J,1) = 1. -ICOMP(l)*PD(1)/ TOT *CUMPROB(1) 1 - ICOMP(2)*PD(2)frOT*CUMPROB(2) - ICOMP(3)*PD(3)/ TOT *CUMPROB(3) 410 CONTINUE IF(MOD (J,NREP/100).EQ.0)THEN IPC-IPC +l PRINT 109,IPC 109 FORMAT ('+THE CALCULATION 13 ',13,'% COMPLETE') ENDIF 500 CONTINUE C C WRITE OUT Tile FILE CONTAINING THE UNCERTAINTY DISTRIBUTION AT C EACH OF THE NTIME SPECIFIED TIME POINTS C C Tills FILE WILL BE AN NREP x NTIME MATRIX WITH EACH COLUMN CONTAINING C Tile UNCERTAINTY DISTRIBUTION AT A GIVEN TIME POINT. THESE DISTRIBUTIONS C ARE USED BY THE LilS PROGRAM IN THE UNCERTAINTY ANALYSIS. THE VALUES IN C EACH COLUMN HAVE BEEN SORTED FROM SMALLEST TO LARGEST. C OPEN (UNIT = 11 FILE = IP//'.DAT', STATUS = 'NEW') DO 800 !=1,NX CALL SIFT (NREP,RESULTS(1,1)) 80Q CONTINUE DO 90001 = 1,NREP WRITE (11,*) (RESULTS(1,lDT(J))J -1,NTIM E) 9000 CONTINUE CLOSE(UNIT = 1l) C WRITE OUT FILE FOR MAPPER WITH 90% UNCERTAINTY BOUNDS C AND FILE WITH TIIB COMPLETE UNCERTAINTY DISTRIBUTION C FOR TilOSE TIME POINTS IDENTIFIED IN IDT C PRINT *,'DO YOU WANT TO CREATE A M APPER FILE FOR PLOTTING 7 Y OR N' READ '(A)', CANS { IF(CANS.EQ.'N')GO TO 802 Vol. 2, Part 2 G-157 NUREG/CR 6143
LOSP Frequency DO 8011-1,NX CALL QUANT (.05,NREP,RESULTS(1,1),0UTPUT(1,1)) CALL QUANT (.50,NREP,RESULTS(1,1),0UTPUT(2,1)) CAI.L QUANT (.95,NREP,RESULTS(1,1),0UTPUT(3,I)) 801 CONTINUE CALL MAPPER (OUTPUT,X,IPLANT(LAST),IP) 802 CONTINUE STOP END C C SUBROUTINE TO SELECT A RANDOM VARIABLE FROM A GAMMA DISTRIBUTION C USING THE ACCEPTANCE-REJECTION METHOD C SUBROUTINE GAMPARAM(AA,B,$,P,FMAX) COMMON A(3),N(3),NN l l COMMON ISEED,AAA ' EXTERNAL GAMIC,GAMMAM A, QUANT, SIFT 300 T= RAN(ISEED)
)
PB-RAN(ISEED) AA = T/(1.-T) AAA=AA C C IN ALPIIA IS TOO LARGE OR TOO SMALL, TRY ANOTHER VALUE. C TlHS AVOIDS NUMERICAL PROBLEMS. C IF (AA.LT.(5.0E-3)) GOTO 300 IF(AA.GT. 999999) GOTO 300 Fl = F(T,NN,P,S) C C ACCEPT OR REJECT THE VALUE OF ALPHA C IF (Fl/FMAX LT.RAN(ISEED)) GOTO 300 ARGl= 2.*PB*AA*NN ARG2-0. l *NN *AA ARG3 =.000l*NN*AA ARG4 = 1. IF(AA.GT.20.) GOTO 300 C C FINP A VALUE OF BETA CORRESPONDIN'3 TO A CUMULATIVE PROBABILITY P l C CALL FINVER(GAMMAMA PB ARGI,ARG2,ARG3,ARG3,ARG4) B = ARGl/S 330 CONTINUE RETURN END C C C REAL FUNCTION F(T,N,P,5) DIMENSION P(l),S(l),N(1) A -T/(1.-T) NN = N(1) SS-S (1) NUREG/CR-6143 G 158 Vol. 2, Part 2 l l l l
I l l LOSP Frequency PP-P (1) FL = (A-l.)* LOG (PP) + G AM LN(NN *A)-NN *G AM LN(A) X -NN*A* LOG (SS)-2* LOG (1.-T)-LOG (A) F=EXP(FL) FTEST=P RETURN l END l C l C C REAL FUNCTION FNEG(T.P.S,N,N2,N3) DIMENSION P(l),5(1),N(1) FNEG =-F(T,N.P.S) FTEST= FNEO RETURN END C C FINDS THE VALUE OF THE VARIABLE THAT MAXIMIZES THE DENSITY F C SUBROUTINE RMAX(XMIN,S,P,N) DIMENSION P(l),S(l),N(1) EXTERNAL FNEG E=.01 A=E B = l.-E TOL=.001 CALL ZXGSP(FNEG,P,S,N,lP4,IPS,A,B,TOL,XMIN,IER) FTEST=XMIN RETURN END C C C i SUBROUTINE GAMMAMA(X,FOFX) COMMON A(3),N(3),NN COMMON ISEED,AA IF (X.LT.O.0) THEN F0FX-0. RETURN ENDIF TOL= 1.E-5 NUNIT=1 XX=X AAA= AA*NN IF (X.GT.5.*AAA) THEN j FOFOX- 1.0 i RETURN ENDIF CALL GAMIC (X,AAA,TOL,NUNIT FOFX,NZ) F0FXX-F0FX RETURN END C C Vol. 2, Part 2 G-159 NUREG/CR-6143
LOSP Frequency SUBROUTINE DIRICHLET(RI R2,R3,PI,P2) COMMON A(3),N(3),NN COMMON ISEED,AA CONL - G AM LN(R1 + R2 + R3)4 AM LN(RI)-G AMLN(R2)-G AM LN(R3) RN = Rl+ R2 + R3 PIMAX=(RI-1.)/(RN-1.) P2 MAX-(R2-1 )/(RN-1.) FM AX = CONL + (Rl-1.)* LOG (PIM AX) + (R2-1.)* LOG (P2M AX) + (R3-1.)* X LOGO.-PIMAX-P2 MAX) 100 CONTINUE Pl =RANOSEED) P2-RAN(ISEED) P3 = RANOSEED) IF(Pl + P2.GT,1.) GOTO 100 F = CONL + (RI-1.)* LOG (PI) + (R2-l.)* LOG (P2) + (R3-1.)* LOGO-PI-P2) IP (P3.LT.EXP(F-FMAX)) RETURN GOTO 100 END C C SUBROUTINE DIRICllLET2(R1,R2,PI) COMMON A(3),N(3),NN COMMON ISEED, AA CONL- G AM LN(Rl + R2)-G AM LN(RI)-G AM LN(R2) RN= Rl+ R2 PlMAX=(RI-l.)/(RN .) FM AX = CONL + (Rl-1.)* LOG (P!M AX) + (R2-1.)* LOG (1. P!M AX) 100 CONTINUE Pl= RAN(ISEED) P2 = RAN(ISEED) F = CONL + (RI-l.)* LOG (PI) + (R2-1.)* LOG (1-PI) IF (P2.LT.EXP(F-FMAX)) RETURN GO TO 100 END C C C SUBROUTINE QUANT (QNT.N,X XQNT) DIMENSION X(N) IF (MOD (FLOAT (N)*QNT,1.0) .EQ. 0.0) THEN IQNT = N
- QNT JQNT = IQNT + 1 ELSE IQNT = N
- QNT + 1 JQNT = IQNT ENDIF XQNT = 0.5 * (X(IQNT) + X(JQNT))
RETURN END SUBROUTINE SIFT (N,XV) DIMENSION XV(N) M=N 10 M = M/2 NUREG/CR-6143 G-160 Vol. 2, Part 2
l LOSP Frequency IF (M) 30,20,30 20 RETURN 30 K=N M J-l 40 !=J 50 L-I+ M IF (XV(I)-XV(L)) 70,70,60 60 A-XV(I) XV(I)=XV(L) XV(L)= A I-I-M IF (I) 70,70,50 70 J-J +1 IF (J-K) 40,40,10 END l C l C SUBROUTINE TO WRITE OUT M APPEP. FILE FOR PLOTTING C SUBROUTINE MAPPER (XQ,X,lPLANT,lP) PARAMETER (K = 3,N = 86) DIMENSION XQ(K,N),X(N) CHARACTER *(*) IPLANT,lP OPEN (UNIT =2, FILE = IP//'.M AP', STATUS ='NEW') C C WRITE OUT THE TITLE IN THE PLOT FILE FOR M APPER C WRITE (2,104) WRITE (2,105)IPLANT C C WRITE OUT LOWER 5 % POINTS ON E = 1.0 ) ZER0 = 0.0 WRITE (2,106) WRITE (2,101) ZERO,0NE DO 401 = 1,N 1 WRITE (2,102) X(I), XQ(1,1) 40 CONTINUE WRITE (2,103) X(N), XQ(1,N) C C WRITE OUT 50% POINTS C WRITE (2,107) WRITE (2,101) ZERO,0NE i DO 50 I = 1,N-1 l WRITE (2,102) X(I), XQ(2,1) i 50 CONTINUE WRITE (2,103) X(N), XQ(2,N) C C WRITE OUT UPPER 5 % POltRS C . WRITE (2,108) WRITE (2,101) ZERO,0NE DO 60 I = 1,N-1 i Vol. 2, Part 2 G-161 NUREG/CR-6143
- ---- - I
LOSP Frequency WRITE (2,102) X(I), XQ(3,1) 60 CONTINUE WRITE (2,103) X(N), XQ(3,N) CLOSE (2) 101 FORMAT ('SLINE(',E14.7,',',E14.7,',l') 102 FORMAT (E14.7,',*,E14.7) 103 FORMAT (E14.7, ',',E14.7,*,2',/,' RETURN') 104 FORMAT ('* TITLE *',/'LABE!41,8.5,9.5.11,2,0') 105 FORMAT ('AI.35 > RECOVERY CURVE FOR ',A,/,' RETURN') 106 FORMAT ('* LOWER **) 107 FORMAT ('* MEDIAN **) 108 FORMAT ('* UPPER **) RETURN l NUREG/CR-6143 G-162 Vol. 2, Part 2
LOSP Frequency Anehment G-38 GAMMA.FOR Vol. 2. Part 2 G-163 NUREG/CRH5143
LOSP Frequency C PROGRAM TO CALCULATE TIIE MLE'S FOR TIIE GAMMA DISTRIBUTION C PER LAWLESS CHARACTER *80 CFILE REAL LAMBDA PRINT *,' INPUT FILE NAME ENCLOSED IN SINGLE QUOTES' READ *,CFILE OPEN(UNIT =1. FILE-CFILE, STATUS ='OLD') OPEN(UNIT- 6, FILE = 'M LE.OUT', STATUS = 'NEW') SUM = 0. SUMLOG = 0. N=0 10 READ (1,*,END-1)X N=N+1 SUM = SUM + X SUMLOG = SUMLOG + LOG (X) 00 TO 10 1 CONTINUE AMEAN = SUM / FLOAT (N) GMEAN = EXP(SUMLOG/ FLOAT (N)) S = LOG (AMEAN/GMEAN) IF(S.GT.5772)ALPilAT = (8.898919 + 9.059950*S + .9775373*S*S)/ 1 (S*(17.79728 + 11.%8477*S + S*S)) IF(S.LE.5772)ALPHAT=(.50006'76 + .1648852*S .0544274*S*S)/S BETAl{AT = ALPilAT/AMEAN WRITE (6,102)CFILE 102 FORMAT (' MLE: FOR INPUT FILE: ',A) WRITE (6,100)AMEAN,GMEAN,S,ALPH AT,BETAHAT N 100 FORMAT (*0 SAMPLE MEAN = ' E12.7/ , 1
- GEOMETRIC MEAN = ',E12.7/
2 *S= ' F12.7/ 3
- ALPHA HAT =
- F12.7/
4 ' BETA HAT = ' F12.7/ 5 ' SAMPLE SIZE = ' 15) CALL EXIT END NUREG/CR4143 G-164 Vol. 2, Part 2
LOSP Frequency 9 Attachment G-39 MLE.OUT Vol 2 Part 2 G-165 NUREG/CR 6143
LOSP Frequency MLEs FOR INPUT FILE: ggpc4.dat SAMPLE MEAN = .9475484E + 00 GEOMETRIC MEAN = .2486961E + 00 S = 1.3376462 ALPHA HAT = 0.4659370 BETA HA = 0.4917290 SAMPLE SIZE = 62 NUREG/CR-6143 G.166 Vol. 2, Part 2
LOSP Frequency C l l i i l I Attachment G-40 AMOSLIB.FOR l i I l 1 Vol. 2. Pac 2 G-167 NUREG/CR-6143
LOSP Frequency SUBROUTINE ERRCHK (NCHARS,NARRAY) C C SANDIA MATHEMATICAL PROGRAM LIBRARY C APPLIED MATHEMATICS DIVISION 2642 C SANDIA LABORATORIES C ALBUQUERQUE, NEW MEXICO 87115 C , C SIMPLIFIED VERSION FOR STAND-ALONE USE. APRIL 1977 C C ABSTRACT C THE ROUTINES ERRCHK, ERXSET, AND ERRGET TOGETHER PROVIDE C A UNIFORM METHOD WITH SEVERAL OITIONS FOR THE PROCESSING C OF DIAGNOSTICS AND WAkNING MESSAGES WHICH ORIGINATE C IN THE MATHEMATICAL PROGRAM LIBRARY ROUTINES. C ERRCHK IS THE CENTRAL ROUTINE, WHICH ACTUALLY PROCESSES C MESSAGES. C C DESCRIPTION OF ARGUMENTS l C NCHARS- NUMBER OF CHARACTERS IN HOLLERITH MESSAGE. C IF NCHARS IS NEGATED, ERRCHK WILL UNCONDITIONALLY C PRINT THE MESSAGE AND STur' EXECUTION. OTHL. WISE, I C THE BEHAVIOR OF ERRCHK MAY BE CONTROLLED BY C AN APPROPRIATE CALL TO ERXSET. C NARRAY- NAME OF ARRAY OR VARIABLE CONTAINING THE MESSAGE, C OR ELSE A LITERAL HOLLERITH CONSTANT CONTAINING C THE MESSAGE. BY CONVENTION, ALL MESSAGES SHOULD C BEGIN WITH *IN SUDNAM, ...
- WHERE SUBNAM IS THE C NAME OF THE ROUTINE CALLING ERRCHK.
C C EXAMPLES C 1. TO ALLOW CONTROL BY CALLING ERXSET, USE C CALL ERRCHK(30,30HIN QUAD, INVALID VALUE OF ERR.) C 2. TO UNCONDITIONALLY PRINT A MESSAGE AND STOP EXECUTION,USE C CALL ERP4'9K(-30,30HIN QUAD, INVALID VALUE OF ERR.) C C C C ERRCHK USES SUBROUTINES ERRGET, ERRPRT, ERXSET, ERSTGT C COMPILE DECKS ERRCHK DIMENSION NARRAY(14) C CALL ERRGE-(NF,NT) C IF ERRCHK WAS CALLED WITH NEGATIVE CHARACTER COUNT, SET FATAL FLAG IF (NCHARS.LT.0) NF = -1 C IF MESSAGES ARE TO BE SUPPRESSED, RETURN IF (NF.EQ.0) RETURN C , IF CIIARACTER COUNT IS INVALID, STOP IF (NCHARS.EQ 0; PRINT 5 5 FORMAT (/3'H ERRCHK WAS CALLED INCORRECTLY.) IF (NCHARS.EQ.0) STOP ! C PRINT MESSAGE CALL ERRPRT(IABS(NCHARS),N' ARRAY) C IF LAST MESSAGE, SAY SO NUREG/CR-6143 G-168 Vol. 2, Part 2
l LOSP Frequency IF (NF.EQ.1) PRINT 10 10 FORMAT (30H ERRCHK MI3 SAGE LIMIT REACHED.) C PRINT TRACE-BACK IF ACKED TO C IF ((NT.GT.0).OR.(NF.LT.0)) CALL SYSTEM ROUTINE FOR TRACEBACK C DECREMENT MESSAGE COUNT IF (NF.GT 0) NF - NF-1 , CALL ERXSET(NF,NT) C IF ALL IS WELL, RETURN IF (NF.GE.0) RETURN C IF Tills MESSAGE IS SUPPRESSABLE BY AN ERXSET CALL, C THEN EXPLAIN ERXSET USAGE. i IF (NCHARS.GT.0) PRINT 15 15 FORMAT (/13H *** NOTE *** l I/53H TO MAKE THE ERROR MESSAGE PRINTED ABOVE BE NONFATAL, l 2/3911 OR TO SUPPRESS THE MESSAGE COMPLETELY, 3/37H INSERT AN APPROPRIATE CALL TO ERXSET 4 3OH AT THE START OF YOUR PROGRAM. 5/62H FOR EXAMPLE, TO PRINT UP TO 10 NONFATAL WARNING MESSAGES, USE 6/27H CALL ERXSET(10,0) PRINT 20 20 FORMAT (/28H PROGRAM ABORT DUE TO ERROR.) STOP END SUBROUTINE ONECIIK(NCHARS,NARRAY) C C ABSTRAC.T C ONECHK IS A COMFANION ROUTINE OF ERRCHK. IT IS CALLED C JUST LIKE ERRCHK, AND MESSAGES FROM IT MAY BE SUPPRESSED C BY AN APPROPRIATE CALL TO ERXSET. IT DIFFERS FROM ERRCHK C IN THAT EACH CALL TO ONECHK WILL PRODUCE NO MORE THAN ONE C PRINTED MESSAGE, REGARDLESS OF HOW MANY TIMES THAT CALL IS C EXECUTED, AND ONECHK NEVER TERMINATES EXECUTION. C ITS PURPOSE IS TO PROVIDE ONE-TIME-ONLY INFORMATIVE C DIAGNOSTICS. C C DESCRII' TION OF ARGUMENTS C NCHARS- NUMBER OF CHARACTERS IN THE MESSAGE. C IF NEGATED THE MESSAGE WILL BE PRINTED (ONCE) EVEN l C IF NFATAL HAS BEEN SET TO O (SEE ERXSET). C NARRAY- SAME AS IN ERRCHK C C C ONECHK USES SUBROUTINES ERRGET, ERRPRT, ERXSET, ERSTGT C COMPILE DECKS ERRCHK C DIMENSION NARRAY(I4) DATA NFLAG/4H.$,*/ IF (NARRAY(1).EQ.NFLAG) RETURN CALL ERRGET(NF,NT) IF ((NF.EQ.0). AND.(NCHARS.GT.0)) RETURN CALL ERRPRT (59,59HTHE FOLLOWING INFORM ATIVE M AGNOSTIC WILL APPEA IR ONLY ONCE.) CALL ERRPRT(IABS(NCHARS).NARRAY) Vol. 2, Part 2 G-169 NUREG/CR-6143 1
LOSP Frequency IF (NP.GT.0) NF - NF-1 CALL ERXSET(NF,NT) NARRAY(1) - NFLAG END SUBROUTINE ERRPRT(NCHARS,NARRAY) C C UTILITY ROUTINE TO SIMPLY PRINT THE HOLLERITH MESSAGE IN NARRAY, C WHOSE LENGTH IS NCHARS CHARACTERS. C DIMENSION NARRAY(14) C C NOTE - NCH MUST BE THE NUMBER OF HOLLERITH CHARACTERS STORED C PER WORD. IF NCH IS CHANGED, FORMAT I MUST ALSO BE C CHANGED CORRESPONDINGLY. C ' NCH = 10 C FOR LINE PRINTERS, USE I FORMAT (lX,13A10) C FOR DATA TERMINALS, USE C 1 FORMAT (IX,7A10) NWORDS = (NCHARS+NCH-1)/NCH PRINT I,(NARRAY(1),1=1,NWOPDS) RETURN END SUBROUTINE ERXSET(NFATAL,NTRACE) C C ABSTRACT C ERXSET IS A COMPANION ROUTINE TO SUBROUTINE ERRCIIK. C ERXSET ASSIGNS THE VALUES OF NFATAL AND NTRACE RESPECTIVELY C TO NF AND NT IN COMMON BLOCK MLBLK0 THEREBY SPECIFYING THE C STATE OF THE OlrTIONS WHICH CONTROL THE EXECUTION OF ERRCHK. C C , DESCRIPTION OF ARGUMENTS C BOTH ARGUMENTS ARE INPUT ARGUMENTS OF DATA TYPE INTEG51R. C NFATAL -IS A FATAL-ERROR / MESSAGE-LIMIT FLAG. A NEGATIVE C VALUE DENOTES THAT DETECTED DIFFICULTIES ARE TO BE C TREATED AS FATAL ERRORS. NONNEGATIVE MEANS NONFATAL. C A NONNEGATIVE VALUE IS THE MAXIMUM NUMBER OF NONFATAL C WARNING MESSAGES WHICH WILL BE PRINTED BY ERRCHK, C AFTER WHICH NONFATAL MESSAGES WILL NOT BE PRINTED. C (DEFAULT VALUE IS -1.) C NTRACE .GE.1 WILL CAUSE A TRACE-BACK TO BE GIVEN, C IF THIS FEATURE IS IMPLEMENTED ON THIS SYSTEM. C .LE.0 WILL SUPPRESS ANY TRACE-BACK, EXCElrr FOR C CASES WHEN EXECUTION IS TERMINATED. C (DEFAULT VALUE IS 0.) C C
- NOTE * - SOME CAllJi TO ERRCHK WILL CAUSE UNCONDITIONAL C TERMINATION OF SXECUTION. ERXSET HAS NO EFFECT ON SUCH CALLS.
C C EXAMPLES C 1. TO PRINT UP TO 100 MESSAGES AS NONFATAL WARNINGS USE C CALL ERXSET(100,0) NUREG/CR-6143 G-170 Vol.1, Part 2
.~ - _ _ LOSP Frequency C 2. TO SUPPRESS ALL MATHLIB WARNING MESSAGES USE C CALL ERXSET(0,0) C C C C ERXSET USES SUBROUTINES ERSTGT C COMPILE DECKS ERRCHK , C CALL ERSTGT(0,NFATAL,NTRACE) ' RETURN END SUBROUTINE ERRGET(NFATAL,NTRACE) C , C ABSTRACT C ERRGET IS A COMPANION ROUTINE TO SUBROUTINE ERRCHK. C ERRGET ASSIGNS TO NFATAL AND NTRACE RESPECTIVELY THE VALUES C OF NF AND NT IN COMMON BLOG MLBLK0 THEREBY ASCERTAINING THE C STATE OF THE ONIONS WHICH CONTROL THE EXECUTION OF ERRCHK. C C DESCRINION OF ARGUMENTS C BOTH ARGUMENTS ARE OUTPUT ARGUMENTS OF DATA TYPE INTEGER. C
- NFATAL - CURRENT VALUE OF NF (SEE DESCRIPTION OF ERXSET.)
C NTRACE - CURRENT VALUE OF NT (SEE DESCRINION OF ERXSET.) C CALL ERSTGT(1,NFATAL,NTRACE) RETURN END SUBROUTINE ERSTGT(K,NFATAL,NTRACE) C C THIS ROUTINE IS A SLAVE TO ERRGET AND ERRSET WIIICH KEEPS C TIIE FLAGS AS LOCAL VARIABLES. C C *** IF LOCAL VARIABLES ARE NOT NORMALLY RETAINED BETWEEN C CALLS ON THIS SYSTEM, THE VARIABLES LNF AND LNT CAN BE . C PLACED IN A COMMON BLOCK AND PRESET TO THE FOLLOWING C VALUES IN THE MAIN PROGRAM. C DATA LNF/-l/-LNT/0/ IF (K.LE.0) LNF = NFATAL IF (K.LE.0) LNT = NTRACE IF (K.GT.0) NFATAL = LNF IF (K.GT.0) NTRACE = LNT RETURN END SUBROUTINE FINVER(FUN,Y,X,DELX,ABSERR,RELERR,FMON) C C WRITTEN BY D.E.AMOS AND S.L. DANIEL, SEPTEMBER,1969. C C REFERENCES C SC-DR-72-0917 C C ELEMENTS OF NUMERICAL ANALYSIS BY P. IIENRICI, WILEY,1964, C PP. 211-213 Vol. 2, Part 2 G 171 NUREG/CR-6143
I l l i LOSP Frequency
]
C C ABSTRACT C FINVER INVERTS F(X)=Y OR FINDS A ROOT OF F(X)-Y=0. C AN INITIAL ESTIMATE FOR X MUST BE SUPPLIED AS WELL AS AN C INCREMENT FOR SEARCHING OUT A CHANGE IN SIGN OF F(X)-Y. I C MONOTONICITY OF F IN TIIE AREA OF SEARCH MUST ALSO BE C l SPECIFIED. ONCE BOUNDS ARE ESTABLISHED ON A ROOT ~ C THE ESTIMATE IS REFINED BY LINEAR INTERPOLATION-C WHICH GIVES A THIRD POINT. SUCCESSIVE UPPER AND LOWER C BOUNDS ARE REFINED REPEATEDLY BY QUADRATIC TNTFRPOLATION. I C l C DESCRIIrFION OF ARGUMENTS C i C INPUT C FUN - AN EXTERNAL SUBROUTINE FOR F(X) TO BE SUPPLIED ) C BY THE USER WITH THE CALL LIST j C ' C SUBROUTINE FUN (X,FOFX) l C C AN EXTERNAL STATEMENT C C EXTERNAL FUN C C MUST APPEAR IN THE CALLING PROGRAM. C Y - GIVEN FUNCTION VALUE C X -INITIAL ESTIMATE FOR THE SOLUTION OF F(X)-Y=0 C DELX - SEARCH INCREMENT FOR BOUNDING THE ROOT, DELX.GT.0.0 C ABSERR - ABSOLUTE ERROR TOLERANCE IN MIXED ERROR TEST C ABS (F(X)-Y).LE.RELERR* ABS (Y)+ ABSER.R. C RELERR=0.0 FOR A PURE ABSOLUTE ERROR. C 0.LE. ABSERR.LE.1. , C RELERR - RELATIVE ERROR TOLERANCE IN MIXED ERROR TEST C ABS (r[X).Y).LE.RELERR* ABS (Y) + ABSERR. C ABSERR=0.0 FOR A PURE RELATIVE ERROR. O.LE.RELERR.LE.1. C FMON - A MONOTONICITY INDICATOR FOR F(X) C FMON=-l. MEANS F IS MONOTONE DECREASING, C FMON= +1. MEANS F IS MONOTONE INCREASING C IN THE VICINITY OF X. C C OUTPUT C X - RESULT FOR THE SOLUTION OF F(X)=Y C C ERROR CONDITIONS C IMPROPER VALUES FOR DELX OR FMON ARE FATAL ERRORS. C C ! C l C FINVER USES SUBROUTINES ERRCHK ~ ERRGET- ERRPRT, ERXSET, ERSTGT l C COMPILE DECKS FINVER, ERRCHK ! EXTERNAL FUN IF(FMON.NE.-l.0. AND. FMON.NE.1.0) GO TO 901 NUREG/CR-6143 G-172 Vol. 2, Part 2 l
LOSP Frequency IF(DELX.EQ.0.0) GO TO 902 IF(ABSERR.LT.O.0.OR. ABSERR.GT.I.) GO TO 903 IF(RELERR.LT.O.0.OR. RELERR.GT.I.) GO TO 904 SIGN =FMON/ ABS (FMON) FLAG =0. ALFA-SIGN *Y i D=DELX IFLAG =0 FTOL=RELERR* ABS (ALFA)+ABSERR C C C COMPUTATION OF FOFX 100 CONTINUE CALL FUN (X,FOFX) FOFX= SIGN *FOFX F2 = FOFX-ALFA FAB = ABS (F2) IF(FAB PTOL) 200,200,86 86 CONTINUE IF(IFLAG.EQ.I) GO TO 36 C BOUNDING TIIE ZERO OF F(X)-Y IF(FLAG) 20,21,20 21 IF(F2) 25,200,85 20 IF(F2) 30,200,70 30 IF(FI) 40,75,80 25 FLAG =1. 40 XP=X X=X+D Fl= F2 GO TO 100 70 IF(FI) 80,75,90 85 FLAG =l. 90 XP=X , X=X-D Fl=F2 GO TO 100 75 F2= FI X=XP GO TO 100 C END PROGRAM FOR BOUNDING TiiE ZERO C C MULLERS METHOD FOR INVERSE INTERPOLATION C IIENRICI, ELEMENTS OF NUMERICAL ANALYSIS, P.212 80 CONTINUE F0= FI Fl=F2 XO O-XP X10= X XP1-X Xil =(Fl*X00-F0*X10)/(F1-F0) X20= Xil IF(X20.GE.XP.AND.X20.LE.XPI) GO TO 88 IF(X20.GE.XPl. AND.X20.LE.XP) GO TO 88 j Vol. 2, Part 2 G-173 NUREG/CR-6143 i l l l 1
LOSP Frequency X .5*(XP + X) GO TO 100 88 X=X20 IFLAG = 1 GO TO 100 36 IFLAG=0 DEN!= F2-Fi IF(DENI.EQ.0.0) GO TO 205 DEN 2 - F2-F0 IF(DEN 2.EQ.0.0) GO TO 205 X21 = (F2*X10-Fl*X20)/DENI X22 -(F2*Xil-FO*X21)/ DEN 2 IF(X22.GE.XP. AND.X22.LE.XPI) GO TO 99 IF(X22.GE.XPl. AND.X22.LE.XP) GO TO 99 X .5*(X00+X10) D =.5 *D GO TO 100 99 FO=FI F1-F2 X00= X10 X10 = X20 X11=X21 X20= X22 GO TO 88 200 CONTINUE C FAB = ABS (FOFX-Y) C l RETURN 205 IFLAG = 0 FLAG =0. D - D *.5 GO TO 100 I 901 CALL ERRCHK(54,54HIN FINVER, MONOTONIC INDICATOR, FMON, IS NOT 1. IOR -1.) RETURN i 902 CALL ERRCHK(23,23111N FINVER, DELX IS ZERO) l RETURN ' 903 CALL ERRCIIK(37,37HIN FINVER, IMPROPER INPUT FOR ABSERR.) , RETURN ' 904 CALL ERRCHK(37,37HIN FINVER, IMPROPER INPUT FOR RELERR.) RETURN END j SUBROUTINE GAMIC (X, ALPHA,REL,N,Y,NZ) l C C WRITTEN BY D.E. AMOS AND S.L. DANIEL, NOVEMBER,1974. ! C C REFERENCE SC-DR-72 0303 C C ABSTRACT C GAMIC COMPUTES AN N MEMBER SEQUENCE OF INCOMPLETE GAMMA C FUNCTIONS NORMALIZED SO THAT AT X-INFINITY, THE INCOMPLETE C GAMMA FUNCTION HAS THE VALUE 1. THE SEQUENCE IS DENOTED BY C NUREG/CR-6143 G.174 Vol. 2, Part 2 l l
l LOSP Frequency j C Y(K) = INCG AM MA(ALPHA + K-1,X)/G AM M A(ALPHA + K-l), K - 1,2,.. . . ,N i C C AND IS COMPUTED TO A RELATIVE ERROR REL OR BETTER WHERE ALPHA C .GT.O. IF ALPHA +N-1.GE.X, THE LAST MEMBER IS COMPUTED BY THE C CONFLUENT HYPERGEOMETRIC SERIES WITH THE OTHER MEMBERS . C COMPUTED BY BACKWARD RECURSION ON A TWO-TERM FORMULA, l C C Y(K-l) = Y(K) + EXP((ALPHA + K-l)*ALOG(X)-X-G AM LN(ALPHA + K)). C C IF ALPHA +N-1.LT.X, AN INTEGER M IS ADDED SO THAT I C ALPHA +N-l+M.GE.X AND THE FIRST PROCEDURE IS APPLIED. SPECIAL C PROCEDURES APPLY FOR ALPHA.EQ.1 OR AN UNDERFLOW OCCURS OR C X EXCEEDS A CRITICAL VALUE, APTEST, WHERE ALL MEMBERS ARE 1. C TO THE WORD LENGTH OF THE CDC 6600. GAMIC USES GAMLN. C C DESCRII' TION OF ARGUMENTS C C INPUT C X - ARGUMENT, X.GE.0.0 C ALPHA - PARAMETER, ALPHA.GT.O.0 C REL - RELATIVE ERROR TOLERANCE, REL-l.E-S FOR S C SIGNIFICANT DIGITS C N - NUMBER OF GAMMA FUNCTIONS IN THE SEQUENCE C BEGINNING AT PARAMETER ALPHA, N.GE.1 C C OUTPUT C Y - A VECTOR CONTAINING AN N MEMBER SEQUENCE C Y(K)= INCGAMMA(ALPHA +K-1,X)/ GAMMA (ALPHA +K-l), j C K - 1,. . . ,N TO A RELATIVE ERROR REL. C NZ - UNDERFLOW FLAG C NZ.EQ.0, A NORMAL RETURN C NZ.NE.0, UNDERFLOW, Y(K)=0.0, K=N-NZ+1,N RETURNED C C ERROR CONDITIONS C IMPROPER INPUT PARAMETERS - A FATAL ERROR C UNDERFLOW - A NON-FATAL ERROR. C C C C GAMIC USES SUBROUTINES GAMLN, ERRCHK, ERRGET, ERRPRT, ERXSET, I C ERSTGT l' C COMPILE DECKS GAMIC, GAMLN, ERRCHK DIMENSION Y(1) DIMENSION AA(6) BB(6),CC(5) C DATA AA /1.18399941922176E +00, 3.30888136276861E +02, 1 1.04930832947926E + 04, 3.78420325596908E + 04,1.57586618187374 E + 02, 21.3056%32410551E+03/ DATA BB / 1.02652821626751 E + 00, 9.29753107520368E + 03,
! 6.53848923630220E + 06, 2.89543295992889E + 08, 8.16836456953161E + 03, 3 4.12237656364399E+ 06/
DATA CC / 4.30952856710482E + 05, 8.27988256743362E +09, 1 2.41944468684445E + 12, 4.21722873236008E + 05, 7.56593802747116E + 09/ Vol. 2 Part 2 G-175 NUREG/CR-6143
l LOSP Frequency l DATA SLOG /-6.6774%76968273E+2/ ' DATA CON 14 / 3.32361913019165E+1/ DATA SCALE /1.E-35/ DATA ASCL /1.E-18/ l C IF(REL.LE.O.) GO TO 91 IF(N.LT.1) GO TO 92 IF(ALPilA.LE.O.0) GO TO 93 l NZ-0 l IF(X) 94,10,20 10 DO 111-1,N i 11 Y(I)=0. l RETURN C - C IP X.GE.XLIM(ALPIIA+N-1), TIIEN Y(K)=l., K-1,2,,N 20 NN= N RX-1./X l NBAR=0 l APN = ALPIIA + FLOAT (N)-1. AirTEST= APN AMl= ALPIIA 1. IF(APN.LE.I.) GO TO 22 21 IF(X.LE. APTT.ST) GO TO 40 IF(APTEST.GT.200.) GO TO 25 St = ((AA(1)*AITEST + AA(2))* APTEST + AA(3))* APTEST + AA(4) l S2=(AIFTEST+ AA(5))* APTEST + A's(6) GO TO 226 25 IF(APTEST.GT.10000.) GO TO 36 Sl = ((B B(1)* APTEST + BB(2))*AI TEST + B B(3))* APTEST + B B(4) S2=(APTEST + BB(5))*AFTEST+ BB(6) 226 XLIM =Sl/S2 C IF(X.GE.XLIM) GO TO 26 GO TO 35 36 Sl = ((APTEST + CC(l))* APTEST + CC(2))*AFTEST + CC(3) S2=(APTEST +CC(4))* APTEST + CC(5) GO TO 226 26 DO 27 I=l,N 27 Y(I)=1. RETURN C 22 IF(ALPilA.NE.I.) GO TO 32 IF(X.GT. CON 14) GO TO 26 IF(X.LT.O.1) GO TO 40 Y(NN)=1.-EXP( X) RETURN 32 NBAR-1 APTEST = APN +1. GO TO 21 35 NBAR =X-APTEST +5. + FLOAT (NBAR) 40 ABAR= APN + FLOAT (NBAR) XLOG = ALOG(X) Al-l. l NUREG/CR-6143 0 176 Vol. 2, Part 2
LOSP Freqwecy SUM -1. ABK- ABAR + 1. 80 Al - Al*X/ABK SUM = SUM + Al : IF(Al.LT.REL) GO TO 100 ABK= ABK+ 1. GO TO 80 100 YY= SUM
- SCALE D- ABAR IF(NBAR.EQ.0) GO TO I10 105 CONTINUE DO 106 K-1,NBAR XOD =X/D IF(XOD.LT.ASCL) GO TO 106 YY= XOD*YY + SCALE 106 D-D-l. ,
C , IF(NZ.NE.0) GO TO 114 110 E= -X +D*XLOG-GAMLN(D +1.) 114 IF(E.GE. SLOG) GO TO 120 Y(NN)=0 NZ=NZ+1 NN = NN-1 IF(NN.EQ.0) RETURN NBAR-1 APN - APN-1. ; E = E + ALOG(D*RX) l GO TO 105 l 120 EXE = EXP(E) Y(NN)=(EXE/ SCALE)*YY NMI-NN-1 IF(NMI.EQ.0) RETURN F = EXE*APN*RX KK=NN AK-FLOAT (NN) + AMI DO 125 K-1,NMI Y(KK-1)= Y(KK)+ F KK-KK-1 AK - AK-l. F = F*AK*RX 125 CONTINUE RETURN C 91 CAI.L ERRCHK(33,33HIN GAMIC, IMPROPER INPUT FOR REL.) RETURN 92 CALL ERRCHK(31,31HIN GAMIC, IMPROPER INPUT FOR N.) RETURN 93 CALL ERRCHK(35,35111N GAMIC IMPROPER INPUT FOR ALPHA.) RETURN 94 CALL ERRCHK(31,31HIN GAMIC, IMPROPER INPUT FOR X.) RETURN END FUNCTION G AMLN(X) Vol. 2, Part 2 G-177 NUREG/CR-6143
LOSP Frequency i C C WRTITEN BY D. E. AMOS, SEPTEMBER,1977. C C REFERENCES C SAND-77-1518 C C COMPUTER APPROXIMATIONS BY J.F. HART, ET.AL., SIAM SERIES IN , C APPLIED MATHEMATICS, WILEY,1968, P.135-136. ' C C NBS HANDBOOK OF MATHEMATICAL FUNCTIONS, AMS 55, BY C M. ABRAMOWITZ AND I.A. STEGUN, DECEMBER.1955, P.257. , C . C ABSTRACT C GAMLN COMPUTES THE NATURAL LOG OF THE GAMMA FUNCTION FOR C X.GT.O. A RATIONAL CHEBYSHEV APPROXIMATION IS USED ON C 8.LT.X.LT.1000 , THE ASYMPTOTIC EXPANSION FOR X.GE.1000. AND C A RATIONAL CHEBYSHEV APPROXIMATION ON 2.LT.X.LT.3. FOR C 0.LT.X.LT.8. AND X NON. INTEGRAL, FORWARD OR BACKWARD
)
, C RECURSION FILLS IN THE INTERVALS 0.LT.X.LT.2 AND C 3.LT.X.LT.8. FOR X = 1.,2..... ,100., GAMLN IS SET TO ; C HATURAL LOGS OF FACTORIALS. C C DESCRIPTION OF ARGUMENTS C ; C INPUT C X - X.GT.0 C C OUTPUT C GAMLN - NATURAL LOG OF THE GAMh.A FUNCTION AT X C C dRROR CONDITIONS C IMPROPER INPUT ARGUMENT - A FATAL ERROR C C C C. GAMLN USES SUBROUTINES ERRCHK, ERRGET, ERRPRT, ERXSET, ERSTGT C COMPILE DECKS GAMLN, ERRCHK DIMENSION GLN(100),P(5),Q(2),PCOE(9),QCOE(4) C i DATA XLIMI,XLIM2,RTWPIL/ 8.,'1000. ,9.18938533204673E-01/ DATA P / 7.66345188000000E-04,-5.94095610520000E-04, 1 7.93643110484500E-04,-2.77777775657725E-03, 8.33333333333169E-02/ , C I DATA Q /-2.77777777777778E-03, 8.33333333333333 E-02/ C DATA PCOE / 2.97378664481017E-03,9.23819455902760E-03, ! 1 1.09311595671044 E-01, 3.98067131020357E-01, 2.15994312846059E + 00, 2 6.33 ft06799938727E + 00, 2.07824725317921 E + 01, 3.60367725300248E + 01, 3 6.20038380071273E+0!/ C DATA QCOE / 1.00000000000000E + 00,-8.90601665949746E + 00, t 1 9.82252110471399 E + 00, 6.20038380071270E + 01/ C NUREG/CR-6143 G 178 Vol. 2, Pad 2 i
.-y, + , - y- I i.- ., ,-- w - -y-. c.w m ,
- _ - . __ - ~ _ . - . .
LOSP Frequency DATA (GLN(I),I- 1,60) / 2*0.0 , 6.93147180559945E-01, 1 1.79175946922806E + 00, 3.17805383034795E + 00, 4.78749174278205E + 00, 2 6.57925121201010E + 00, 8.52516136106541 E + 00,1.06046029027453 E + 01, 3 1.28018274800815 E + 01, 1.51044125730755 E + 01, 1.75023078458739 E + 01, 4 1.99872144956619E + 01, 2.25521638531234E + 01, 2.51912211827387E + 01, 52.78992713838409E + 01, 3.06718601060807E + 01, 3.35050734501369E + 01, 6 3.63954452080331 E + 01, 3.93398841871995E + 01, 4.23356164607535E + 01, . 7 4.53801388984769E + 01, 4. 84711813518352E + 01, 5.16066755677644E + 01, 8 5.47847293981123 E + 01, 5. 80036052229805E + 01, 6.12617017610020E + 01, 9 6.45575386270063E + 01, 6.78897431371815E + 01, 7.12570389671680E + 01, A 7.46582363488302E + 01, 7.80922235533153E + 01, 8.15579594561150E + 01, { B 8.50544670175815E + 01, 8. 85808275421977E + 01, 9.21361756036871 E + 01, C 9.571 %945421432E + 01, 9.93306124547874E + 01,1.02%8198614514E + 02, D 1.06631760260643E+02,1.10320639714757E+02,1.14034211781462E+02, l E 1.17771881399745E+02,1.21533081515439E+02,1.25317271149357E+02, F l.29123933639127E+02,1.32952575035616E+02,1.36802722637326E+02, G 1.40673923648234E + 02,1.44565743946345E + 02,1.48477766951773E + 02, 3 11 1.52409592584497E + 02,1.56360836303079E + 02,1.60331128216631 E + 02, ' I 1.64320112263195E + 02,1.68327445448428E + 02,1.72352797139163 E + 02, J 1.76395848406997E + 02,1.80456291417544E + 02,1.84533828861449E + 02/ : D ATA(G LN(I),I - 61,100)/ 1. 88628173423672E + 02, 1.92739047287845 E + 02, 1 1.96866 I 81672890E + 02, 2.01009316399282E + 02, 2.05168199482641 E + 02, ' i 2 2.09342586752537E + 02, 2.13532241494563E + 02, 2.17736934113954E + 02, 3 2.21956441819130E + 02, 2.26190548323728E + 02, 2.30439043565777E + 02, ! 42.34"/01723442818 E + 02, 2.38973389561834 E + 02, 2.43268849002983 E + 02, ! 5 2.47572914096187E+02,2.51890402209723E+02,2.56221135550010E+02, i 6 2.60564940971863 E + 02, 2.64921649798553E + 02, 2.69291097651020E + 02, 72.73673124285694E + 02, 2.78067573440366E + 02, 2. 82474292687630E + 02, a 2.86893133295427E +02,2.91323950094270E+02,2.95766601350761E+02 - 9 3.00220948647014 E + O2, 3.04686856765669E + 02, 3.09164193580147E + 02, i A 3.13652829949879E + 02, 3.18152639620209E + 02, 3.22663499126726E + 02, f B 3.271 S$287703775E + 02, 3.317178871%928E + 02, 3.36261181979198E + 02, ; C 3.40815058870799E + 02, 3.45379407062267E + 02, 3.49954118040770E + 02, ! D 3.54539085519441 E + 02, 3.59134205369575E + 02/ - C l IF(X) 90,90,5 SNDX=X T=X-FLOAT (NDX) ' IF(T.EQ.0.0) GO TO 51 DX=XLIMI X IF(DX.LT.O.0) GO TO 40 , C C RATIONAL CllEBYSHEV APPROXIMATION ON 2.LT.X.LT.3 FOR GAMMA (X) C NXM-NDX2 PX-PCOE(I) DO 10 !=2,9 10 PX-T*PX+PCOE(I) QX = QCOE(1) DO 15 I-2,4 15 QX-T*QX+ QCOE(I) DGAM = PX/QX IF(NXM.GT.0) GO TO 22 Vol. 2 Part 2 G-179 NUREG/CR-6143
LOSP Frequency IF(NXM.EQ.0) GO TO 25 C C BACKWARD RECURSION FOR 0.LT.X.LT.2 C DOAM = DGAM/(1. +T) IF(NXM.EQ.-1) GO TO 25 DGAM =DGAM/T GAMLN- ALOG(DGAM) RETURN C C FORWARD RECURSION FOR 3.LT.X.LT.8 C 22 XX = 2. +T DO 24 I-1,NXM DGAM = DG AM*XX 24 XX = XX + 1. 25 GAMLN= ALOG(DGAM) RETURN C C X.GT.XLIMI C 40 RX-1./X RXX-RX*RX IF((X XLIM2).LT.O.) GO TO 41 PX = Q(1)*RXX + Q(2) GAMLN= PX*RX+(X .5)*ALOG(X)-X + RTWPIL 1 RETURN I C i C X.LT.XLIM2 l C 41 PX-P(l) SUM =(X .5)*ALOG(X) X l DO 42 I-2,5 PX = PX*RXX + P(l) 42 CONTINUE l GAMLN= PX*RX + SUM + RTWPIL RETURN C C TABLE LOOK UP FOR INTEGER ARGUMENTS LESS TIIAN OR EQUAL 100. C 51 IF(NDX.GT.100) GO TO 40 GAMLN=GLN(NDX) RETURN 90 CALL ERRCllK(49,49111N GAMLN, ARGUMENT IS LESS THAN OR EQUAL TO ZERO 1.) RETURN END SUBRCUTINE GAMTL(X,B,REL,N.Y,NZ) C C WRITTEN BY D.E. AMOS AND S.L. DANIEL, OCTOBER,1974 i C l C REFERENCE SC-DR-72 0303 C NUREG/CR-6141 G 180 Vol. 2. Part 2
LOSP Frequency C ABSTRACT C GAMTL COMPUTES AN N MEMBER SEQUENCE OF COMPLEMENTARY C GAMMA FUNCTIONS C C Y(K)=l.-INCGAMMA(B +K-1,X)/ GAMMA (B +K-l), K-1,... N, C C TO A RELATIVE ERROR REL FOR X.GE.0 AND B.GT.O. THE CONTINUED C FRACTION IS EVALUATED FOR BO.GT.O., BO=B INTEGER PART OF C B, FOLLOWED BY FORWARD RECURSION ON ITS TWO TERM RELATION TO C RAISE BO TO B+N-l. THE CONVERGENCE IS BEST FOR LARGE C X .GE. MAX (1,BO). WHERE SPEED IS A CONSIDERATION, EVALUATE C Y(K) BY SUBTRACTING THE INCOMPLETE GAMMA FUNCTION FROM 1. C USING SUBROUTINE GAMIC FOR X.LT. MAX (1,B +K-1) AND GAMTL FOR C X.GE.M AX(1,B + K-1). C C DESCRIIrTION OF ARGUMENTS C C INPUT C X - ARGUMENT, X.GE 0.0 C B - PARAMETER, B.GT.0.0 C REL - RELATIVE ERROR REQUIREMENT, C REL=1.E-S FOR S SIGNIFICANT DIGITS,0.LE.S.LE.12 C N - NUMBER OF COMPLEMENTARY FUNCTIONS IN THE SEQUENCE C BEGINNING AT PARAMETER B, N.GE.1 C C OUTPUT C Y - A VECTOR CONTAINING AN N MEMBER SEQUENCE C Y(K)=1.-INCGAMMA(B + K-1,X)/GAMM A(B + K-l), K-1,... N C TO A RELATIVE ERROR REL. C NZ - UNDERFLOW FLAG C NZ.EQ.0, A NORMAL RETURN C NZ.NE.0, UNDERFLOW, Y(K)=0.0, K-1,NZ RETURNED. C C ERROR CONDITIONS C IMPROPER INPUT - A FATAL ERROR C CONTINUED FRACTION DOES NOT CONVERGE - A FATAL ERROR. C UNDERFLOW - A NON-FATAL ERROR. C j C C GAMTL USES SUBROUTINES GAMLN, ERRCHK, ERRGET, ERRPRT, ERXSET, C ERSTGT C COMPILE DECKS GAMTL, GAMLN, ERRCHK DIMENSION Y( 1) ! DIMENSION AA(6),BB(6),CC(6),DD(5) DATA AA / 1.68859588328389E + 00,1.46584889514920E + 03, 1 1.73155244984160E + 05, 2.30183328529532E + 06, 2.27877181874608E + 02, ! 2 3.47933198737331E + 03/ DATA BB / 1.25558472503917E + 00, 4.44539043255409E + 03, 1 2.40212910342450E + 06, 2.22905539488737E + 08, 1.84918400518640E + 03, 2 3.17776548571970E+05/ ' DATA CC / 1.09010860762347E + 00, 2.03790209154944E + 04, 1 4.60641404764333 E + 07,1.36803284952888E + 10,1.39702132796605E + 04, 21.59209661717833E+ 07/ Vol. 2, Part 2 G-181 NUREG/CR-6143
LOSP Frequency DATA DD / 4.68251145610753E+05,1.11348212926478E+ 10, . I 1.38713354995651E + 13, 4.29493174834810E + 05, 7.88439389479852E + 09/ DATA MAXR,W,SP250,5M250,A250/1280,632.5,1.E+35,1.E-35,
$5.75646273248511E+2/
DATA ELIM , RLIM/ 667. , l.E-12/ IF(N.LE.0) GO TO 91 IF(B.LE.O.0) GO TO 92 NZ-0 IP (X) 93,6,8 6 DO 7 J-1,N 7 Y(J) = 1. RETURN 8 CONTINUE IF(RELLT.RLIM) GO TO 94 C IF X.GE.XLIM(B+N 1), Y(K)=0., K-1,2,,N DUE TO UNDERFLOW C BPN = B + FLOAT (N)-l. BP1 EST= BPN BMI = B-1. IF(BPN.LE.I.) GO TO 11 IF(X LE.BWEST) GO TO 9 IF(BWEST.GT.200.) GO TO 12 Sl=((AA(1)*BPTEST+ AA(2))*BPTEST+ AA(3))*BI' TEST + AA(4) S2 =(BPTEST+ AA(5))*BPTEST+ AA(6) GO TO 15 12 IF(BirTEST.GT.1000.) GO TO 14 Sl = ((B B(1)* B PTEST + BB(2))*BirrEST + B P(3))*B PTEST + BB(4) S2=(BPTEST+ BB(5))*BPTEST+ BB(6) GO TO 15 14 IF(BPTEST.O f.10000.) GO TO 16 Sl = ((CC(l)*B PTEST + CC(2))*B PTEST + CC(3))*B PTEST + CC(4) S2=(BPTEST+ CC(5))*BPTEST+ CC(6) GO TO 15 16 Sl = ((Bl* TEST + DD(1))*B PTEST + DD(2))*SPTEST + DD(3) S2=(BPTEST+ DD(4))*BPTEST+DD(5) 15 XLIM-SI/S2 IF(X.GE.XLIM) GO TO 17 GO TO 9 17 DO 18 !=l,N 18 Y(I)=0-NZ=N RETURN 11 IF(X.LT.ELIM) 00 TO 9 GO TO 17 9 CONTINUE NU-B BO=B-FLOAT (NB) IF(BO) 10,10,20 10 BO=l. N B = N B-1 GBOPLX = 0. SCALE =0. R1 = X NUREO/CR-6143 G 182 Vol. 2 Part 2
LOSP Frequency GBX -1. GO TO 100 C C COMPUTE BIOGAM (BO,X) BY CONTINUED FRAC. TION C 20 KFLAG =0 NB AR = 10. + 1./(X + .01) 30 IF(NBAR.GT.MAXR) GO TO 95 RN Pl = 0. SN = NB AR +1 DO 21 J-1,NBAR SN- SN-l. RN = X +(SN-BO)*RNPl/(SN + RNPI) RNPl=RN 21 CONTINUE C IF(KFLAG.NE.0) GO TO 23 KFLAG=1 NBAR-NBAR+NBAR RSAVE= RN GO TO 30 C 23 RTEST= ABS ((RSAVE-RN)/RN) IF(RTEST.LE.REL) GO TO 40 RSAVE-RN l NBAR=NBAR4 NBAR GO TO 30 C 40 CONTINUE GBOPLX-BO*ALOG(X)-GAMLN(BO) SCALE = 0. Rl =1./BO GBX =1./RN 1 100 AJ = BO I ETERM --X + GBOPLX ) IF(NB.LE.0) GO TO 110 C C RAISE PARAMETER FROM BO TO B BY RECURSION l C IF TERM.GT.SP250 OR .LT.SM250, SCALE AND CONTINUE C 102 DO 105 K-1,NB , GBX = GBX + RI l AJ = AJ + 1. ! R1- Rl*X/AJ {
)
IF(R).LE.SP250) GO TO 104 R1= Rl*SM250 GBX-GBX*SM250 SCALE = SCALE + A250 l GO TO 105 104 IF(RI.GE.SM250) GO TO 105 Rl = Rl*SP250 l GBX = GBX*SP250 SCALE = SCALE A*.50 Vol. 2. Part 2 G-183 NUREG/CR-6143
LOSP Frequency 10S CONTINUE 110 CONTINUE GARG =ETERM + ALOG(GBX)+ SCALE IF(GARG.GT.-ELIM) GO TO 114 C ' C UNDERFLOW VALUES SET TO ZERO C NZ=NZ+1 Y(NZ)=0.0 IF(NZ.EQ.N) RETURN NB-1 GO TO 102 C C COMPUTATION OF Y(K) BY RECURSION C 114 IK=NZ+1 Y(IK)= EXP(GARG) IF(N.EQ.IK) RETURN IF(R).LE.0.0) GO TO 116 RI-EXP(ETERM + ALOG(RI) + SCALE) 117 KEND=N-1 DO 115 K=lK,KEND Y(K +1)= Y(K)+ R1 AJ = AJ + 1. R1 = Rl*X/AJ 115 CONTINUE RETURN 116 RI = 0. GO TO 117 C 91 CALL ERRCilK(31,31HIN GAMTL, IMPROPER INPUT FOR N.) RETURN 92 CALL ERRCHK(31,3111?N GAMTL, IMPROPER INPUT FOR B.) RETURN 93 CALL ERRCHK(31,31HIN GAMTL, IMPROPER INPUT FOR X.) RETURN 94 CALL ERRCHK(33,33HIN GAMTL, IMPROPER INPUT FOR REL.) RETURN 95 CALL ERRCHK(67,67111N GAMTL, CONTINUED FRACTION DOES NOT CONVERGE, IUSE I. INCGAMM A(X).) RETURN END FUNCTION FNORM(X,KODE,NZ) C C WRITTEN BY D.E. AMOS AND S.L. DANIEL, OCTOBER,1974 C C REFERENCE 3C-DR-72-0918
- C
! C ABSTRACT C FNORM COMPUTES THE CUMULATIVE NORM AL DISTRIBUTION F(X) OR C ITS COMPLEMENT 1.-F(X). CHEBYSHEV EXPANSIONS FOR ERF(Z) ON C 0.LE.Z.LT.2 AND ERFC(Z) ON 2.LE.Z.LE.4 AND Z.GT.4 ARE C USED FOR EVALUATION. THE RELATIONS NUREG/CR-6143 G-184 Vol. 2, Part 2
l LOSP Frequency C F(X)=.5*ERFC(Z) , Z--X/SQRT(2) , X.LT.-2.*SQRT(2) C F(X)=.5 .5*ERF(Z) , Z=-X/SQRT(2) ,-2*SQRT(2).LE.X.LT.0 C F(X)=.5 +.5+ERF(Z) , Z= X/SQRT(2) ,0.LE.X.LT.2*SQRT(2) C F(X)= 1. .5 +ERFC(Z) , Z-X/SQRT(2) , 2.LE.Z.LT.6 C F(X)=1. , X.GE.6*SQRT(2) C F( X)-1. F(X) , C ARE USED TO COMPLETE THE DEFINITION ON THE REAL LINE SO THAT C SIGNIFICANT DIGITS ARE RETAINED OVER THE FULL EXPONENT RANGE. C C DESCRIPTION OF ARGUMENTS ; C \ C INPUT .l C X ARGUMENT OF THE DISTRIBUTION C KOCE - A SELECTION PARAMETER C KODE-l RETURNS FNORM=F(X) C KODE=2 RETURNS FNORM-1.-F(X) C C OUTPUT C FNORM - ANSWER FOR F(X) OR 1. F(X) DEPENDING ON KODE. C NZ - UNDERFLOW FLAG C NZ-0, A NORMAL RETURN C NZ-1, UNDERFLOW, FNORM-0.0 RETURNED C C ERROR CONDITIONS C IMPROPER INPUT FOR KODE- A FATAL ERROR C UNDERFLOW - A NON FATAL ERROR, XLIM--36.5444845898331 IS THE C CRITICAL VALUE. C C C FNORM USES SUBROUTINES ERRCHK, ERRGET, ERRPRT, ERXSET, ERSTGT C COMPILE DECKS FNORM, ERRCHK DIMENSION Al(2J),A2(23),A3(17) DATA Al / 2.94268192595158E-01,-1.20794002859252E-01, 1-5.38155411612267E-03, 9.61245872309754 E-03,-1.56928442055175E-03, 2 3.13379686339925E-04,1.34539944432857E-04 -2.01886311941572E-06, 3 -6.02924420904726 E-06, 7.33514212717164 E-07, 1.68200375041707 E-07, 4-4.21496636122487 E-08,-2.34039537886964 E-09, 1.54397950861409 E49, 5 3,83910453258562E-11.-4.18791755643448F-11,3.66254323806330E-12, 6 8.67662501706706E-13,1.38490737068408E 13,-1,30609215123467E-14, 7 3.7o420840390550E 15/ C DATA A2 / 3.93098827656776E-01, O. 1-5.72072868438617E-03, 0.0 ,1.18630151591342E-os, 2 0.0 .-3.91103704629101E 06, 0.0 31.72795234431416E-07, 0.0 , 9.42361518118889E-09, 4 0.0 ,6.C4595735693237E-10, 0.0 5-4.42225118426537E-11, 0.0 , 3.607471531187I IE-12, 6 0.0 ,-3.22932023145379E-13, 0.0 7 3.13323522258447E-14, 0.0 ,-3.26302072101379E-15/ C DATA A3 / 2.66657721330163E-01, 8.94380310492471E-03, 1 1.90087646908402 E-03, 3.48555717528185 E-04,-5. 81844230476253 E-05, 2 9.06838380458210E-06,-1.33859970500872E 06,1.88850668170541E-07, Vol. 2, Part 2 G 185 NUREG/CR-6143
LOSP Frequency ) 3-2.56245596590501 E-08, 3.35935312400552E-09,-4.27010392442662E-10, 4 5.27726756655456E-11,-6.35545872359585E-12,7.47249710210314E '.3, ; 5-8.59121451944801E-14,9.67175305486972E-15,-1.0674133951597IE 15/ C DATA RTWO.TRTWO,FRTWO,SRTWO,XLIM/ 1 1.41421356237310E + 00, 2.82842712474619E + 00, 5.65685424949238E + 00, r 2 8.48528137423857E+00,-3.65444845898331E+01/ i C DATA Ni,N2 N3,MI,M2,M3/21,23,17,19,21,15/ C IF(KODE.LT.I.OR.KODE.GT.2) GO TO 900 NZ-0 GO TO (100,200),KODE 100 CONTINUE i XX=X 150 IF(XX.GE.XLIM) GO TO 102 FNORM = 0.0 NZ-1 RETURN 102 IF(XX.LT.SRTWO) GO TO 104 FNORM-10 RETURN 104 IF(XX.LE.FRTWO) GO TO 106 ASSIGN 110 TO ISET 1 107 CONTINUE , Z-FRTWO/XX TZ-Z+Z J= N2 Bl= A2(J) B2 - 0. DO 25 I=l M2 J =]-1 TEMP =B1 Bl=TZ*BI B2+ A2(J) B2= TEMP 25 CONTINUE ANS = Z*BI-B2 + A2(1) , FNORM-(EXP(-XX*XX*.5)/XX)*ANS GO TO ISET,(110,115) 110 FNORM-l.-FNORM 115 RETURN 106 IF(XX.GT.TRTWO) GO TO 112 IF(XX.LT.-TRTWO) GO TO 108 Z- ABS (XX)/RTWO-l. TZ-Z+Z J = N1 Bl= Al(J) ! B2-0. i l DO 45 !=1,MI J=J-l ' TEMP =BI l Bl=TZ*BI B2+ Al(J) ' B2= TEMP ( 45 CONTINUE i 1 NUREG/CR-6143 G-186 Vol. 2, Part 2 l
LOSP Frequency FNORM =XX*(Z*BI-B2 + Al(l)) + 0.5 RETURN ' 108 IF(XX.GT. FRTWO) GO TO 109 ASSIGN 115 TO ISET XX= XX GO TO 107 109 CONTINUE XS=-XX/RTWO 113 Z=XS 3. TZ = Z + Z J-N3 BI- A3(J) 1 B2 - 0. DO 36 I-1,M3 J=J-l
'TMP=Bl Bl=TZ*BI B2+ A3(J)
B2 = TEMP 36 CONTINUE , ANS = Z*BI-B2 + A3(1) FNORM = EXP(-XS*XS)*ANS/XS IF(XX.GT.O.0) FNGRM =1. FNORM RETURN 200 XX--X GO TO 150 112 XS = XX/RTWO GO TO 113 900 CALL ERRCIIK(34,34HIN FNORM, IMPROPER INPUT FOR KODE.) RETURN END Vol. 2, Part 2 G 187 NUREG/CR-6143
LOSP Frequency Attachnent G-41 GG.DAT i l i NUREG/CR-6143 G-188 Vol. 2, Part 2 l
1 l l LOSP Frequency TITLE
- TABE!/1,8.5,9.5,11,2,0 1.35 > RECOVERY CURVF 3 FOR GRAND GULF RETURN LOWER
- LH(E( 0.0000000E + 00, O.1000000E + 01,1 0.5000000E-01, 0.6332765E + 00 0.1000000E +00, 0.5221666E +00 0.1500000E +00, 0.4418805E +00 0.2000000E + 00, 0.3805399E +00 0.2500000B + 00, 0.3321897E + 00 0.3000000B +00, 0.2959414E + 00 0.3500000E + 00,0.2639019E + 00 0.4000000E+00,0.2377251,E +00 0.4500000E+00,0.2159356E+00 0.5000000E + 00, O.1979217E + 00 0.5500000E + 00, 0,1835196E + 00 0.6000000E + 00, O.1708331E + 00 0.6500000E + 00, O.1598593E + 00 0.7000000E +00, 0,1493906E + 00 0.7500000E +00, O.1405793E + 00 0.8000000E + 00, O.I333128E + 00 0.8500000E + 00, 0.1262909E + 00 0.9000000E + 00, O.1205451E + 00 0.9500000E + 00, O.I149577E + 00 0.1000000E + 01, 0.1102719E + 00 0,1050000B + 01, O.1056353E + 00 0.1100000E + 01, 0.1014440E + 00
- 0. I133000E +01, 0.9869112E-01 0.1200000E + 01, 0.9392024E 01 0.1250000E + 01, 0.8945530E 01 0,1283000E + 01, 0.8722764E-01 0.1333000B +01, 0.8405942E-01 0.1400000E+01,0.8031324E 01 0.1450000E + 01,0.7762612E-01 0.1500000E +01, 0.7501823E-01 0.1550000E + 01, 0.7281739E-01 0.1600000E + 01, 0.7047690E-01 0,1650000E + 01, 0.6827596E-01 0.1700000E + 01, 0.6635383E-01 0,1750000E + 01, 0.6447174E-01 0.I800000E + 01, 0.626790$E-01 0.1850000E + 01,0.6098870E-01 0.1900000E + 01, 0.5930665E-01 0.1950000E + 01, 0.5773523E-01 0.2000000E +01, 0.5629625E-01 0.2050000E +01, 0.550848IE 01 0.2100000E + 01,0.5343305E-01 0.2150000E + 01, 0.5228697E-01 0.2200000E + 01, 0.5091853E-01 ,
0.2250000E+01,0.4930571E41 0.2300000E + 01, 0.4812152E-01 0.23f'vX)0E + 01, 0.4712099E-01 0.240JU00E+01,0.4609329E-01 0.24500J0E + 01, 0.4509338E-01 Vo!. 2, Part 2 G-189 NUREG/CR4143
LOSP Frequency
- 0.2500000E + 01, 0.4413055E-01 0.2750000E+ 01, 0.3985612E-01 0.3000000E + 01, 0.3599319E-01 0.3167000E+01,0.3364090E-01 0.3500000B+01,0.2977570E 01 0.3750000B + 01, 0.2700900E-01 0.4000000E+ 01, 0.2464051E-01 O.4250000E +01, 0.2305845E 01 0.4500000E + 01, 0.2131568E-01 0.4750000E + 01, D.1970513E-01 0.5000000E +01, O.I842000E-01 0.5250000B + 01, O.1704338E-01 0.5500000E+01, O.1558531E 01 .
0.5750000E + 01, O.1451475E-01 ' O.6000000E + 01, O.1370299E-01 0.6250000E+01, O.128%71E-01 0.6500000E + 01, O.1204479E-01 I 0.6750000E + 01, O.I111974E-01 0.7000000E + 01, O.1035678E-01 0.7250000E + 01, 0.9655474E-02 0.7500000E + 01, 0.8968785E 02 0.7750000E + 01, 0.8355397E-02 0,8000000E + 01, 0.7840881E-02 0.8250000E + 01, 0.7255260E-02 i 0.C500000E+01,0.6714201E-02 0.8750000E + 01, 0.6235197E-02 0.9000000E + 01, 0.5782876E42 0.9250000E + 01, 0.54I 8809E-02 0.9500000E + 01, 0.5086483E-02 I 0.9750000E + 0I, 0.4756637E-02 I 0.1000000E + 02, 0.443229dE-02 0.1330000E + 02, 0.1716932E-02 0.1500000E + 02, O.1068773E-02 i 0.1600000E + 02, 0.7913224E-03
- 0. I800000E + 02, 0.4602075E 03 ,
0.2300000E + 02, O.I144893E-03 4 0.2700000E +02, 0.4291907E-04.2 RETURN MEDIAN
- l INE( 0.0000000E + 00, O.1000000E + 01,1 !
0.5000000E-01, 0.7463541E + 00 l 0.1000000E + 00, 0.6327068E + 00 0.1500000E + 00, 0.5513938E + 00 0.2000000E + 00, 0.4899929E + 00 0.2500000E + 00, 0.4406971E+ 00 ' O.3000000E + 00, 0.4001229E + 00 0.3500000E + 00, 0.3628054E + 00 0.4000000E + 00, 0.3333218E + 00 0.4500000E + 00, 0.3073997E + 00 0.5000000E + 00, 0.2850477E + 00 0.5500000E + 00, 0.2652728E + 00 0.6000000E + 00, 0.2483225E + 00 0.6500000E + 00, 0.2333687E + 00 0.7000000E +00, 0.2203711E + 00 0.7500000E + 00, 0.2097112E + 00 NUREG/CR 6143 G 190 Vol. 2, Part 2
%^
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l 1 LOSP Frequency 0.8000000E + 00, O.1992576E + 00 0.8500000E + 00, O.1902534E + 00 0.9000000E + 00, O.I825861E +00 0.9500000E +00, 0.1743934E+00 J 0.1000000E + 01, 0.1675142E + 00 ; 0.1050000E+ 01, 0.16163%E +00 0.I100000E+01, O.155%24E + 00 i 0.1133000E+01,0.1521893E+00 i 0.1200000E +01, 0.1468140E +00 0.12500dCE +01, 0.1425016E + 00 0.1283000E +01, 0.1393100E + 00 0.1333000E +01, O.1357623E +00 0.1400000E +01, 0.1306901E + 00 0.1450000E +01, O.1270454E + 00 0.1500000E +01, O.1232989E + 00 0.1550000E + 01, 0.1200562E + 00 0.1600000E + 01, O.I172448E + 00 0.1650000E +01, 0.1145043E+00 0.1700000E + 01, 0.1116334E +00 0.1750000E +01, O.1090089E + 00 0.1800000E + 01, 0.1066669E + 00 0.1850000E + 01, 0.1041265E+ 00 0.1900000E+01, O.1020300E+00 0.1950000E +01, 0.9953812E-01 0.2000000E +01, 0.9761813E-01 0.2050000E+01,0.9561905E-01 0.210000)C.+ 01, 0.9363572E-01 0.2150000E+ 01, 0.9173092E-01 0.230000E + 01, 0.8988579E-01 0.2250000E +01, 0.8837061E OI 0.2360000E + 01, 0.8693677E-01 0.2350000E + 01, 0.8543687E-01 O.2400000E +01, 0.83%951E-01 0.2450000E + 01, 0.8256046E-01 0.2500000E +01, 0.8126954E-01 0.2750000E+ 01, 0.7452092E-01 0.3000000E +01, 0.6894428E-01 0.3167000E+01,0.6517899E4)1 0.3500000E + 01, 0.5970375E-01 0.3750000E +01, 0.5649908E-01 0.4000000E +01, 0.5294258E-01 0.4250000E+ 01, 0.4993482E-01 0.4500000E+01, 0.4706598E-01 0.4750000E+01, 0.4466926E-01 0.5000000E +01, 0.4245387E-01 0.5250000E + 01, 0.4051010E-01 0.5500000E + 01, 0.3881580E-01 ; 0.5750000E +01, 0.3692094E-01 0.6000000E +01, 0.3515644E-01 0.6250000E + 01, 0.3354414E-01 0.6500000E + 01, 0.3214720E-01 0.5750000E + 01, 0.3076831E-01 ; 0.7000000E + 01, 0.2945143E-01 j 0.7250000E + 01, 0.2812898E-01 0.7500000E+01,0.2681594E 01 Vol. 2, Part 2 G-191 NUREG/CR-6143 , l 1
LOSP Frequency 0.7750000E + 01, 0.2568585E-01 0.80000 DOE +01,0.2471176E-01 0.8250000E+01,0.2344669E-01 0.8500000E +01, 0.2230225E-01 0.8750000E +01,0.2121469E-01 0.9000000E+01,0.2026050E 01 0.9250000E + 01, 0.1950373E-01 0.9500000E +01, 0.1871312E-01 0.9750000E+01, 0.1803369E-01 0.1000000E +02, 0.1727138E-01 0.1330000E +02, 0.1065451E41 0.1500000E+ 02, O.2241972E-02 0.1600000B+02, 0.70VJ074E-02 0.1800000E +02, 0.530271'tE-02 0.2300000E +02, 0.2524897E-02 0.2700000E +02, 0.1405742E-02,2 ETURN UPPER *
- LINE( 0.0000000E + 00, 0.10000WE + 01,1 0.5000000E-01, 0.8269160E + 00 0.1000000E +00, 0.7265984E +00 0.1500000E +00, 0.6552023E+ 00 0.2000000E+00,0.6002278E+00 0.2500000E + 00, 0.5536128E +00 0.3000000E+ 00, 0.5119509E + 00 <
0.3500000E +00, 0.4762957E + 00 ' O.4000000E +00, 0.4432515E + 00 0.4500000E ! 00,0.4168997E+00 0.5000000E + 00, 0.3915053E +00 0.5500000E+00, 0.3703218E +00 0.6000000E +00, 0.349771BE + 00 0.6500000E+00,0.3334318E+00 0.7000000E+00, 0.3173733E + 00 0.7500000E +00, 0.3034671E + 00 0.8000000E +00, 0.2909432E + 00 0.8500000E+00, 0.2791729E + 00 0.9000000E+00, 0.2671401E+00 > 0.9500000E +00, 0.2573200E +0J 0.1000000E + 01, 0.2478499E +00 0.1050000E + 01, 0.2388053E+00 ' O.1100000E + 01, 0.2307131E + 00 0.1133000E+01, 0.2259223E + 00 0.1200000E + 01, 0.2174941E +00 0.1250000E+01, 0.2112151E+ 00 0.1283000E + 01, 0.2075935E +00 l 0.1333000E+01, 0.2024275E +00 0.1400000E+01,0.1960352E+00 0.1450000E + 01, 0.1915764E+ 00 0.1500000E+01, 0.1879017E + 00 0.1550000E+01, 0.1843548E+ 00 , 0.1600000E + 01, 0.1809978E +00 0.1650000E + 01, 0.1770544E + 00 s 0.1700000E+01, 0.1745154E +00 ' O.1750000E + 01, 0.1718642E + 00 0.1800000E + 01, 0.1693036E + 00 j NUREO/CR-6143 G-192 Vol. 2, Part 2
l LOSP Frequency 0.1850000B +01, 0.1652479E+00 0.1900000E +01, 0.1621052E +00 0.1950000E +01, 0.1594075E + 00 0.2000000E+01, 0.1562051E +00 0.2050000E +01, 0.1529781E +00 0.2100000E +01, 0.1505008E +00 0.2150000E +01, 0.1481019E + 00 0.2200000E + 01,0.1457740E + 00 0.2250000E + 01, O.1435089E +00 j 0.2300000E + 01, O.1412663E+00 1 0.2350000E 4 01,0.1389527E+00 0.2400000E + 01, 0.1368531E+ 00 0.2450000E + 01, 0.1348111E +00 0.2500000E + 01, 0.1328239E + 00 0.2750000E+01, 0.1253677E +00 0.3000000E+ 01, 0,1184479E + 00 0.3167000E+01, 0.1137395E + 00 0.3500000E +01, 0.1056090E + 00 0.3750000E + 01, 0.9%8156E-01 ; 0.4000000E+01, 0.9447845E-01 0.4250000E +01, 0.9048945E-01 0.4500000E + 01, 0.8682710E-01 0.4750000E +01, 0.8340991E-01 ; 0.5000000E + 01, 0.8040784E-01 0.5250000E + 01, 0.7825368E-01 0.5500000E + 01, 0.7641406E-01 0.5750000E+01, 0.7468758E-O'. 0.6000000E+01, 0.7307281E-01 0.6250000E+01,0.7154985C-01 l 0.6500000E+01, 0.7011337E-fil i ; 0.6750000E+01, 0./821700F 41 , 0.7000000E + 01, 0.6626640E-01 l 0.7250000.E +01,0.6491457E-01 0.7500000E + 01, 0.6326144E-01 0.7750000E +01, 0.6150336E-01 0.8000000E +01, 0.5973991E-01 0.8250000E +01, 0.5795457E-01 0.8500000E +01, 0.5645822E-01 0.8750000E+01, 0.5527582E-01 0.9000000E +01, 0.5412262E-01 0.9250000E +01, 0.5270466E-01 0.9500000E+ 01, 0.5174899E-01 t 0.9750000E + 01, 0.5086838E-01 0.1000000E +02, 0.4984432E-01 0.1330000E+02, 0.3822363E-01 0.1500000E+02, 0.3366899E-01 0.1600000E+ 02,0.3180100E-01 0.1800000E + 02, 0.2834608E-01 0.2300000E +02, 0.2041070E-01 0.2700000E + 02, 0.1534511E-01.2 RETURN Vol. 2, Pad 2 G 193 NUREG/CR-6143 1
LOSP Frequency I l 6 1 1
)
i Attachment G-42 i COMMEAN.FOR ! l i l i NUREG/CR-6143 G-194 Vol. 2, Part 2 i
LOSP Frequency l PROGRAM COMMEAN C COMPUTE MEAN FOR EACH TIME STEP PRODUCED BY ' MOD'dL'. I' C 'MODEL' NAMES THE PLOT FILE ' plant name'.DAT. THAT NAME IS C CHANGED TO MAP.DAT SO THAT RMAPPER CAN BE USED WITHOUT CHANGE. C THIS PROGRAM PRODUCES A PLOT FILE, 'MEAN.DAT', THAT IS USED C IN THE CONTROL STREAM IN ' UPPER.DAT'. . C TO GET A, PLOT: j C - MAPPER device name C 'Ihe mponse to ENTER OPTIONS is C != UPPER.DAT PARAMETER (NOT= 88) DIMENSION XVAMNOT,3),XMEAN(NOT),Tild(NOT),EF(NOT) CHARACTER UNE*80 OPEN (10, FILE = 'M AP.DAT',READONLY, STATUS = 'OLD') OPEN (12, FILE = 'LOGNORM AL.DAT', STAT US = 'NEW') OPEN (13, FILE = 'M EAN.D AT', STATUS = 'Nt3W') DO1I-1,NOT 1 XMEAN(I)=0. DO 2 M-1,5 READ (10,'(A)')UNE WRITE (13,'(A)')LINE 2 CONTINUE DO 50 J- 1,3 READ (10,11) TIM (1),XVAMI,J) , 11 FORMAT (6X,E14.3,1X,E14.3) DO 101-2,NOT READ (10,*) TIM (I),XVA41,J) TYPE *, TIM (I),XVAL(I,J) 10 CONTINUE READ (10,'(A)')LINE READ (10,'(A)',END = 99) 50 CONTINUE C COMPUTE ERROR FACTOR 60 DO 100 I-1,NOT IF(XVAMI,1).EQ.0)THEN TYPE *,1 ENDIF EF(I)= XVAL(I 2)/XVAMI,1) XM EAN(I) = XVAMI,2)*EXP( ~ LOG (EF(I)))* *2/5.42) 100 CONTINUE WRITE (12.110) 110 FORMAT (' TIME ',' EF , MEAN ') DO 120 l=1,NOT WRITE (12,1 1 1) TIM (I), EF(l),X M EAN(I) 111 FORM AT(F8.2,4X,4 X,F4.1.4X,lPE 12.3) 113 FORM AT('SLINE(',E 14.3,',*,E 14.3,', l ') 113 FORM AT(E14.7,',,E14.7) 114 FORM AT(E14.3,',',E14.3,*,2') IF(I.EQ.1) WRITE (13,112) TIM (I),XMEAN(I) ; IF(I.EQ.NOT)THEN WRITE (13,114) TIM (I),XMEAN(I) GO TO 120 ENDIF WRITE (13,1I3) TIM (I),XMFAN(I) 120 CONTINUE WRITE (13,Il5) 115 FORMAT (* RETURN') l STOP 1 99 GO TO 60 ) [ END l Vol. 2, Part 2 G-195 NUREG/CR-6143
LOSP Frequency i I l l I l l j Attachment G-43 ! LOGNORMAL.DAT NUREG/CR-6143 G 196 Vol. 2, Past 2
LOSP Frequency TIME EF MEAN TIME EF MEAN 0.00 1.0 1.000E+ 00 3.00 1.9 7.453E-02 0.05 1.2 7.501E-01 3.17 1.9 7.066E-02 0.10 1.2 6.370E-01 3.50 2.0 6.528E-02 0.15 1.2 5.564E-01 3.75 2.1 6.247E 02 0.20 1.3 4.958E-01 4.00 2.1 5.898E42 0.25 1.3 4.472E 01 4.25 2.2 5.575E 02 0.30 1.4 4.069E-01 4.50 2.2 5.284E-02 0.35 1.4 3.697E 01 4.75 2.3 5.054E-02 0.40 1.4 3.404E-01 5.00 2.3 4.828E-02 0.45 1.4 3.146E-01 5.25 2.4 4.652E-02 0.50 1.4 2.921E-01 5.50 2.5 4.526E-02 0.55 1.4 2.720E 01 5.75 2.5 4.336E-02 0.60 1.5 2.548E-01 6.00 2.6 4.141E-02 ) 0.65 1.5 2.396E-01 6.25 2.6 3.970E-02 { 0.70 1.5 2.266E-01 6.50 2.7 3.840E-02 O.75 1.5 2.160E-01 6.75 2.8 3.725E-02 0.80 1.5 2.053E-01 7.00 2.8 3.603E-02 0.85 1.5 1.962E-01 7.25 2.9 3.474E-02 0.90 1.5 1.885E-01 7.50 3.0 3.346E-02 0.95 1.5 1.801E-01 7.75 3.1 3.242E-02 1.00 1.5 1.730E-01 8.00 3.2 3.151E 02 1.05 1.5 1.67IE-01 8.25 3.2 3.022E-02 1.10 1.5 1.614E-01 8.50 3.3 2.910E-02 1.13 1.5 1.575E-01 8.75 3.4 2.798E-02 1.20 1.6 1.523E-Ol' 9.00 3.5 2.'iO8E-02 1.25 1.6 1.483E-01 9.25 3.6 2.640E-02 1.28 1.6 1.451E-01 9.50 3.7 2.559E-02 1.33 1.6 1.416E-01 9.75 3.8 2.503E-02 1.40 1.6 1.365E-01 10.00 3.9 2.430E-02 1.45 1.6 1.329E-01 13.30 6.2 1.970E-02 1.50 1.6 1.290E-01 15.00 7.7 1.780E-02 1.55 1.6 1.257E-01 16.00 8.8 1.682E-02 1.60 1.7 1.230E-01 18.00 11.5 1.597E-02 1.65 1.7 1.203E-01 23.00 22.1 1.476E-02 1.70 1.7 1.173E-01 27.00 32.8 1.328E-02 1.75 1.7 1.147E-01 1.80 1.7 1.124E-01 1.85 1.7 1.098E-01 1.90 1.7 1.077E-01 1.95 1.7 1.051E-01 2.00 1.7 1.032E-01 2.05 1.7 1. OllE-01 2.10 1.8 9.923E-02 2.15 1.8 9.724E-02 2.20 1.8 9.540E-02 2.25 1.8 9.410E-02 2.30 1.8 9.273E-02 2.35 1.8 9.120E-02 2.40 1.8 8.973E-02 2.45 1.8 8.832E-02 2.50 1.8 8.706E-02 2.75 1.9 8.010E-02 Vol. 2, Part 2 G-197 NUREG/CR-6143 i
. --_ - - - - _ - - l
l l LOSP Pnquency Attachment G-44 LHS Input File: LOSP.EKI NUREG/CR-6143 G-198 Vol. 2, Part 2
l LOSP Frequency
$ Developed 9/8/93
$ UIS and UISPOST Keywords for LOSP CF UISTITL RLOSP SAMPLE FOR LEVELI UUOBS 500 LHSPEED1 U1SPVAL 1 LHSMSG C:\LPS\POSS\LOSP.LMO l UISOUT C:\LPS\POS$\LOSP.LSP 1 LHSPOST C:\LPS\POSS\LOSP.MSP DATASET:
RNLOSP 250 UNIFORM 1.0 500.9999 PNTLOSP 250 - INT ( RNLOSP ) LAMDG 2.OE 3 LOGNORMAL 2.OE-310 LAM-DG 2.OE LAMDG PNRDGDG2 0.87 MAXIMUM ENTROPY O.087 0.871.0 PNR-DG2 0.87 = PNRDG2 PNRDG3 0.80 MAXIMUM ENTROPY 0.08 0.801.0 PNR-DG3 0.80 - PNRDG3 PNRDG35 0.9 MAXIMUM ENTROPY 0.0775 0.7751.0 PNR-DG35 0.775 = PNRDG35 PNRDG5 0.7 MAXIMUM ENTROPY 0.07 0.71.0 PNR-DG5 0.7 - PNRDG5 PNRDG6 0.65 MAXIMUM ENTROPY 0.065 0.651.0 PNR-DG6 0.65 = PNRDG6 PNRDGil 0.48 MAXIMUM ENTROPY 0.048 0.481.0 PNR-DGil 0.48 = PNRDGil PNRDG14 0.41 M AXIMUM ENTROPY 0.0410.41 1.0 PNR-DG14 0.41 = PNRDG14 PNRCMDG2 0.77 MAXIMUM ENTROPY 0.077 0.771.0 PNRCM-DG2 0.77 - PNRCMDG2 PNRCMDG3 0.70 MAXIMUM ENTROPY 0.07 0.701.0 PNRCM-DG3 0.70 = PNRCMDG3 PNRCMDG35 0.675 MAXIMUM ENTROPY 0.0675 0.6751.0 PNRCM-DG35 0.675 = PNRCMDG35 PNRCMDG5 0.6 MAXIMUM ENTROPY 0.06 0.61.0 PNRCM-DG5 0.6 = PNRCMDG5 PNRCMDG6 0.55 MAXIMUM ENTROPY 0.055 0.551.0 PNRCM-DG6 0.55 = PNRCMDG6 PNRCMDGil 0.29 MAXIMUM ENTROPY 0.029 0.291.0 PNRCM-DGli 0.29 - PNRCMDGil PNRCMDG14 0.24 MAXIMUM ENTROPY 0.024 0.241.0 PNRCM-DG14 0.24 = PNRCMDG14 Vol. 2, Part 2 G-199 NUREG/CR-6143
- s
LOSP Frequency ;
.t r
Attachment G-45 FORTRAN Program: RLOSP NUREG/CR-6143 G.200 Vol. 2, Part 2
LOSP Frequency PROGRAM RLOSP C PARAMETER (NPT= 86, NOBS-500, NLHS=500, NTIME=7, NVARl=7, NVAR2=7) CHARACTER *10 NAME INTEGER IN, OUT,0UTI,0UT2,0UT3,0UT4 EXTERNAL EQ2 DOUBLE PRECISION TSTR1,TM.TCD,LAMDG,TCDVEC(NTIME), TEND DOUBLE PRECISION H,HMIN.HMAX,EMIN,EM AX,TPRCV(NPT), XINTRP DOUBLE PRECISION VPDGl(NVARI), VPDG2(NVAR2), LDGPTE DOUBLE PRECISION CFl(NTIME),CF2(NTIME),CF3(NTIME),CF4(NTIME) - DOUBLE PRECISION PNRMN(NPT),PNRDAT(NOBS,NPT), PRCV(NPT,2) DOUBLE PRECISION X, XCTCC(NTIME), XMNTCD(NTIME) DOUBLE PRECISION T, TCTCD(NTIME), TMNTCD(NTIME) COMMON /VSETl/ TCD, LAMDG COMMON /PRDATA/ PRCV, NTIMPT COMMON /INOUT/ IN, OUT DATA IN2,IN3/8,9/ DATA OUT1,0UT2,0UT3,0UT4/ll,12,13,14/ D ATA TCDVEC/2.0, 3.0, 3.5, 5.0, 6.0,11.0,14.0/ NTIMPT = NIrr IN = 7 OUT = 10 C C INPUT FILES C OPEN(UNIT =IN2, STATUS ='OLD*, FILE ='C:\F77L3\LPSFOR\LOSP.MSP') OPEN(UNIT =IN3, STATUS ='OLD', FILE ='C:\F77L3\LPSFOR\RLOSPCUR.LPS') C C OUTPUT FILES C OPEN(UNIT = OUT, FILE = 'C:\F77L3\LPSFOR\RLOSP.OUT') OPEN(UNIT = OUTI, FILE = 'C:\F77L3\LPSFOR\CFl.OUT') OPEN(UNIT = OUT2, FILE = 'C:\F77 L3\LPSFOR\CF2.OUT') OPEN(UNIT =OUT3, FILE ='C:\F77L3\LPSFOR\CF3 OUT') OPEN(UNIT = OUT4, FILE = 'C:\F77L3\LPS FOR\CF4.OUT') C INITIALIZE VARIABLES TSTRI - 0.0 ; TEND = 24.0 LAMDG = 2.OD-03 LDGPTE = LAMDG C TOLERANCES FOR INTEGRATION HMIN = 3D-7 HMAX = 20.0 EMIN = 0.0 EMAX = ID-4 ITMAX = 1000000 i C======================================================= l Vol. 2, Part 2 G-201 NUREG/CR-6143 1
LOSP Frequency C READ INPUT FILE READGN3,*)NCURVE,lMAX C CHECK TO MAKE SURE DIMENSIONS ARE CORRECT IF(NPT .NE. IMAX + 1)THEN WRITE (OUT,920) 920. FORMAT (IX,' ERROR: NUMBER OF POINTS (IMAX) EXCEEDS DIMENSION *) STOP ELSEIF(NOBS .NE. NCURVE)THEN WRITE (OUT,921) 921. FORMATGX,' ERROR: NUMBER OF POWER CURVES EXCEEDS DIMENSION') STOP ENDIF READ (IN3, *)(TPRCV(J + 1),J - 1,IM AX)
)
TPRCV(1) = 0.0 READGN3,*)(PNRMN(J + 1),J =1,IM AX) PNRMN(I) = 1.0 DO 65 I = 1, NCURVE READ (IN3,*)(PNRD AT(1,J + 1),J = 1,1M AX) PNRDAT(1,1) = 1.0 CONTINUE C READ LHS FILE ' C ICHK = 1 1 IFGCHK.EQ.1)THEN READ (IN2,801.END = 999)NAME 801 FORM AT(IX,A10) IF(NAME.EQ.'SAMPLEDATA')lCIIK = 0 GOTO1 ENDIF C j C SELECT MEAN POWER NON-RECOVERY CURVE ' C DO 701=1,NPT PRCV(I,1) = TPRCV(I) PRCV(I,2) = PNRMN(I) 70 CONTINUE i DO 85 L2 = 1,NTIME TM = TEND ; TCD = TCDVEC(L2) l C C CALL INTEGRATION SUBROUTINE C C IFLAG = 0; SUCCESSFUL PROCEDURE C IFLAG = 1: H OUT OF RANGE C IFLAG = 2: H OUT OF RANGE AT ENDPOINT C IFLAG = 3; MAXIMUM NUMBER OF ITERATIONS REACHED C C INITIAL CONDITIONS FOR INTEGRATION NUREG/CR-6143 G-202 Vol. 2, Part 2
i i LOSP Frequency X = 0.0 1 T =TSTRI j H = 0.1 i I CALL RK45AD(EQ2 T,X,H,TM,lTMAX,EMIN,EMAX,HMIN,HMAX,IFLAG) XMNTCD(L2) = X l TMNTCD(L2)= T 85 CONTINUE j WRITE (OUT,940) 940 FORMAT (IX,'CF2 WITHOUT DENOMINATOR FOR MEAN CURVE') i 1 WRITE (OUT,950)(TCD VEC(I),1 = 1,NTIM E) 950 FORMAT (IX,7(IX,' TIME *,F4.1,1X),/lX) WRITE (OUT,95 I)(XM NTCD(I),1 - 1,NTIM E) 951 FORMAT (IX,7(IX,lPE10.3)) C C WRITE OUTPUT FILE HEADER c WRITE (OUTI,942) i 942 FORMAT (IX,'CFl: POWER NON-RECOVERY CURVES') WRITE (OUTI,950)(TCDVEC(I),1=1,NTIME) WRITE (OUT2,944) 944 FORMAT (IX,'CF2: LOSP AS 1.E: D ~ FAILS TO RUN') WRITE (OUT2,950)(TCDVEC(I),I-1,NTIME) WRITE (OUT3.946) 946 FORMAT (IX,'CF3: LOSP AS I.E: DG FAILS TO START') WRITE (OUT3,950)(TCDVEC(I),1=1,NTIME) WRITE (OUT4,948) 948 FORMAT (IX,'CF4: LOSP AS !.E: DG FAILS TO START COMMON MODE *) WRITE (OUT4,950)(TCDVEC(I),1 - 1,NTIM E) C LHS LOOP C DO 30 Ll = 1,NLHS READ (IN2,*)DUM I,D UM 2,LHSPNT, LAM DG ,(VPDGl(I),1 = 1,NV ARI), l l
+ (VPDG2(I),1 =1,NVAR2)
C C SELECT APPROPRIATE PO%tR NON-RECOVERY CURVE C DO 75 I-1,NPT PRCV(I,1) = TPRCV(I) PRCV(I.2) = PNRDAT(LHSPNT,1) 75 CONTINUE ' C PERFORM CALCULATIONS FOR EACH CORE DAMAGE TIME C DO 80 L2 - 1,NTIME TM = TEND TCD = TCDVEC(L2) C CASE 1: CF = NON RECOVERY CURVES CFl(L2) = XINTRP(TCD,PRCV,NPT) C C CASE 2: CF = LOSS OF OFFSITE POWER AS 1.E.: DG FAILS TO RUN C C CALL INTEGRATION SUBROUTINE C INITIAL CONDITIONS FOR INTEGRATION C X = 0.0 T = TSTRI H = 0.1 CALL RK45AD(EQ2,T,X,11,TM,ITM AX,EMIN,EM AX,HMIN,IIM AX,lFLAG) XCTCD(L2) = X Vol. 2, Part 2 G-203 NUREGICR4143
LOSP Frequency . TCTCD(L2) - T CF2(L2) - X/(1.0-DEXP( LDGPTE*TM)) C C CASE 3: CF - LOSS OF OFFSITE POWER AS I.E.: DG FAILS TO START CF3(L2) - CFl(L2)*VPDGl(L2) C C CASE 4: CF - LOSS OF OFFSITE POWER AS I.E.: DG FAILS TO START COMMON MODE CF4(L2) = CFl(L2)*VPDG2(L2) C 80 CONTINUE C ' C . WRITE OUTPUT TO FILE I C WRITE (OUTI,951)(CFl(I) I-1,NTIME) WRITE (OUT2,951)(CF2(I),I - 1,NTIM E) WRITE (OUT3,951)(CF3(I),I = 1,NTIM E) WRITE (OUT4,95 l)(CI-4(1),I - 1,NTIM E) C C WRITE (OUT,952)TCDVEC(l),TCTCD(1),XCTCD(1),IFLAG l C 952 FORM AT(IX.2X,F6.2,2X,F6.2,5X,lPE 10.3,6X,II) 30 CONTINUE , STOP 999 . WRITE (9,910) , 10 FORMAT (IX,' ERROR - END OF FILE REACHED') 1 STOP END C FUNCTION EQ2 C--------------------------------- C FUNCTION USED TO EVALUATE CASE 2: LOSP I.E & DG PAILS TO RUN DOUBLE PRECISION FUNCTION EQ2(1,X) DOUBLE PRECISION T X, XINTRP DOUBLE PRECISION TCD, LAMDG DOUBLE PRECISION TRCV, PRCV, PNR COMMON IVSETl/ TCD, LAMDG COMMON /PRDATA/ PRCV(86,2),NTIMPT TRCV = T + TCD ! PNR - XINTRP(TRCV,PRCV,NTIMPT) EQ2 = LAMDG*DEXP(-LAMDG*T)*PNR RETURN END C ADAPTATIVE STEPPING ROUTINE FOR RUNGE-KUTTA C-------------------------------==--------------------- SUBROUTINE RK45AD(F,T,X,H TB,ITM AX,EMIN,EM AX,HMIN,HM AX,lFLAG) EXTERNAL F DOUBLE PRECISION F T,X,H,TB,EMIN,EMAX,HMIN HMAX DOUBLE PRECISION EPSI,DT,XSAVE,TSAVE,EST INTEGER IN, OUT COMMON /INOUT/ IN, OUT NUREG/CR-6!43 G-204 Vol. 2, Part 2
i LOSP Frequency DATA EPSI/0.5D-10/ IFLAG = 3 NSTEP = 0 2 DT = DABS (TB -T) IF(DT .GT. DABS (H)) GOTO 3 IFLAG = 0 IF(DT .LE. EPSl*DMAXI(DABS (TB), DABS (T))) RETURN H = DSIGN(DT,H) IF(HMIN .LE. DABS (H) .AND. DABS (H) .LE. HMAX) GOTO 3 IFLAG =2 RETURN 3 XSAVE - X TSAVE = T CALL RK45(F,T,X,H,EST) NSTEP = NSTEP + 1 IF(NSTEP .GT. ITM AX .OR. IFLAG .EQ. 0) RETURN IF(EST .LT. EMIN) GOTO 4 IF(EST .LE. EMAX) GOTO 2 H = 0.5*H GOTO5 4 H = 2.0*H 5 X = XSAVE T = TSAVE IF(HMIN .LE. DABS (H) .AND. DABS (H) .LE. HMAX) GOTO 2 IFLAG = 1 RETURN END C======================================================= C RUNGE-KUTTA INTEGRATION ROUTINE C======================================================= SUBROUTINE RK45(F,T,X,H EST) C EXTERNAL F DOUBLE PRECISION F,T,X,H,EST DOUBLE PRECISION C21,C31,C32,C41,C42,C43,C51,C52,C53,C54 DOUBLE PRECISION C61,C62,C63,C64,C65,Al,A3,A4,A5 DOUBLE PRECISION BI,B3,B4,B5,B6,C40,F1,F2,F3,F4,FS,F6,XS DATA C21,C31,C32,C41 C42,043,C51,CS2,C53,C54,
+ C61,C62,C63,C64,C65, Al, A3, A4, A5,BI,B3,B4,B5,B6, C40
+ /0.25,0.09375,0.28125,
+ 0.87938097405553,-3.27719617660446,3.32089212562585
^ 2.0324074074074,-8.0,7.17348927875244,0.20589668615984,
+ -0.2%2%2962963,2.0,-1.38167641325536,0.45297270955166,-0.275,
+ 0.11574074074074,0.54892787524366,0.5353313840156,-0.2,
+ 0.I1851851851852,0.51898635477583,0.50613149034201,-0.18,
+ 0.0363636363636364,0.92307692307692/
Fl= H'F(T,X) F2= H'F(T+0.25'H, X + C21*F1) F3- H'F(T+0.375*H, X + C31*FI + C32*F2) F4= H*F(T + C40*H, X + C41*F1 + C42*F2 + C43*F3) Vol. 2 Part 2 G-205 NUREG/C.R-6143
LOSP Frequency F5- H'F(T + H, X + C51*F1 + C52*F2 + C53*F3 + C54*F4) F6= H*F(T + 0.5*H, X + C61*F1 + C62*F2 + C63*F3 + C64*F4 + C65*F5). X5 - X + Bl*F1 + B3*F3 + B4*F4 + B5*F5 + B6*F6 X = X + Al*FI + A3*F3 + A4*F4 + AS*FS T = T + H EST = DABS (X - X5) RETURN END C LINEAR INTERPOLATION ROUTINE C================================================ C THIS FUNCFION PERFORMS A LINEAR INTERPOLATION i C T(IMAX,2) = 2 DIMENSIONAL ARRAY C T(I,1) or X DATA C T(I,2) = Y DATA C IMAX - TOTAL NUMBER OF X VALUES (AND ALSO Y VALUES) CX = X VALUE FOR WHICH A Y VALUE WILL BE CALCULATED DOUBLE PRECISION FUNCTION XINTRP(X,T,lMAX) DOUBLE PRECISION T(IMAX 2), X, XLO, XHl. YLO, YHI C IF THE VALUE OF X IS GREATER THAN THE LAST VALUE IN T, SET Y TO THE C LAST VALUE IN T IF(X .GT. T(IMAX,1))THEN XINTRP = T(IMAX,2) ELSEIF(X .LT. T(1,1))THEN XINTRP = T(1,2) ELSE I=1 10 IF(X .GT. T(I,1))THEN I-I+1 GOTO 10 ELSE IF(I .EQ.1) I=2 XLO = T(I-1,1) YLO = T(I-1,2) XHI - T(1,1) YHI - T(I, 2) XINTRP = (X - XLO)/(XHI - XLO)*(YH1 - YLO) + YLO ENDIF ENDIF RETURN END NUREG/CR-6143 G-206 Vol. 2, Part 2
LOSP Frequency I Attachment G-46 ' IRRAS Histogram Development Spread Sheet Inpui l l l I l l Vol. 2, Part 2 G-207 NUREG/CR-6143 l e,.-
[ t LOSP Frapaeocy f l Point LOSP-2H LOSP 3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP-14H 1 0.09264 0.0658 0.05742 0.03928 0.03137 0.01291 0.007832 2 0.08686 0.06034 0.05324 0.03491 0.0286 0.01133 0.006642 3 0.06559 0.04222 0.03629 0.02212 0.01718 0.00505 0.002583 4 0.08587 0.05961 0.05215 0.03465 0.02782 0.01087 0.00651 . 5 0.1197 0.08889 0.07911 0.05563 0.04664 0.02354 0.01611
}
6 0.08475 0.05921 0.05158 0.03443 0.02743 0.01057 0.006332 7 0.08327 0.05792 0.05068 0.03383 0.02648 0.01008 0.005758 8 0.1082 0.07709 0.06884 0.04924 0.04043 0.01874 0.01217 ! 9 0.07628 0.05248 0.04552 0.02988 0.022 % 0.00756 0.004266 - 10 0.1174 0.08649 0.07679 0.05394 0.04525 0.02254 0.01555 l 11 0.09791 0.06905 i 0.06116 0.04258 0.03531 0.01511 0.009755 12 0.1506 0.1116 0.1013 0.07769 0.06876 0.04103 0.03315 13 0.06128 0.03966 0.03366 0.02091 0.0152 0.00395 0.001831 14 0.0705 0.047 0.04061 0.02574 0.01992 0.00612 0.003154 ! 15 0.1119 0.08114 0.07204 0.05108 0.04205 0.01987 0.0132 16 0.1018 0.07257 0.06418 0.04537 0.0373 0.01669 0.01076 : 17 0.07839 0.05388 0.04693 0.03049 0.02373 0.00768 0.004419 i 18 0.1328 0.1004 0.09019 0.06652 0.05691 0.02973 0.02186 ! 19 0.09006 0.06254 0.05492 0.03659 0.02968 0.01207 0.007246 20 0.1506 0.1115 0.1012 0.07764 0.06817 0.04096 0.03284 l 21 0.1623 0.1249 0.I14 0.0912 0.07934 0.04995 0.041;2 , 22 0.1417 0.1062 0.09609 0.07146 0.06149 0.03465 0.02548 f 23 0.05871 0.03852 0.03255 0.01916 0.01442 0.00365 0.001635 l 24 0.1445 0.107 0.09706 0.07427 0.06396 0.03722 0.02707 l 25 0.09323 0.06588 0.05752 0.03939 0.03149 0.01301 0.007935 l 26 0.07097 0.04759 0.04116 0.02583 0.02021 0.00613 0.003204 27 0.07595 0.05207 0.04526 0.02 % 2 0.02292 0.00755 0.004259 28 0.1348 0.101 0.09085 0.06738 0.05731 0.03018 0.02256 < 29 0.07988 0.05518 0.04816 0.03195 0.02474 0.00869 0.004903 , 30 0.04782 0.02948 0.02451 0.01327 0.00882 0.00193 0.0007853 31 0.04742 0.02849 0.02361 0.0126 0.00871 0.00164 0.0005726 32 0.1563 0.1iE7 0.1073 0.08054 0.07374 0.0455 0.03725 33 0.1107 0.07858 0.06993 0.05001 0.04141 0.01933 0.01276 NUREG/CR 6143 G 208 Vol. 2, Part 2 ! i
LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP-14H 34 0.06524 0.04204 0.03607 0.02193 0.01683 0.00504 0.002508 , l 1 35 0.09456 0.06662 0.0583 0.03996 0.03239 0.01333 0.008309 36 0.0555 0.03453 0.0294 0.01735 0.01321 0.00317 0.001309 0.08316 0.05787 0.05053 0.03373 0.02629 0.01005 0.00574 37
)
38 0.06521 0.0419 0.03586 0.02184 0.01682 0.00503 0.00248 39 0.1234 0.09091 0.08109 0.05838 0.04871 0.02464 0.017 40 0.1201 0.08925 j 0.07932 0.0558 0.04704 0.0237 0.01621 41 0.1383 0.1025 0.09352 0.06942 0.0589 0.03261 0.02401 42 0.1221 0.09009 0.08018 0.05627 0.04782 0.02416 0.01629 43 0.0808 0.05594 0.04889 0.03227 0.0251 0.00904 0.005035 44 0.07962 0.05502 0.04795 0.03155 0.0247 0.00851 0.004757 45 0.2028 0.183 0.1792 0.1691 0.1636 0.1454 0.1391 46 0.08213 0.0568 0.04972 0.03319 0.02597 0.00969 0.005408 47 0.09475 0.06665 0.05838 0.04003 0.03246 0.01335 0.00833 48 0.108 0.07688 0.06866 0.0489 0.04028 0.0187 0.01205 49 0.05899 0.03862 0.03271 0.01959 0.01459 0.00369 0.001714 50 0.1409 0.1043 0.09455 0.07018 0.06026 0.03358 0.02442 51 0.1468 0.1082 0.09804 0.07465 0.06452 0.03803 0.0293 52 0.1317 0.09866 0.08864 0.0653 0.05562 0.02852 0.0205 53 0.1206 0.08941 0.07961 0.05586 0.04714 0.02394 0.01624 54 0.1413 0.1048 0.09509 0.07092 0.06062 0.03433 0.0249 55 0.04487 0.02696 0.02183 0.01226 0.00847 0.00118 0.0004245 56 0.09804 0.0694 0.06138 0.04276 0.03539 0.01535 0.009771 57 0.1149 0.0832 0.07376 0.05236 0.04328 0.02046 0.01403 58 0.1249 0.09146 0.08172 0.05988 0.05007 0.02507 0.0173 59 0.06699 0.04462 0.03829 0.02376 0.01809 0.00556 0.002774 60 0.0942 0.06649 0.058 0.0397 0.03222 0.01331 0.008271 61 0.1002 0.07147 0.06301 0.04388 0.03674 0.01603 0.01025 62 0.09155 0.06487 0.05645 0.03837 0.03102 0.01243 0.007448 63 0.1266 0.09322 0.0835 0.06082 0.05137 0.02566 0.01787 64 0.07582 0.05196 0.04516 0.02951 0.02287 0.00752 0.004182 65 0.09516 0.06703 0.05864 0.04036 0.03314 0.01368 0.0085 66 0.08381 0.05854 0.0511 0.03399 0.02701 0 01027 0.006071 Vcl. 2. Part 2 G-209 NUREG/CR-6143
LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP-14H 67 0.1033 0.07291 0.06456 0.04556 0.03748 0.01681 0.01123 68 0.07098 0.04776 0.04126 0.02608 0.02026 0.00619 0.003241 69 0.1647 0.1324 l 0.1213 0.09333 0.08578 0.05293 0.04275 70 0.07543 0.05173 0.04486 0.02927 0.02272 0.00737 0.004142 71 0.06044 0.03911 0.03322 0.02061 0.0149 0.00385 0.001783 72 0.08194 0.05655 0.0494 0.03297 0.02564 0.00952 0.005281 73 0.07448 0.0505 0.04394 0.02866 0.02218 0.00714 0.003934 74 0.09409 0.06631 0.05789 0.03967 0.03211 0.01326 0.00819 75 0.1132 0.08196 0.07274 0.05169 0.04234 0.02002 0.01362 76 0.09131 0.06459 0.05631 0.03816 0.03083 0.01239 0.007341 77 0.07757 0.05384 0.04659 0.03029 0.02343 0.00767 0.0 M 413 78 0.06569 0.04262 0.03(68 0.0225 0.01734 0.0052 0.002644 79 0.1198 0.08894 0.07915 0.05575 0.04687 0.02355 0:0162 l 80 0.1075 0.07646 0.06827 0.04858 0.03995 0.01838 0.01182 81 0.05214 0.03142 0.02622 0.01512 0.01151 0.00249 0.001023 82 0.1951 0.1586 0.145 0.1158 0.1071 0.07912 0.06775 83 0.162 0.1195 0.1109 0.09118 0.07721 0.04979 0.03954 84 0.08853 0.06185 0.0543 0.03576 0.02942 0.01182 0.007001 85 0.1923 0.1576 0.1441 0.1119 0.1006 0.06848 0.05719 86 0.07056 0.04709 0.04087 0.0258 0.02021 0.00612 0.003163 87 0.06002 0.03908 0.03319 0.01989 0.01464 0.00377 0.001771 88 0.0959 0.06752 0.05933 0.04109 0.03405 0.01402 0.008765 89 0.07457 0.05125 0.04444 0.02893 0.02246 0.00719 0.004009 90 0.09767 0.06895 0.06096 0.M 249 0.03517 0.01503 0.009647 91 0.1252 0.09161 0.08216 0.06008 3.05048 0.02534 0.0174 92 0.1523 0.1149 0.1031 0.07866 0.06919 0.04315 0.03324 93 0.1084 0.0771 0.06892 0.04942 0.04054 0.01876 0.01227
- 94 0.08642 0.05981 0.05248 0.0348 0.02S34 0.011 0.006555 95 0.06565 0.04228 0.0365 0.02243 0.01731 0.00519 0.002634 96 0.07904 0.05482 0.04775 0.03146 0.02463 0.00841 0.0 M 707 97 0.1153 0.08342 0.07388 0.05238 0.04334 0.02061 0.01413 98 0.1641 0.1321 0.1208 0.09311 0.08362 0.05272 0.04241 99 0.06473 0.04119 0.03519 0.02141 0.01646 0.0 M 9 0.002326 i
NUREG/CR-6143 G-210 Vol. 2, Put 2
-- - - . . - - . . - . - - . . _ _ _ _ ~ - . - . . . - . .
1 LOSP Frequency Point LOSP-2H LOSP 3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP-14H 100 0.1279 0.09488 0.08524 0.0629 0.05283 0.02646 0.01925 101 0.1411 0.1045 0.09475 0.07045 0.0603 0.03392 0.02443 102 0.1473 0.1084 0.09818 0.07479 0.06473 0.03914 0.02958 ) 103 0.06645 0.04361 0.03744 0.02337 0.01775 0.00542 0.002772 104 0.166 0.1366 0.1264 0.1016 0.0909 0.05555 0.0466 , l 105 0.07884 0.05464 0.04756 0.03092 0.02436 0.00802 0.004586 106 0.1479 0.1098 0.09921 0.07652 0.06544 0.03 % 0.0313 107 0.1363 0.1021 0.09201 0.06823 0.05851 0.03062 0.02345 108 0.06346 0.04056 0.0347 0.02126 0.01632 0.00462 0.002157 109 0.1036 0.07297 0.06467 0.04577 0.03756 0.01689 0.01125 i 110 0.1067 0.07564 0.06742 0.04738 0.03912 0.01785 0.01164 111 0.1474 0.1088 0.09846 0.07586 0.0649 0.03917 0.03 i 112 0.09945 0.06997 0.06203 0.04341 0.03595 0.01553 0.009865 113 0.0869 0.06058 0.05343 0.03511 0.02871 0.01138 0.006707 114 0.05525 0.03409 0.02891 0.01705 0.01284 0.0029 0.001263 - 115 0.09757 0.06894 0.06092 0.04242 0.03514 0.01479 0.009557 116 0.1055 0.07505 0.06692 0.04695 0.03865 0.01775 0.01152 ; 117 0.07979 0.05512 0.04809 0.03182 0.02471 0.00856 0.004782 , 118 0.08269 0.05727 0.05013 0.03339 0.02612 0.00982 0.005529 l 119 0.05791 0.03713 0.03147 0.01886 0.01419 0.00342 0.001471 i 120 0.1243 0.09144 0.08169 0.05968 0.04949 0.025 0.0173 l 121 0.1168 0.08547 0.07585 0.05331 0.04483 0.02199 0.01518 122 0.04112 0.02174 0.0187 0.00978 0.00641 0.0011 0.0004035 123 0.09454 0.06649 0.05802 0.0399 0.03226 0.01331 0.008306 124 0.09635 0.06758 0.05954 0.04127 0.03416 0.01415 0.008828 125 0.1319 0.09877 0.08874 0.06532 0.05569 0.02854 0.0 M 126 0.06861 0.04618 0.03939 0.02419 0.01848 0.00581 0.00h 127 0.1094 0.07843 0.06977 0.04975 0.04081 0.01923 0.01261 ) 128 0.1413 0.1049 0.09535 0.07094 0.06106 0.03441 0.02498 129 0.08282 0.05745 0.0503 0.03345 0.02616 0.00998 0.00565 130 0.155 0.1174 0.1052 0.08019 0.07193 0.04521 0.03468 131 0.08816 0.06177 0.05424 0.03571 0.02942 0.01177 0.006993 132 0.08662 0.06013 0.05286 0.03485 0.02849 0.01118 0.006562 133 0.1431 0.1066 0.09673 0.07232 0.06238 0.03542 0.02571 Vol. 2, Part 2 G-211 NUREG/CR-6143
- - - - - . - . . _ . . --- . . - -_ - - - - - . - _ . . _ ~ .
LOSP Frequency Point LOSP 2H LOSP-3H LOSP-3.5H LOSP 5H LOSP-6H LOSP-llH LOSP-14H 0.07479 0.05169 0.04477 0.02912 0.02267 0.00733 0.004141 134 135 0.07557 0.05194 0.04513 0.02943 0.02275 0.00748 0.004181 0.1393 0.1034 0.09403 0.06951 0.05891 0.03299 0.0241 136 137 0.08674 0.06016 0.05291 0.03491 0.02858 0.01119 0.006582 138 0.05782 0.03706 0.03125 0.01868 0.01406 0.00338 0.001466 139 0.09981 0.07092 0.06266 0.04367 0.03637 0.01598 0.01008 140 0.1003 0.07157 0.06307 0.04389 0.0368 0.01613 0.01029 141 0.06852 0.04578 0.03902 0.02405 0.01843 0.00565 0.002853 142 0.1364 0.1022 0.09226 0.06826 0.05865 0.03065 0.02363 143 0.1011 0.07191 0.0635 0.04468 0.03694 0.01631 0.01045 144 0.07851 0.05405 0.04708 0.03052 0.0238 0.00777 0.004448 145 0.06816 0.04515 0.03865 0.02403 0.01837 0.00563 0.002834 146 0.07637 0.05301 0.04602 0.03015 0.02318 0.00761 0.004278 147 0.1294 0.09661 0.0867 0.06396 0.05396 0.02727 0.01988 148 0.1088 0.07742 0.06912 0.04943 0.04064 0.01881 0.01228 149 0.08544 0.05958 0.05205 0.03463 0.02773 0.01076 0.006397 150 0.07435 0.05024 0.N38 0.02854 0.02217 0.0071 0.00383 151 0.09529 0.0C704 0.05869 0.04047 0.03327 0.01369 0.008582 152 0.09555 0.06723 0.05884 0.04088 0.03353 0.01374 0.008626 153 0.08278 0.05737 0.05021 0.03341 0.02614 0.00988 0.005539 154 0.06576 0.04377 0.03771 0.02339 0.01785 0.00543 0.002772 155 0.06444 0.04108 0.035 0.0214 0.01641 0.00489 0.002289 156 0.07631 0.05249 0.04566 0.02992 0.02312 0.00757 0.004271 157 0.1282 0.09514 0.08568 0.06329 0.05367 0.02668 0.01952 158 0.08343 0.05811 0.05083 0.03389 0.02683 0.01021 0.005879 159 0.1114 0.08023 0.07144 0.05 % 0.04199 0.01975 0.013 160 0.073 % 0.0496 0.04331 0.02794 0.0216 0.00694 0.003734 161 0.1167 0.08511 0.07565 0.0533 0.04481 0.02183 0.01513 162 0.08732 0.06136 0.05394 0.03531 0.02897 0.01144 0.006834 163 0.08854 0.06186 0.05432 0.03585 0.02944 0.0119 0.007016 164 0.1015 0.07229 0.06384 0.04484 0.03715 0.01648 0.01063 165 0.09374 0.0661 0.0577 0.03954 0.03164 0.01308 0.008125 166 0.1518 0.1126 0.1019 0.07842 0.06886 0.04107 0.0332 167 0.06504 0.04135 0.03547 0.02162 0.01673 0.00497 0.002469 NUREG/CR-6143 G-212 Vol. 2, Part 2 f g
i LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP 14H , i 168 0.104 0.07395 0.06554 0.M 601 0.03804 0.01704 0.01138 169 0.05901 0.03905 0.033 0.01961 0.01461 0.00373 0.001737 170 0.1133 0.082 0.07279 0.05175 0.04254 0.02011 0.01368 171 0.1316 0.09856 0.08853 0.06506 0.0554 0.02824 0.02047 172 0.09183 0.06521 0.05678 0.03868 0.03119 0.0128 0.007574 173 0.1399 0.1039 0.09426 0.0698 0.05962 0.033 0.02414 174 0.07851 0.05425 0.04719 0.03056 0.02389 0.00778 0.004486 175 0.09709 0.06789 0.0602 0.04213 0.03493 0.01458 0.009229 176 0.1174 0.0866 0.07687 0.05399 0.N527 0.02265 0.01563 177 0.09113 0.06395 0.05585 0.03752 0.03077 0.0123 0.007315 178 0.1138 0.08234 0.07304 0.05195 0.04258 0.02027 0.01382 179 0.09802 0.06913 0.06122 0.04262 0.03538 0.01529 0.009766 180 0.1274 0.09382 0.08403 0.06239 0.05235 0.02633 0.01876
~
181 0.06617 0.04341 0.03725 0.02311 0.01758 0.00536 0.002711 182 0.08893 0.06196 0.05447 0.03611 0.0295 0.01194 0.007116 183 0.08323 0.0579 0.05064 0.03377 0.02646 0.01008 0.005758 184 0.07426 0.05024 0.0437 0.02834 0.02206 0.00698 0.003828 185 0.08199 0.05666 0.0496 0.03315 0.02565 0.00968 0.005398 186 0.1561 0.1181 0.1056 0.08027 0.0724 0.04543 0.03476 187 0.1055 0.07502 0.06684 0.04667 0.03835 0.01766 0.0115 188 0.1157 0.08435 0.07506 0.05276 0.04381 0.0211 0.01464 189 0.08339 0.05808 0.05077 0.03386 0.02673 0.0102 0.005809 190 0.1322 0.0992 0.0891 0.06589 0.056 0.02874 0.02107 191 0.1407 0.1042 0.09447 0.07008 0.06004 0.03348 0.02424 192 0.09654 0.06776 0.06003 0.04139 0.03445 0.01432 0.008983 193 0.05488 0.03407 0.0286 0.01689 0.01233 0.00289 0.001217 194 0.07653 0.05334 0.0462 0.03017 0.02323 0.00764 0.0N29 195 0.09682 0.06779 0.06011 0.042 0.03486 0.01446 0.009215 196 0.07456 0.05067 0.04413 0.02885 0.0222 0.00718 0.003935 197 0.1221 0.09035 0.08032 0.05677 0.04794 0.02428 0.01629 198 0.1411 0.1046 0.09489 0.07083 0.06061 0.03406 0.02459 199 0.09716 0.06883 0.06084 0.04239 0.03504 0.01471 0.009463 l 200 0.1069 0.07585 0.06764 0.04773 0.03922 0.01796 0.01167 201 0.1154 0.08371 0.07451 0.05254 0.04342 0.02075 0.01425 i Vol. 2. Part 2 G-213 NUREG/CR-6143 l 1
LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP-14H 202 0.1345 0.1008 0.0906 0.0671 0.05718 0.03011 0.0225 203 0.09009 0.06258 0.05497 0.0366 0.0301 0.01215 0.00725 204 0.05274 0.03245 0.02713 0.01556 0.01178 0.00275 0.001087 205 0.09174 0.0652 0.05677 0.03864 0.03113 0.01261 0.007528 206 0.1116 0.0804 0.07161 0.05067 0.042 0.01979 0.01305 207 0.1433 0.1066 0.09681 0.07297 0.06333 0.03619 0.02594 208 0.09677 0.06778 0.0601 0.04189 0.03474 0.01444 0.009135 209 0.08151 0.05643 0.04933 0.03296 0.0256 0.00945 0.005219 210 0.1673 0.1397 0.1292 0.1029 0.0911 0.05991 0.04855 211 0.1311 0.09848 0.0885 0.06498 0.05493 0.02785 0.02043 212 0.09909 0.06968 0.06168 0.04305 0.03562 0.01543 0.009817 213 0.06898 0.04658 0.03996 0.02505 0.01901 0.00603 0.003001 214 0.0803 0.05593 0.04878 0.03226 0.02509 0.00892 0.005018 215 0.08597 0.05965 0.0522 0.03467 0.02788 0.01096 0.006514 216 0.02701 0.01349 0.01095 0.00582 0.00422 0.00085 0.0003165 217 0.07168 0.04823 0.')415 0.02672 0.02043 0.00625 0.003256 218 0.1618 0.1193 0.iO94 0.08589 0.07561 0.04842 0.03919 219 0.0739 0.04934 0.04314 0.02783 0.02159 0.00693 0.003698 220 0.1154 0.08412 C.07488 0.05272 0.04361 0.02105 0.01433 221 0.05413 0.03346 0.02793 0.01625 0.01231 0.00288 0.001196 222 0.08361 0.05833 0.05097 0.03392 0.02691 0.01021 0.005942 223 0.1126 0.0816 0.07248 0.0514 0.0423 0.01995 0.01333 224 0.07174 0.04829 0.04157 0.02673 0.02056 0.00627 0.003294 225 0.138 0.1024 0.09332 0.0691 0.05889 0.03211 0.02392 226 0.1416 0.1051 0.09554 0.07122 0.06108 0.03453 0.02548 227 0.1349 0.1013 0.09134 0.06741 0.05776 0.03038 0.0227 228 0.1278 0.09466 0.08504 0.06261 0.05271 0.02644 0.01921 229 0.06344 0.04013 0.03431 0.02124 0.01625 0.00458 0.002118 230 0.1164 0.0847 0.07533 0.05296 0.04426 0.02167 0.01499 231 0.1492 0.1111 0.101 0.07737 0.06626 0.04034 0.03238 232 0.0849 0.05925 O 0516 0.0345 0.02753 0.01063 0.006358 233 0.09984 0.07137 0.06291 0.04378 0.03639 0.01601 0.01017 234 0.1324 0.1001 0.0E975 0.06642 0.05662 0.02969 0.02142 235 0.07402 0.04993 0.04354 0.02829 0.02201 0.00698 0.003745 NUREG/CR-6143 G-214 Vol. 2 Part 2
1 l LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5'8 LOSP-5H LOSP4H LOSP-11H LOSP-14H 236 0.1038 0.0736 0.06514 0.04594 0.03801 0.01692 0.01132 237 0.1117 0.0808 0.07185 0.0507 0.04201 0.01981 0.01307 238 0.1042 0.07403 0.0656 0.04605 0.03807 0.01737 0.0114 239 0.09232 0.06551 0.05727 0.03917 0.03125 0.01283 0.007795 240 0.06549 0.N 22 0.03626 0.02206 0.01709 0.00504 0.002558 241 0.08542 0.05936 0.05185 0.03463 0.02768 0.01069 0.006368 242 0.1149 0.08269 0.0735 0.05221 0.04328 0.02 N 0.01399 243 0.1203 0.08934 0.07956 0.05581 0.0471 0.02389 0.01623 244 0.1286 0.09526 0.08578 0.06358 0.05374 0.02674 0.01978 245 0.06191 0.03984 0.03397 0.021 0.01564 0.00418 0.001917 246 0.09214 0.06549 0.05716 0.03911 0.03124 0.01282 0.007782 247 0.1267 0.09329 0.08367 0.06189 0.05154 0.0257 0.01801 248 0.1005 0.07173 0.06324 0.04454 0.03693 0.01624 0.01042 249 0.1171 0.08605 0.07641 0.05375 0.04523 0.02221 0.01542 250 0.08298 0.05782 0.0505 0.03365 0.02618 0.00999 0.005721 251 0.1188 0.08806 0.07784 0.05467 0.04566 0.02314 0.01583 252 0.0953 0.06712 0.05876 0.04048 0.03336 0.01373 0.008583 253 0.1604 0.1193 0.1085 0.08286 0.07524 0.04796 0.03799 254 0.09112 0.06382 0.05578 0.03733 0.03071 0.01226 0.007307 255 0.07295 0.04878 0.04245 0.02742 0.02109 0.0067 0.003553 256 0.1091 0.07834 0.06969 0.04963 0.0408 0.01911 0.01249 257 0.06947 0.04668 0.04033 0.02532 0.0194 0.00605 0.003084 258 0.06887 0.04627 0.03965 0.02453 0.01873 0.00588 0.002882 259 0.111 0.07966 0.07064 0.05015 0.04156 0.01938 0.01284 260 0.1536 0.1I66 0.1048 0.07917 0.06994 0.N 353 0.03412 261 0.07229 0.04862 O.04229 0.02702 0.02079 0.0065 0.003355 262 0,1369 0.1023 0.09252 0.06853 0.05878 0.03128 0.02369 263 0.09626 0.06756 0.05944 0.04112 0.03408 0.01404 0.008826 264 0.1072 0.0762 0.06797 0.04839 0.03936 0.01828 0.01168 265 0.1282 0.09504 0.08544 0.0631 0.05361 0.02652 0.01939 266 0.06443 0.04088 0.034 0 0.02133 0.01635 0.0048 0.00225 267 0.05835 0.03794 0.03212 0.01911 0.01428 0.00362 0.001611 268 0.05158 0.02971 0.02489 0.01366 0.00943 0.00207 0.0008738 269 0.09127 0.06414 0.05605 0.0376 0.03077 0.01238 0.007338 Vol. 2, Part 2 G-215 NUREG/CR4143 O
LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-IIH LOSP-14H 270 0.05656 0.03616 0.03043 0.01846 0.01372 0.00331 0.001417 271 0.1529 0.1155 0.1041 0.07911 0.06946 0.04332 0.03393 272 0.1465 0.1078 0.09776 0.07455 0.06437 0.03755 0.02864 273 0.07349 0.04897 0.04257 0.02751 0.02118 0.00678 0.003593 274 0.1797 0.142 0.1336 0.1109 0.09598 0.06402 0.05498 I 275 0.1448 0.1077 0.09757 0.07435 0.06419 0.03742 0.02828 276 0.08431 0.05862 0.05117 0.03402 0.0271 0.01035 0.006095 277 0.06973 0.04693 0.04056 0.02563 0.01974 0.0061 0.003134 278 0.1112 0.08009 0.07127 0.05053 0.04187 0.01962 0.013 l 1 279 0.09374 0.06607 0.05763 0.03941 0.03157 0.01304 0.008047 280 0.04613 0.02728 0.02257 0.01229 0.00858 0.00118 0.0004862 281 0.1207 0.0896 0.0798 0.05587 0.0472 0.02403 0.01626 282 0.08601 0.05968 0.05239 0.03478 0.02799 0.01097 0.006549 283 0.09481 0.06666 0.05839 0.04008 0.03261 0.01349 0.008363 284 0.04583 0.06735 0.05909 0.04108 0.03399 0.01396 0.008757 285 0.119 0.08819 0.07807 0.05478 0.04596 0.02317 0.01583 286 0.06559 0.04226 0.03633 0.02218 0.01726 0.00516 0.002604 287 0.07366 0.04903 0.04291 0.02755 0.02137 0.00682 0.003661 288 0.09652 0.0677 0.05997 0.04132 0.03438 0.01426 0.008921 289 0.1826 0.1448 0.1359 0.1115 0.1005 0.06492 0.05624 290 0.1263 0.09307 0.08338 0.06069 0.05132 0.02565 0.0177 291 0.1144 0.08257 0.0734 0.05206 0.04314 0.02038 0.01397 292 0.1154 0.08351 0.07404 0.05252 0.04335 0.02074 0.01419 293 0.08948 0.06238 0.05475 0.03638 0.02962 0.01206 0.00715 294 0.09877 0.0696 0.0616 0.04289 0.03548 0.01541 0.009816 295 0.1054 0.07441 0.06593 0.0465 0.03811 0.01758 0.01146 296 0.09264 0.06583 0.05745 0.0393 0.03145 0.01291 0.007913 297 0.07731 0.05373 0.04649 0.03023 0.02336 0.00766 0.004375 298 0.04772 0.0292 0.02404 0.01312 0.00878 0.00189 0.0 0 7708 299 0.08689 0.06051 0.05333 0.035 0.02864 0.01134 0.006696 300 0.08859 0.06192 0.05443 0.03607 0.02948 0.01193 0.007099 301 0.05179 0.03062 0.02555 0.01408 0.01039 0.00212 0.0008958 302 0.1647 0.1331 0.1235 0.1002 0.08815 0.05499 0.0435 303 0.1079 0.07657 0.06845 0.04875 0.04023 0.01855 0.01192 NUREG/CR 6143 G-216 Vol. 2, Part 2
LOSP Frequency Point LOSP-211 LOSP-311 LOSP-3.511 LOSP-511 LOSP-611 LOSP-Illi LOSP-14H 304 0.1487 0.1107 0.1008 0.07712 0.06599 0.04016 0.03228 305 0.1309 0.09743 0.08778 0.06468 0.05426 0.02751 0.02022 306 0.09167 0.06498 0.05665 0.03862 0.03112 0.01255 0.00752 307 0.06617 0.04351 0.03735 0.02318 0.01766 0.00538 0.002726 308 0.1294 0.09681 0.08693 0.06418 0.054 0.02731 0.01998 309 0.1639 0.1291 0.1184 0.09277 0.08286 0.0527 0.04215 310 0.1295 0.09686 0.08732 0.0643 0.05411 0.02732 0.02 311 0.1225 0.09035 0.08036 0.05685 0.04833 0.02428 0.01661 312 0.0802 0.05535 0.04841 0.03198 0.02494 0.0087 0.004947 313 0.1478 0.1096 0.09909 0.07639 0.06541 0.03919 0.03017 314 0.1075 0.07648 0.06834 0.04862 0.04001 0.01846 0.01191 315 0.1089 0.07829 0.06963 0.04961 0.04078 0.0189 0.01233 316 0.07374 0.04931 0.04308 0.02762 0.02157 0.00692 0.003689 317 0.08753 0.06142 0.05402 0.03539 0.02899 0.01146 0.006853 318 0.07861 0.05436 0.04729 0.03071 0.02397 0.0079 0.004493 319 0.0668 0.04416 0.03796 0.02366 0.01793 0.00554 0.002773 320 0.09909 0.06974 0.06173 0.04313 0.03567 0.01544 0.009835 321 0.1258 0.09268 0.08292 0.06039 0.05094 0.02546 0.01753 322 0.1089 0.07752 0.06922 0.0495 0.04076 0.01888 0.01232 323 0.08141 0.05635 0.04927 0.03294 0.12557 0.00931 0.005196 324 0.09514 0.06688 ' O.05855 0.04027 0.03285 0.01364 0.008498 325 0.09786 0.06901 0.0611 0.04251 0.0353 0.01507 0.009733 326 0.1033 0.07286 0.06441 0.04555 0.03747 0.01674 0.01108 327 0.06927 0.04665 0.04015 0.02516 0.01928 0.00604 0.003068 328 0.09714 0.06879 0.06081 0.04236 0.03502 0.01467 0.009388 329 0.08755 0.06149 0.05406 0.03.542 0.02913 0.01159 0.006893 330 0.08647 0.05991 0.05253 0.03484 0.02838 0.01112 0.006557 331 0.09936 0.06984 0.06193 0.04318 0.03569 0.01545 0.009837 332 0.08024 0.05563 0.04857 0.03205 0.02495 0.00874 0.004958 333 0.07435 0.05024 0.0438 0.02854 0.02217 0.0071 0.00383 ! 334 0.06574 0.04296 0.03685 0.02287 0.01734 0.0053 0.002658 335 0.1251 0.09158 0.08195 0.05995 0.05029 0.0253 0.01736 336 0.1074 0.07629 0.06812 0.0485 0.03973 0.01828 0.01169 337 0.118 0.08718 0.07726 0.0543 0.04538 0.02282 0.01573 Vol. 2, Part 2 G-217 NUREG/CR-6143
i l LOSP Frequency j Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP-14H 338 0.1129 0.08172 0.07255 0.05164 0.0423 0.01998 0.01351 339 0.1052 0.07431 0.06574 0.0463 0.03811 0.01745 0.01144 340 0.09105 0.06374 0.05569 0.03728 0.03046 0.01226 0.0073 341 0.08541 0.0593 0.05165 0.03453 0.02759 0.01067 0.006359 342 0.07883 0.05464 0.0475 0.03083 0.02418 0.00799 0.004503 343 0.05592 0.03542 0.0299 0.0174 0.01349 0.00318 0.001396 344 0.1232 0.09073 0.08095 0.05782 0.04853 0.02456 0.01692 345 0.0299 0.02082 0.01676 0.00802 0.00528 0.00106 0.0003858 346 0.1277 0.0941 0.08435 0.06246 0.05244 0.02636 0.01884 1 347 0.1158 0.08436 0.07509 0.0528 0.04389 0.02129 0.01474 348 0.07188 0.04835 0.04181 0.02682 0.0206 0.00628 0.003294 349 0.1164 0.08453 0.0752 0.05287 0.04402 0.02167 0.01484 350 0.1194 0.08854 0.07894 0.05511 0.04661 0.02348 0.01605 351 0.1016 0.07241 0.06396 0.04485 0.03715 0.01652 0.01063 352 0.1169 0.08573 0.07618 0.05362 0.04521 0.02218 0.0154 1 353 0.106 0.07512 0.06699 0.04698 0.03869 0.01779 0.01156 i 354 0.1293 0.09603 0.08633 0.06396 0.05382 0.02684 0.01986 355 0.06278 0.04013 0.03426 0.02118 0.01588 0.00456 0.002064 356 0.07842 0.05394 0.047 0.0305 0.0238 0.00773 0.004441 357 0.1487 0.1101 0.1 0.07655 0.06594 0.03995 0.03174 358 0.06973 0.0468 0.04046 0.02545 0.01945 0.0061 0.003102 359 0.07301 0.04886 0.04251 0.02749 0.02114 0.00673 0.003571 360 0.0938 0.06621 0.05782 0.03967 0.03197 0.01311 0.008137 361 0.09968 0.07053 0.06245 0.04364 0.03619 0.01596 0.009976 362 0.1423 0.1063 0.09629 0.07215 0.06228 0.03481 0.02563 363 0.1096 0.07856 0.06985 0.04987 0.04099 0.0193 0.01261 364 0.09712 0.06872 0.06068 0.0422 0.03498 0.01463 0.009236 l 365 0.1191 0.0882 0.07813 0.05491 0.0461 0.02319 0.01588 366 0.1307 0.09723 0.08763 0.06465 0.05416 0.02738 0.02019 367 0.1038 0.07347 0.06497 0.0458 0.03778 0.01689 0.01128 368 0.08245 0.05686 0.04985 0.03328 0.02601 0.00975 0.005501 369 0.09955 0.07018 0.06227 0.04345 0.03606 l 0.01554 0.009965 370 0.0949 0.06679 0.05848 0.04019 0.03267 0.01351 0.008381 371 0.08094 0.05604 0.04895 0.03232 0.02519 0.00914 0.005038 NUREG/CR-6143 G-218 Vol. 2, Part 2 l
LOSP Frequency Point LOSP 2H LOSP-3H LOSP-3.5H LOSP-5H LOSP4H LOSP-11H LOSP-14H 372 0.1017 0.07245 0.06405 0.04529 0.03715 0.01654 0.01071 373 0.1375 0.1023 0.09279 0.068 9 0.05887 0.03198 0.02389 374 0.07212 0.04846 0.04187 0.027 0.02061 0.00643 0.003296 375 0.079 0.05475 0.04768 0.03145 0.02441 0.00836 0.004606 376 0.1066 0.07523 0.06706 0.04701 0.03884 0.0178 0.01162 377 0.1126 0.08142 0.07237 0.05136 0.04222 0.01995 0.01326 378 0.1322 0.1 0.08958 0.06614 0.05612 0.02929 0.02131 379 0.08025 0.0559 0.N 875 0.03216 0.02505 0.00889 0.005017 380 0.07546 0.0519 0.04507 0.02928 0.02272 0.00743 0.0 N 147 381 0.1191 0.08832 0.07856 0.05508 0.04626 0.02328 0.01592 382 0.0794 0.05486 0.04785 0.03149 0.02465 0.00848 0.ON72 383 0.08973 0.06249 0.05484 0.03652 0.02965 0.01207 0.007163 384 0.1706 0.1419 0.1333 0.109 0.09349 0.0618 0,0507 385 0.1401 0.l M 0.09434 0.07008 0.05977 0.03325 0.02416 386 0.I137 0.08214 0.07291 0.05186 0.04257 0.02019 0.01375 387 0.1235 0.09093 0.08122 0.05853 0.04873 0.02468 0.01701 388 0 08433 0.05905 0.05141 0.03436 0.02726 0.01041 0.006207 389 0.1066 0.07554 0.06735 0.04714 0.03889 0.01781 0.01164 390 0.08443 0.0591 0.05144 0.03441 0.0273 0.01043 0.006287 391 0.06578 0.04312 0.03697 0.02296 0.01758 0.00532 0.002693 392 0.09258 0.06562 0.05732 0.03926 0.03135 0.01285 0.007815 393 0.1023 0.07261 0.06421 0.04543 0.03734 0.0167 0.01081 394 0.1295 0.09718 0.0876 0.06464 0.05412 0.02737 0.02014 395 0.1421 0.1062 0.09622 0.07187 0.06151 0.03476 0.02551 3% 0.1184 0.08768 0.07758 0.0546 0.04554 0.02305 0.01575 397 0.1627 0.125 0.1152 0.09261 0.08215 0.05149 0.04136 398 0.07852 0.05434 0.04726 0.03068 0.02394 0.00789 0.004487 399 0.1071 0.07598 0.06781 0.04773 0.03935 0.01798 0.01168 400 0.124 0.09137 0.08165 0.05941 0.04943 0.02479 0.01704 401 0.1005 0.07172 0.06316 0.04443 0.03684 l 0.01614 0.01032 402 0.1096 0.07857 0.06988 0.04988 0.04116 0.01932 0.01263 403 0.1668 0.1368 0.1272 0.102 0.t .r9 0.05834 0.0468 404 0.07235 0.04867 0.04239 0.02704 0.02085 0.00663 0.003361 405 0.1006 0.07182 0.06343 0.04462 0.03693 0.01626 0.01043 Vol. 2, Part ', G-219 NUREG/CR-6143
LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP-14H 406 0.08107 0.05624 0.04909 0.03257 0.02523 0.00915 0.005063 407 0.131 0.09837 0.08832 0.06494 0.05441 0.02783 0.02035 408 0.05247 0.03233 0.02703 0.0153 0.01169 0.00275 0.001074 409 0.134 0.1007 0.09049 0.06693 0.05717 0.03004 0.02245 410 0.1187 0.08793 0.07771 0.05465 0.04563 0.02312 0.01582 411 0. % 911 0.04663 0.04004 0.02516 0.01927 0.00603 0.003052 412 0.1154 0.08343 0.07399 0.05247 0.04334 0.02062 0.01417 413 0.09156 0.06496 0.05652 0.03856 0.03108 0.01244 0.007488 414 0.1214 0.09003 0.08008 0.05603 0.04758 0.02405 0.01627 415 0.1109 0.07876 0.07018 0.05009 0.04152 0.01936 0.01283 416 0.06478 0.04131 0.03526 0.02158 0.01658 0.J0496 0.002466 417 0.1692 0.I399 0.1299 0.1051 0.09146 0.0618 0.0486 418 0.1264 0.09317 0.08347 0.06079 0.05132 0.02565 0.01771 419 0.06815 0.04466 _ U.03837 0.02386 0.01812 0.00562 0.002816 420 0.09961 0.07037 0.06237 0.04362 0.03619 0.01585 0.009972 421 0.07988 0.05513 0.0481 0.03193 0.02473 0.00862 0.004802 422 0.07764 0.05384 0.04679 0.0304 0.02372 0.00768 0.004416 423 0.08253 0.05714 0.05001 0.03338 0.02603 0.00976 0.005505 424 0.1128 0.08161 0.07249 0.05164 0.0423 0.01997 0.01349 425 0.07373 0.04929 0.04306 0.02756 0.02153 0.00682 0.003669 426 0.1144 0.08257 0.0734 0.05206 0.04314 0.02038 0.01397 427 0.08139 0.05634 0.04923 0.03283 0.02555 0.00921 0.005171 428 0.1267 0.09322 0.08355 0.06122 0.05138 0.02567 0.01792 ! 429 0.1575 0.1191 0.1079 0.081b7 0.07472 0.04654 0.03759 430 0.1293 0.09564 0.08599 0.06363 0.05379 0.02681 0.01978 431 0.1118 0.08104 0.07198 0.05093 0.04202 0.01985 0.01315 432 0.1631 0.1263 0.116 0.09261 0.08272 0.05204 0.04182 l 433 0.09572 0.0673 0.05904 0.04098 0.03391 0.01394 0.008709 434 0.1255 0.09239 0.08273 0.0602. 0.0508 0.02535 0.01744 435 0.1329 0.1004 0.09026 0.06655 0.05698 0.02999 0.02197 436 0.1154 0.08396 0.07466 0.05256 0.04345 0.02075 0.01431 437 0.06196 0.04008 0.03421 0.02117 0.01572 0.00433 0.001971 438 0.1166 0.08504 0.07556 0.05306 0.04454 L.02178 0.01512 439 0.2393 0.2101 0.203 0.1873 0.1817 0.171 0.169 NUREG/CR-6143 G-220 Vol. 2, Part 2 l l l l
LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-11H LOSP-14H 440 0.08694 0.06106 0.05367 0.03525 0.02872 0.01139 0.00673 441 0.1015 0.07196 0.06363 0.04474 0.0371 0.01638 0.01062 f 442 0.1054 0.07497 0.06658 0.04664 0.03811 0.0176 0.01147 ; 443 0.09684 0.0678 0.06011 0.04209 0.03486 0.01456 0.009222 444 0.1267 0.09328 0.08363 0.06185 0.05149 0.02568 0.01798 445 0.09668 0.06777 0.06008 0.04164 0.03473 0.0144 0.009131 446 0.09558 0.06729 0.05895 0.04089 0.03369 0.01384 0.008627 447 0.08791 0.06168 0.05418 0.03543 0.02936 0.01174 0.006938 448 0.1226 0.09072 0.08065 0.05753 0.04841 0.02431 0.01681 l 449 0.1272 0.09355 0.08389 0.0623 0.05163 0.02607 0.01834 0.09079 0.06339 0.05548 0.03727 0.0304 0.01223 0.00729 450 0.05801 0.03747 0.03186 0.01904 0.01421 0.00362 0.001475 451 0.1362 0.102 0.09182 0.06799 0.0584 0.03061 0.02288 452 0.07971 0.07083 0.05019 0.04176 0.01947 0.01291 453 0.I111 0.1326 0.1003 0.09004 0.0665 0.05677 0.02971 0.02183 454 0.07474 0.05135 0.04453 0.02896 0.0225 0.00728 0.004088 455 0.1168 0.0857 0.07615 0.0534 0.04503 0.02214 0.01538 456 0.08919 0.06229 0.05469 0.03629 0.02954 0.01201 0.00714 457 0.08024 0.05573 0.04863 0.03213 0.0'2496 0.00888 0.004962 458 0.06111 0.05371 0.03528 0.02885 0.01139 0.006734 459 0.08721 0.135 0.1017 0.09151 0.0675 0.05781 0.03048 0.02273 460 0.07281 0.06439 0.04555 0.03741 0.01673 0.0109 461 0.1026 0.03442 0.02919 0.01723 C.01298 0.00315 0.001276 462 0.05544 0.03068 0.02561 0.01504 0.01131 0.00243 0.001017 463 0.05181 0.05155 0.04464 0.02904 0.02251 0.00731 0.004099 464 0.07478 0.09902 0.089 0.06551 0.05576 0.02856 0.02087 465 0.1319 0.09285 0.08305 0.06068 0.05126 0.02555 0.01768 466 0.1261 0.03583 0.03021 0.01838 0.01368 0.00328 0.001406 467 0.05603 , 0.107 0.09701 0.07366 0.0639 0.03708 0.02622 468 0.1438 0.0885 0.07865 0.0551 0.04645 0.02334 0.01602 469 0.1192 0.05884 0.0513 0.03423 0.02716 0.01038 0.006187 470 0.08432 0.05441 0.04736 0.03071 0.02416 0.00798 0.004494 471 0.07874 0.06523 0.05689 0.03881 0.03119 0.01282 0.007616 472 0.09196 0.03618 0.03076 0.01854 0.01402 0.00338 0.001426 473 0.05722 Vol. 2, Part 2 G-221 NUREG/CR-6143 I
LOSP Frequency Point LOSP-2H LOSP-3H LOSP-3.5H LOSP-5H LOSP-6H LOSP-IIH LOSP-14H 474 0.1081 0.07704 0.0688 0.04919 0.04037 0.01873 0.01206 475 0.I111 0.08007 0.07117 0.05021 0.04177 0.01954 0.01297 476 0.1356 0.1017 0.09165 0.06756 0.05834 0.03061 0.02283 477 0.05234 0.03201 0.02656 0.01514 0.01155 0.0026 0.001023 478 0.08443 0.0591 0.05144 0.03441 0.0273 0.01043 0.006287 479 0.1236 0.09136 0.08144 0.05873 0.04927 0.02476 0.017N 480 0.05319 0.03263 0.0273 0.01604 0.01178 0.0028 0.001158 481 0.07672 0.05349 0.04632 0.03022 0.02324 0.00766 0.004302 482 0.04476 0.02668 0.02154 0.01076 0.00724 0.00113 0.00N241 483 0.08367 0.05846 0.05104 0.03393 0.02691 0.01026 0.006028 484 0.1141 0.08245 0.07322 0.05204 0.0431 0.02027 0.01392 485 0.04638 0.02785 0.02302 0.01246 0.00859 0.00154 0.0005338 486 0.1277 0.09438 0.08455 0.0625 0.05256 0.02636 0.01894 487 0.09043 0.0631 0.05525 0.03675 0.03026 0.01218 0.007259 488 0.1164 0.08487 0.07543 0.05297 0.04436 0 92168 0.01503 489 0.06889 0.04652 0.03982 0.02488 0.01884 0.00593 0.002986 490 0.06114 0.03945 0.03345 C.02083 0.01491 0.00392 0.001823 491 0.07285 0.04877 0.04245 0.02738 0.02093 0.00666 0.003438 492 0.09639 0.0676 0.05979 0.04129 0.03435 0.01421 0.008897 493 0.06172 0.03971 0.03369 0.02097 0.01534 0.00411 0.001914 494 0.1156 0.08432 0.07502 0.05274 0.04374 0.02106
, 0.0146 4b 0.1332 0.1005 0.09042 0.06692 0.05712 0.03 0.02212 496 0.1175 0.08676 0.077 0.05421 0.04534 0.02275 0.0157 497 0.1168 0.08549 0.07601 0.05331 0.04484 0.02201 0.01531 498 0.1654 0.1361 0.125 0.1007 0.08931 0.05512 0.04512 499 0.06889 0.04654 0.03994 0.02503 0.01895 0.00598 0.002998 500 0.1323 0.1001 0.08963 0.06641 0.05647 0.02936 0.02142 NUREG/CR-6143 G-222 Vol. 2, Part 2
i LOSP Frequency t Attachment G-47 IRRAS Histogram Development Spread Sheet i i i i Vol. 2, Part 2 G 223 NUREG/CR-6143
LOSP Frequency Step LOSP-2H Bin Bound Frequency Bin Mdpt Prob Density (%) Running Tot 0.00 0.00 0.0252 0.00 0.00 0.00 0.002 2.7010e-02 0.0504 10 0.04 2.00 0.02 0.004 2.9900e-02 0.0599 24 0.06 4.80 0.07 0.006 4.1120e-02 0.0693 40 0.06 8.00 0.15 l 0.008 4.4760e-02 0.0756 35 0.07 7.00 0.22 ! 0.01 4.4870e-02 0.0819 37 0.08 7.40 0.29 0.012 4.6130e-02 0.0845 22 0.08 4.40 0.34 0.014 4.6380e-02 0.0882 22 0.09 4.40 0.38 0.016 4.7420e-02 0.0945 33 0.09 6.60 0.45 0.018 4.7720e-02 0.1008 48 0.10 9.60 0.54 0.02 4.7820e-02 0.1071 26 0.10 5.20 0.59 { 0.022 5.1580e-02 0.1134 33 0.11 6.60 0.66 ! 0.024 5.1790e 02 0.I197 39 0.12 7.80 0.74 0.026 5.1810e-02 0.126 21 0.12 4.20 0.78 0.028 5.2140e-02 0.1323 33 0.13 6.60 0.85 0.03 5.2340e-02 0.1386 18 0.14 3.60 0.88 0.032 5.2470e-02 0.1512 29 0.14 5.80 0.94 0.034 5.2740e-02 0.1638 14 0.16 2.80 0.97
]
0.036 5.3190e-02 0.1764 10 0.17 2.00 0.99 j 0.038 5.4130e-02 0.2016 4 0.19 0.80 1.00 0.04 5.4880e-02 0.2.194 2 0.22 0.40 1.00 0.042 5.5250e-02 0.00 0.M4 5.5440e-02 500 100 Step LOSP-2H l j l 0.046 5.5500e-02 ; 0.M8 5.5920e-02 l 0.05 5.6030e-02 0.052 5.6560e-02 1 0.054 5.7220e-02 1 0.056 5.7820e-02 0.058 5.7910e-02 ! 0.06 5.8010e-02 4 1 NUPIG/CR-6143 G-224 Vol. 2, Put 2 A
LOSP Frequency Step LOSP-2H - 0.062 5.8350e-02 l
\
0.064 5.8710e-02 0.066 5.8990e-02 0.068 5.9010e42 0.07 6.0020e-02 I 0.072 6.0440e-02 1 0.074 6.I140e-02 0.076 6.1280e-02 ) 0.078 6.1720e-02 0.08 6.1910e-02 0.082 6.1960e-02 j 0.084 6.2780e-02 l 0.086 6.3440e-02
]
0.088 6.3460e-02 l 0.09 6.4430e-02 0.092 6.4440t 02 0.094 6.4730e42 0.096 6.4780e-02 i 0.098 6.5040e-02 l 0.! 6.521De-02 ! 0.102 6.5240e-02 ) 0.104 6.5490e-02 i 1 0.106 6.5590e-02 0.108 6.5590e-02 i 0.I1 6.5650e-02 l 0.112 6.5690e42 0.I14 6.5740e-02 0.I16 6.5780e-02 0.118 6.6170e-02 0.12 6.61 a-02 i 0.122 6.64;50e42 0.124 6.6760e-02 0.126 6.6800e-02 0.128 6.6990e42 Vol. 2, Part 2 G-225 NUREG/CR,-6143
l LOSP Frequency l l Step LOSP-2H 0.13 6.8150e-02 0.132 6.8160e-02 0.134 6.8520e-02 0.136 6.8610e-02 0.138 6.8870e-02 0.14 6.8890e-02 0.142 6.8890e-02 0.144 6.8980e-02 0.146 6.9110e42 0.148 6.9270e-02 0.15 6.9470e-02 0.152 6.9730e 02 0.154 6.9730e-02 0.156 7.0500e42 0.158 7.0560e-02 0.16 7.0970e-02 0.162 7.0980e-02 0.164 7.1680e-02 0.166 7.1740e-02 0.168 7.1880e-02 0.17 7.2120e-02 0.172 7.2290e-02 0.174 7.2350e-02 0.176 7.2850e-02 0.178 7.2950e-02 0.18 7.3010e-02 0.182 7.3490e-02 0.184 'i.3660e-02 0.186 7.3730e-02 0.188 7.3740e-02 0.19 7.3900e-02 0.192 7.3960e-02 0.194 7.4020e-02 0.196 7.4260e-02 c-226 Vol. 2, Part 2 NUREG/CR-6143
LOSP Frequency Step LOSP 211 0.198 7.4350e-02 0.2 7.4350e-02 0.202 7.4480e42 0.204 7.4560e-02 0.206 7.4570e-02 0.208 7.4740e-02 0.21 7.4780e-02 0.212 7.4790e-02 0.214 7.5430e-02 0.216 7.5460e-02 0.218 7.5570e-02 0.22 7.5820e-02 0.222 7.5950e-02 0.224 7.6280e-02 0.226 7.6310e-02 0.228 7.6370e-02 0.23 7.6530e-02 0.232 7.6720e-02 0.234 7.7310e-02 0.236 7.7570e-02 0.238 7.7640e-02 0.24 7.8390e-02 0.242 7.8420e-02 0.244 7.8510e-02 0.246 7.8510e-02 0.248 7.8520e-02 0.25 7.8610e-02 0.252 7.8740e-02 0.254 7.8830e42 0.256 7.8840e42 0.258 7.9000e-02 0.26 7.9040e-02 0.262 7.9400e-02 0.264 7.9620e-02 Vol. 2 Part 2 G-227 NUREG/CR-6143
LOSP Frequency Step LOSP-2H 0.266 7.9790e42 0.268 7.9880e-02 0.27 7.9880e-02 0.272 8.0200r02 0.274 8.0240e-02 0.276 8.0240e-02 0.278 8.0250e-02 0.28 8.03Me-02 0.282 8.0800e-02 0.284 8.0940e-02 0.286 8.1070e-02 0.288 8.1390e-02 0.29 8.1410e-02 0.292 8.1510e-02 0.294 8.1940e-02 0.2% 8.1990e-02 0.298 8.2130e-02 l 0.3 8.2450e-02 0.302 8.2530e-02 0.304 8.2690e-02 0.306 8.2780e-02 0.308 8.2820e-02 0.31 8.2980e-02 0.312 8.3160e-02 0.314 8.3230e-02 0.316 8.3270e-02 0.318 8.3390e-02 0.32 8.3430e-02 0.322 8.3610e-02 0.324 8.3670e-02 0.326 8.3810e-02 0.328 8.4310e-02 0.33 8.4320e42 0.332 8.4330e 02 l l NUREG/CR-6143 G-228 Vol. 2, Part 2
LOSP Frequency Step LOSP-2H 0.334 8.4430e-02 0.336 8.4430e42 0.338 8.4750e-02 0.34 8.4900e-02 0.342 8.5410e-02 0.344 8.5420e-02 0.346 8.5440e42 0.348 8.5870e- 2 0.35 8.5970e-02 0.352 8.6010e-02 0.354 8.6420e-02 0.356 8.6470e-02 0.358 8.6620e-02 0.36 8.6740e-02 0.362 8.6860e-02 0.364 8.6890e-02 0.366 8.6900e42 0.368 8.6940e-02 0.37 8.7210e42 0.372 8.7320e-02 0.374 8.7530e 02 0.376 8.7550e-02 0.378 8.7910e-02 0.38 8.8160e42 0.382 8.8530e-02 0.384 8.8540e-02 0.386 8.8590e-02 0.388 8.8930e-02 0.39 8.9190e-02 0.392 8.9480e-02 0.394 8.9730e-02 0.396 9.0060e-02 0.398 9.0090e-02 0.4 9.0430e-02 Vol. 2, Part 2 G-229 NUREG/CR-6143
LOSP Frequency . Step LOSP-2H 0.402 9.0790e-02 0.404 9.1050e-02 l 0.406 9.I120e-02 , i 0.408 9.1130e-02 0.41 9.1270e-02 i 0.412 9.1310e-02 I 0.414 9.1550e-02 i 0.416 9.1560e-02 j 0.418 9.1670e-02 ' O.42 9.1740e-02 -i 0.422 9.1830e 02 0.424 9.1960e-02 0.426 9.2140e42 I i 0.428 9.2320e42 0.43 9.2580e-02 ' 0.432 9.2640e-02 0.434 9.2640e-02 0.436 9.3230e-02 0.438 9.3740e-02 0.44 9.3740e-02 0.442 9.3800e-02 0.444 9.4090e-02 0.446 9.4200e-02 0.448 9.4540e-02 0.45 9.4560e-02 0.452 9.4750e-02 0.454 9.4810e-02 0.456 9.4900e-02 0.458 9.5140e-02 0.46 9.5160e-02 0.462 9.5290e-02 0.464 9.5300e-02 0.466 9.5550e-02 I 1 0.46S 9.5580n2 v NUREG/CR-6143 G 230 Vol. 2, Part 2
LOSP Frequency Step LOSP-2H 0.47 9.5720e-02 0.472 9.5830e42 0.474 9.5900e-02 , 0.476 9.6260e-02 0.478 9.6350e-02 0.48 9.6390e42 0.482 9.6520e-02 0.484 9.6540e-02 f 0.486 9.6680e-02 0.488 9.6770e-02 0.49 9.6820e-02 0.492 9.6840e-02 : ( 0.494 9.7090c42 O4% 9.7120e-02 0.498 9.7140e-02 r 0.5 9.7160e-02 t O.502 9.7570e42 0.504 9.7670e42 l 0.506 9.7860e-02 0.508 9.7910e42 , 0.51 9.8020e-02 0.512 9.5040e-02 0.514 9.8770e-02 0.516 9.9090e-02 0.518 9.9090e-02 0.52 9.9360e-02 0.522 9.9450c-02 0.524 9.9550e-02 0.526 9 %10e-02 0.528 9.%80e-02 0.53 9.9810e-02 0.532 9.9840e-02 0.534 1.0020e-01 0.536 l 1.0030e-01 Vol. 2, Part 2 G-231 NUREG/CR-6143
LOSP Frequency Step LOSP 2H 0.538 1.0050e-01 0.54 1.0050e-01 0.542 1.0060e41 0.544 1.0110e-O1 0.546 1.0150e-01 0.548 1.0150e-01 0.55 1.0160e-01 0.552 1.0170e-01 0.554 1.0180e-01 0.556 1.0230e-01 0.558 1.0260e-01 0.56 1.0330e-01 0.562 1.0330e-01 0.564 1.0360e-01 0.566 1.0380e-01 0.568 1.0380e-01 0.57 1.0400e-01 0.572 1.0420e-01 0.574 1.0520e-01 0.576 1.0540e-01 0.578 1.0540e-01 0.58 1.0550e-01 0.582 1.0550e-01 0.584 1.0600e-01 0.586 1.0660e-01 0.588 1.0660e-01 0.59 1.0670e-01 0.592 1.0690e-01 0.594 1.0710e 01 0.596 1.0720e-01 0.598 1.0740e-01 0.6 1.0750e-01 O.602 1.0750e-01 0.604 1.0790e-01 NUREG/CR-6143 G-232 Vol. 2 Part 2
l LOSP Frequency Step LOSP-2H 0.606 1.0800e-01 , l 0.608 1.0810e-01 0.61 1.0820e-01 0.612 1.0840e-01 O.614 1.0880e-01 0.616 1.0890e-01 j i 0.618 1.0890e-01 , 0.62 1.0910e-01 , 0.622 1.0940e-01 l C.624 1.0960e-01 0.626 1.0960e-01 0.628 1.1070e-01 0.63 1.1090e-01 0.632 1.1100e-01 1 0.634 1.1110e-01 0.636 1.1110e-01 ; 0.638 1.1120e-01 , i 0.64 1.1140e-01 i 0.642 1.1160e41 0.644 1.1170e-01 0.646 1.1180e-01 0.648 1.1190e-01 , 0.65 1.1260e-01 0.652 1.1260e-01 ! 0.654 1.1280e-01 0.656 1.1290e-01 , 0.658 1.1320e-01 0.66 1.1330e-01 0.662 1.1370e-01 0.664 1.1380e-01 0.666 1.1410e-01 0.668 1.1440e-01 0.67 1.1440e41 0.672 1.1490e-01 Vol. 2, Part 2 G 233 NUREG/CR-6143
LOSP Frequency Step LOSP-211 0.674 1.1490e-01 0.676 1.1530e 01 0.678 1.1540e-01 0.68 1.1540e-01 0.682 1.1540e-01 0.684 1.1540e-01 0.686 1.1540(A)1 0.688 1.1560e-01 0.69 1.1570e-01 0.692 1.1580e-01 0.694 1.1640e-01 0.696 1.1640e-01 0.698 1.1640e-01 0.7 1.1660e-01 0.702 1.1670e41 0.704 1.1680e-OI 0.706 1.1680e-01 0.708 1.1680e-01 0.71 1.1690e-01 0.712 1.1710e-0] 0.714 1.1740e 01 0.716 1.1740e-01 0.718 1.1750e 01 0.72 1.1800e-01 0.722 1.1840e41 0.724 1.1870e-01 0.726 1.1880e-01 0.728 1.1900e-01 0.73 1.1910e-01 0.732 1.1910e41 0.734 1.1920e-01 j 0.736 1.1940e-01 0.738 1.1970e%1 0.74 1.1980e-01 l NUREG/CR-6143 c.934 Vol. 2, Part 2 I _.___.________________j
I i l LOSP Frequency ) 1 Step LOSP 2H 0.742 1.2010A1 0.744 1.2030e 01 0.746 1.2060e-01 j 0.748 1.2070e-01 l 0.75 1.2140e-01 l 0.752 1.2210e 01 3 0.754 1.2210e-01 0.756 1.2250e-01 0.758 1.2260e-01 0.76 1.2320e-01 0.762 1.2340e 01 0.764 1.2350e-01 0.766 1.2360e-01 0.768 1.2400e41 0.77 1.2430e-01 0.772 1.2490e-01 0.774 1.2510e-01 0.776 1.2520e-01 0.! M 1.2550e-01 0.78 1.2580e-01 , 0.782 1.2610e-01 0.784 1.2630e-01 0.786 1.2640e-01 0.788 1.2660e-01 0.79 1.2670e-01 0.792 1.2670e-01 0.794 1.2670e-01 0.7 % 1.2720e-01 0.795 1.2740e-01 0.8 1.2770e-01 0.602 1.2770e-01 0.804 1.2780e 01 0.806 1.2790e41 0.808 1.2820e-01 Vol. 2, Part 2 G-235 NUREG/CR-6143
LOSP Frequency a Step LOSP-2H 0.81 1.2820e-01 0.812 1.2860e-01 0.814 1.2930e-01 0.816 1.2930e-01 0.818 1.2940e-01 0.82 1.2940e-01 0.822 1.2950e41 0.824 1.2950e-01 l 0.826 1.3070e-01 l 0.828 1.3090e-01 ! 0.83 1.3100c-01 0.832 1.3110e-01 0.834 1.3160e-01 0.836 1.3170e-01 0.838 1.31 % -01 0.84 1.31 % -01 0.842 1.3220e-01 i 0.844 1.3220e41 0.846 1.3230e-01 0.848 1.3240e-01 0.85 1.3260e-01 0.852 1.3280e-01 0.854 1.32 % -01 0.856 1.3320e-01 0.858 1.3400e-01 0.86 1.3450e-01 0.862 1.3480e-01 0.864 1.34W-01 O.866 1.3500e-01 0.868 1.3560e-01 0.87 1.3620e-01 0.872 1.3630e41 0.874 1.3640o-01 0.876 1.36 % -01 NUREG/CR-6143 G-236 Vol. 2, Part 2 ________________________________________.--_______________________I
1 l l LOSP Frequency l Step LOSP-2H 0.878 1.3750e-01 0.88 1.3800e-01 0.~182 1.3830e41 0.884 1.3930e-01 0.886 1.3990e-01 ! 0.888 1.4010e-01 0.89 1.4070e-01 0.892 1.4090e-01 i 0.894 1.4110e-01 l 0.896 1.4110e-01 0.898 1.4130e-01 0.9 1.4130e-01 0.902 1.4160e-01 0.904 1.4170e-01 0.906 1.4210e-01 1 0.908 1.4230e41 0.91 1.4310e 01 0.912 1.4330e-01 0.914 1.4380e-01 0.916 1.4450e-01 0.918 1.4480e-01 0.92 1.4650e-01 j 0.922 1.4680e-01 0.924 1.4730e-01 f 0.926 1.4740e-01 0.928 1.4780e-01 0.93 1.4790e-01 0.932 1.4870e41 0.934 1.4870e-01 ! 0.936 1.4920e-01 l 1 l 0.938 1.5060e-01 l 0.94 1.5060e-01 l 0.942 1.5180e-01 0.944 1.5230e-01 Vol. 2, Part 2 0-237 NUREG/CR-6143
LOSP Frequency Step LOSP-2H 0.946 1.5290e-01 0.948 1.5360e-01 0.95 1.5500e-01 0.952 1.5610e-01 0.954 1.5630e-01 0.956 1.5750e-01 0.958 1.6040e-01 0.96 1.6180e-01 0.%2 1.6200e-01 0.964 1.6230e-01 0.966 1.6270e-01 0.968 1.6310e-01 0.97 1.6390e-01 0.972 1.6410e-01 0.974 1.6470e-01 0.976 1.6470s-01 0.978 1.6540e41 0.98 1.6600e-01 0.982 1.6680e-01 0.984 1.6730e-01 0.986 1.6920e-01 0.988 1.7060e-01 0.99 1.7970e-01 0.992 1.8260e-01 0.994 1.9230e-01 0.996 1.9510e-01 0.998 2.0280e-01 1 2.3930e41 NUREG/CR-6143 G-238 Vol. 2, Part 2
e _L E RA-LDSP-2H 1 0.8 e 55 0.6 - e c
= m y 0.4 0.2 0 :
0 0.2 0.4 5 s Frequency of LOSP j N h w Nure Attaciunent G-471 Example Plot of Cumsnulative DistribuGon Function 43
a s i m i RA-LOSP-2H-Binned g e 1- .. 0.8 .. g .. 50.6 g .--. e m " s a04 O . 0.2 .. 0 : : 0 0.2 0.4 Bin Midpoint Figure Attachment G-47-2 Example " Stair-Step" Plot of Cummutative Distributum Functmn
i I Appendix II. Event Trees nis Appendix contains various event trees that are II.2 Transfer Event Trees not in Section 6 of this report. Sections 6.2 and 6.3 provide the top level event trees for II.1 Generic System-Level Event each initiating event. Section 6.2 provides them for Trees 8Pecific transient initiating events, and Section 6.3 provides them for each LOCA initiating event. Rese top level trees transfer to numerous other event trees,
%e generic, system-level event trees for transients S me of the event trees transferred to are the generic, are included in Figure H.1-1 through H.1-93. The purpose of each tree is described in Section 6.1, and system-level event trees of Section H.1; other special event trees transferred to are included in Figure H.2-1 the acronyms used in the trees are defined in Section through H.2-84. The acronyms used in the trees are 6.4.
defined in Section 6.4. Vol. 2, Part 2 H-1 NUREG/CR-6143
z m E k 8 B Pt3 A5 ISO ISSDC RLOSP DV1-2 HPCSA XTEB SEO # OUTCOME , [ H g 8 1 T Eo a 2 T EP 1 RHR Loop E 3 *NOT-DEVELOPED l , 4 T EX 5 T *CCN m 6 T EA 7 T EAP 1 8 eNOT-DEVELOPEO l , 9T BX 10 T eCCN so e 1 Sequence logic not developed Sequence frequency below 2 truncation
= c: in POS 5, o feedwater line break LOCA that is isolated = 4. is hke o loss of shutdown cooling transient.
y See A5 event tree notes. I 4, E l m O H k \ u
e ADEP STSRV RWCUC SDCUt STISO SDCBS SDCA ADHR1 'J SEO # OUTCOME E w 1 eNOT-VALD 2 T L 3 T L 4 T L l , 5 T L 6 T E 7 eNOT-VALO 8 T E
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( Event Trees i O Q l W h 1 o i I o n n 1 O O o zxxxzx e _; a w e w www w a ~ cN rn + ta to \ w l
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2 T EAP1 i 3 T LP 2 4 T LP o- Set 'ADHIS* to TRLE in d event trees trmsferred to (SDC has already isolated wNch also isolates ADW from overpresstre) 1 ADW isolated, no overpressmzoton 2: Overpressurize ADW so e Y Y w Z D d m H k E k a N
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A1ADX RHRP SDCL iSOAD SEO # OUTCOME E u
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(!i CAUX ISTCT CTGOP OPICT CTISO SPC CS EOSTM SEO # OUTCOME w o esec 1 eOK ' 2 eOK 1 men 3 eOK 2 4 4 eOK 2
, 5 eOK 3 Qn" 6 T CC 4 EPyn 7 *OK 8 eOK open , 9 eOK 10 T CC
@q coseo 11 eOK 12 eOK C open 2= 13 eOK b* 14 eOK 4: 6 '
15 T CC C n open
> b* 16 eOK E 17 eOK H , 18 eOK 3 19 T CC a: Susceptibthty, of core coolino equipment to steam out open containment into auxikary bulding t if containmnet cbsed, steem con overpressurire containment if no suppression pool cooling, but failure of containment is into shield building and this has no ef fect on core cooling equipment per RREG 4550 2: No steam since SP 'rs cooled 3: Equip. not demoged by steam 4: Eqwp. rendered enoperd>Ie due to ef fects of steam C
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% ,a 1 eOK 1 2 eOK 1 open 3 eOK 2 se 4 eOK 2
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- i , 14 eOK
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>t 16 eOK 17 eOK Z , 18 eOK g 19 T CCP a: to steam out Su+ceotibihty. of core cooliopen b conto:nment into ouu. equ<pmentory ' uilding 1 If contoinmnet closed. steem can overpressurize containment if no suppression pool coohng, but f ailure of containment is into sn. erd budding ond tNs has no ef feet on core cooEng equipment per NUREG 4550 2: No steam since SP is cooled 3:
4: Equip. Equip.not damaged rendered byrabe inor ; steam due to ef fects of steam C W tu a w 6 i.
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a: Susceptibility of core cochno eqv:pment to steam out open cont'ainment into ouxiliwy building 1 if contoinment closed, steam con overpressurize containment if no suppression pool cooling. but failure of contoinment is into sheid buildng and ths hcs no etfect on core cocing equipment per NUREG 4550 1 4 . 2: No steam since SP it coofea
- 3: Equip not domoged by steam 4: Eqvp. rendered .~ ape oble due to ef fects of steam o
f - M ' 2 a tJ
Event Trees 8 888888888888888888888888888888888888888888888888888888888888 , W W W O"* >* W h= W W W W >* >* W h* W W W f'* W >* >* >* W W W W >* W W h= W hw h= W Q= >e >e >= > l=* >* W W W W W W W W >m W ho pen W W W &_ W W o """'*****p;onsownseRamaRRRRRR8agAggg4ES?;00:0*00082222ssass8 bi i g __ __ __ __ __ __ __ __ __ __ __ __ __ __ __ __ __ __ ____
~
t 8 i I } l .- lI .. b [b If Is l } Il 3 J b It 11 1 I G G B l l^ l Figure II.1-16 CB Tree l Vol. 2, Part 2 H-17 NUREG/CR-6143 1
i!lli .'l ' lll1l il ll! m<8U1 E , M O C T U DDDDDDDD O CCCCCCCC l 1 O 234S678 E S T N ,' ,' ,' ,' E V 2 H S T G S 1 B C Ya :.rG n3" k I C zCp$anha =A" <E " ?2 N
m s
~
E M O C T U DDDDDDDD O CCCCCCCC 1 O 2345678 E - S - T N ,' ,' ,i ,' E V 2 H S T G S P 1 B C n 5%. 5oO3 4e*k <E" 2a9 %*.* zC #en'A 6Iw
i H1 E
~ M O
C T U DDDDDDDD O CCCCCCCC 4 1 O 234S678 E S T N ,' ,' ,' ,' E V . 2 H , S T G = S , X 1 B C g g o b ;:. s n3xHk cha,ic e <b ". n9
- i
Event Trees i O o b o OOOO 0000 O "NOT w W l l w g __ m m N co o Figure 11.1-20 CB2 Tree Vol. 2, Past 2 H-21 NUREG/CR-6143
Event Trees 1 i l 1 l 1 l l N O O b o OOOO 0000 o "NM to w t i t;; O
,N -- --
(n F-o tn m h O b Figure 11.121 CB2P Tne NUREG/CR-6143 H-22 Vol. 2, Part 2 i l
Event Trees i l 5 o o o ocoo 0000 4t-o w
" N ro t i m
w I i l N -- -- 7 i m 5 m X N cn o Figure II.1-22 CB2X Tree Vol. 2 Part 2 11-23 NUREG/CR4143
M C " w y CBN !STCT CTGOP OPICT CTISN CTISL SPC CS CSNHX SEO f OUTC0hE q a a l M 1 T1 CD E j k a - 2 T 3 T Q CD e l 4 T CD 5 T CD l 6 T Q 7 T CD t w w . cai w ce2 sm -. co n tz Z Hs 2 b a w
M* s _ E 6 O C T 9PPPPP PP1PPP222222FPPPPP222222222222222222PPPPPPPPPP9PPFPPPPPPPPPPPP0PPPPPPPPP9P9PPP222222222222222222 U O 888888888888888888888888888888888888888888888888888888888888 CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC _ l TTiTTTTTTTTTTTTTiTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTTiTTTTTTTTT Q 123456789 1 0123456789 1 01234567890123456789012345678901234567890 1111111122222222223333333333444444444455555555556 E S X -r" H N .h S C l S ,i ,i ,i 1i ii ii ii ,i ii 1 ,i ,i ii ,a ii ,i ,1 ,i ,i ,i C l C P S . , l T R w
=
= W w
nc m " e .. C O S G
- _
T C l T -v =- C P O _ P O
* ~ _
G T C
*=
T = - - _ C __ T _ S _ P B C 3gcg O' .% Ot*2 U {="38
,+* ZCWmQN:&EW =
<!- M, 'a2 N
Z to C 1 M 5 g CC GTCT CTGOP OPCT CTGO CTISL SPC CS CSNHX SEO ( OUTCOhC Q
~
0 i i i CC1 3 M i 2T CC1 8 6 3T CC1 w , 4T CC1 W i - 5T G1 6T CC1 w , 7T CC2
% i 8T CC2 9T CC2
, 10 T CC2 i 11 T CG2 12 T CC2
, O T T1 i 14 T CC1 15 T CC1
*"8 i 16 T CCI i 17 T CC1 18 T CC1 i
19 T CC2 s, < 20 T CC2 21 T CC2
- , 22 T CC2 i - 23 T CC2 24 T CC2
[ c , 25 T 26 T CC2
;) y i 27 T CC2 CC2 i 28 T CC2 .E 29 T CC2
% 7 w i 30 T CC2 4 h
- p* i 31 T CC2 y 32 T CC2 O
i 33 T CC2 0 , 34 T CC2
- i 35 T CC2 s' 36 T CC2 3 i 37 T CCI i 38 T CC1 39 T CCI
% , 40 T CC1 i 41 T CCI 42 T CC1
, 43 T CC2 i 44 T CC2 IW 45 T CC2
, 46 T CC2 i 47 T CC2 48 T CC2
, 49 T CC2 i . 50 T CC2
- 51 T CC2
- 52 T CC2 i . 53 T CC2 54 T CC2
, MT T2 i 56 T CC2 T 57 T CC2 o , 58 T CC2 P i 59 T CC2 9 60 T CC2 E
u
E84i E _ M 0 C_ . T U DDDDDDDD - O CCCCCCCC - 1 O 2345678 - E S T N ,' ,' ,' ,' E V . 2 -. H S - T _ G . S . 1 C C 3 k %.E* nO sk & " ,E N *ti zCho8:36e
E H1 E V O C T U DDDDDDDD O CCCCCCCC 1 O 2345678 E S T N ' ,' ,' ,' E V 2 _ H S T _ G S P C C 2 E a :. b nO sH k 1 Eha6e - <E. ". aw
5!*I E M O C T U DDDDDDDD O CCCCCCCC 1 O 2345678 _ E S
'T N ,' ,' ,> ,'
E V 2 H S T _ G S X 1 C - C .
?!5 nOxHR
<E " mb u W 5me96e
z m C n 8 g lC8X l sTCT lCToup l orcT l CTso l CTa l sai l Cs lCsma j sto a ouTC x a a W M 1 T C8tX i l 2T GM O" 3T GM
*"* ' 4 T C8tX 5T C81X 6T C81X
- , 7 T G2X ee i 8T C82X 9T C82X
, 10 T C82X i 11 T C82X 12 T C82X
, 13 T C81X i 14 T C8 tX 15 i C8tX
*=8 i 16 T C8 tX i r- 17 T C8tX 10 T C8 tX
, 19 T C82X 1
- e. - e hf 22 T h
C82X
~ i 23 7 C82X
- 24 T CO2X 25 T CB2X h @
i 26 T C82X Z 27 T C82X
, 28 T C82X
% Y , i 29 T w2X 6 ,N
- 30 T CB2X o , 31 T C82X O 4 32 T CB2X g _
33 T C82X y' + , 34 T C82X 35 T C82X d i 36 T C82X 2 e , 37 T GM i 38 T CBtX
""'** , T C8 i 41 T C8 tX 42 T C8tX
, 43 T C82X s.,-
i 44 T C82X 45 T C82X
, 46 T C82X i 47 T C82X 48 T CB2X
, 49 T C82X
- i 50 T C82X w" " 51 T C82X 52 T C82X 53 T i
i C82X 54 T C82X
, 55 T C82X i 56 T C82X
- 57 T C82X
, 58 T C82X 59 T C82X o
i 60 i C82X
.N a
w
Event Trees , 5 O T U O o, eob 3 w R
- 3
===
a o "N % N s i t
?
.n -- 1 8 0
.e z -- 7 S-s o @S 6
Figure H.1-30 CSTMN Tree Vol. 2, Part 2 H-31 NUREG/CR-6143
Event Trees 1 l l l 1 l 1 l l 1 l l
)
l i l l l l N o O b o Oi
- o. o O "m N
s Di _ O La G. 2 Di u Figure II.131 CSTMP Tree NUREG/CR-6143 H-32 Vol. 2, Pan 2
1 l 1 Event Trees 1 l l l l l l l l
's o
u YX o o CD eO O "N w (n I 1 2 l th -- 0 : w X 2 th o l I Figure H.1-32 CSTMX Tree l Vol. 2, Part 2 H-33 NUREG/CR4143
Event Trees l 1 1 l l I i l 1 1 I i l N o o b o 0000 u000
- st:
w o " Nro v W w I g . 1 m 1 & \ o 1 m l N o l 0 Figure 11.1-33 CC2 Tree NUREO/CR4143 }{.34 Vol. 2, Part 2
Event Trees 1 I l i O O O 0000 0000
- st:
O "NM ) d i. 1 <.. 1 N __ __ 7 l w , O w Q. N O O Figure 11.1-34 CC2P Tree Vol. 2 Part 2 11-3 5 NUREG/CR-6143
'; l1 li l! !l!i m#g41 E
M O C T U DDDD O- CCCC 1 O 234 E S T N E V 2 . H S T G S ~ X 2 . C C
- . tu
= et u
- OO9X H,k ZC@oa,b0 WaO <b".2 u
,lll l ,'l1 ii m<k ~ 5. 4 E
O PPPPPP PPPPPPPPPPPP C T FPPPPP222222PPPPPPPPPPPPPPPPPPPPPPPPPPPPPP 222222222222222222 U GCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC CCC 222222222222FPPPPP 2 222 O CCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCCC iTTTTTTTTTiTTTTTTTTTTTTTTTTTTTTTTiTTTTTTTTTTTTTTTTTTTTTTTTTT I 123456789 1 01234567890123456789012345678901234567890123450l 530 _ O 1 1111111122222222223333333333444444444455555*i- 56 E _ S X H N ' , S C S ii ii ,i ii 1i ii ii ,i ,i ,i ii ia ii ii ,i ii ii ii 1i ii C C P S - L S I T
- w C
O "* -- G T C T C e* .- P O P O
,v *l
*l l
i G T C , T e C T 5 f P C C qAc@ =~." y OOT i"Q
<E.". 3w
- GJ
- - 7CymC~Q 1 6Em ,
m m
Z tr1 C <
- c I g
~
CCX 15TCT CTGOP CPCT CTISO CTf5L SPC CS CSNHX SEO f OUTCOME
, 1 i CCix 3 Q' i 2T MN 2 3T CC1X ha
= ,
i 4T 5T CC1X CC1X w 6T CC tX w , 7T CC2X
% i 8T CC2X 9T CC2X
, 10 T CC2X i 11 T CC2X 12 T CC2X
, O T MM i 14 T CC1X 15 T CC1X
= , 16 T CC1X i 17 T CCtX
, 18 T CC1X i
, 19 T CC2X i 20 T CC2X 21 T CC2X
, 22 T CC2X -
i 23 T CC2X 3 24 T CC2X
$-s e 25 T 26 T CC2X CC2X
* '*8" i
27 T CC2X
* , 28 T CC2X i 29 T CC2X y
w Gw y'*" 30 T CC2X
, 31 T CC2X n e i 32 T CC2X n v 33 T CC2X x ,
i 34 T 35 T CC2X CC2X d 36 T CC2X l , i 37 T 38 T CC1X CCIX 39 T CCtX l** 40 T CCtX ( I , 41 T CC1X 42 T CC tX 43 T CC2X l 44 T CC2X
=% 45 T CC2X 46 T CC2X l 47 T CC2X 48 T CC2X 49 T CC2X
! , 50 T CC2X 51 T CC2X w 52 T CC2X j , 53 T CC2X 54 T CC2X 55 T CC2X l 56 T CC2X Y 57 T CC2X
< ' 58 T CC2X
- 2. 59 T CC2X y 60 T CC2X a
tJ
Event Trees i
)
l Y 8 5 8888888 sssssss take o ' Nmvotos W M b 0 u S d D z (4) __ __ g, O & n 1 8 s g __ __ B . b E 8 I U ' n l B Ii
= ^5
\
z . 8 d a l Figure !!.1-38 CCN Tree Vol. 2, F art 2 H.39 NUREG/CR-6143 l l
m<Bq , m a t e s f t u o E o t c M 1 2 m me af O a e e fe C t s t s o T K o U 0B t yt te O +C i u m re
-, =ie T # 6er- t s't c O
E 1 2 gt n-e+ t e n w S 4, nt dMs-c ei n f o ,m et c g ru u o q coe id %E E M fcs octu t2 T S o ,' yso O t EEA E hWC t O p L en cee spn M S uok T S : c C
- 1 o
sk = nM: -m3 zCWmo W&rw o <S ". 29
-[ DEP STSRV OPDEP SDCUI STISO SDCBS SDCA ADHR1 SEO # OUTCOME E
l g b C d 1 eNOT-VALID i 2 T L'
, 3 T L i ,
4 T L ' 5 T E2 6 eNOT-VALID 7 T E 8 T OVPR m
? a: All SRV's initially available during HYDRO. In all 3
trees transferred to, do the following:
- C Re lace event 2SRV with 2SALL, Ik Re lace event 1SRV with 1SALL, P,i Re lace event 1SRVS with SAFE.
3 c: Since SDC with RHR and ADHR is isolated, set ever lt OPIS il to 'Yes' in oil trees transferred to, and se t event SDCL to 'Yes' in all event trees transferred to. OPDE nce war ($ronsf fom kDRO cnd d- On ok / ired for low
' varu urwumma where operotor lowers level to 2: Transfer to E is conservat,ve for some recsons as in note 1 2
C E I B 9 t 5 e a
d<8** t @g
*3 85 E*
0 C T CCC CCC CCC CCC F U CCC CCC CCC CCC O EEEFFEEE FFEEEFFEEEFFFSSEEEFFEEEFFFEEEFFEEEFFFSSSOS TTTTiTTT TTTTTTTTTTTTTTiiiTTTTTTTTTTTTTTTTTTTTTiiTi D O f O 56789012345678901 Q 12345678 1 1 012Ow5E1sB 222222222333 1 1 1 O123456789012MM33333444444444455 L F A E S n e e l m see M 4 l SI H i' i' M P O ee f O P II g II II II ;I II II g L l - S C P L Ii iI II iI II gi gI iI g.. .
, g_
l v t o t " ' W_ l g.g P 5 . M l P S . l 5 1 g2 r I V R 5 g-l 1 a, . s v ** m-n t P l O
" y. .
R 5 V I
. ~. .
=e 2 .
.. Y .
l
" %L W
l C R V S We 5 mXS e E t n. a g u
- r m.a_..
P va ., 0 e . l V - " W d t
.e t
m 5 r e. a M G
' e. .
o s y l S W . '
. _ mp C
w.a E . P _ l 0 t.
.:p .
E . m.t l 1 3 soc 2 ===.wL g *124 Zcxg~OM6 D %SN f.9,52N I
1 Event Trees 4
. n en..en.en.,a.en en..~.. en en .= o= -en.,en .,. . w E ~~- o te r
.....s::meer:rammans;wns:nsammnssssssssseemceteess E
t g __ __ _'_ _ __ __ __ __ __ __ __
]
[ ._ __ __ __ __ _ __ __ _ __ _ __ g [ m._t 1 1; . . t i. :s. I _ a i
$ }{ II l ' f l _ .__ _. _ _ _
4 [I y l t
- 'i.l ff9 1: , g' I 4
l -- -- g 4 p.. I. t. ; g . T . b i 6 " i i l i .i T I ll g is l g e l lil I'Ia s: .
.E D
il ! ll 5 - b g : :- 1 i l Figure H.1-42 EA Tree , Vol. 2. Part 2 H-43 NUREG/CR-6143 ;
= k s2g
, PP PP PPTC PC P P P P P[ $PP P
P P C$p P P PCWFFTSEE PP PPP P
, EEWFDCC FFFEEWFE CC PPPPSEPT FF $PP EFF WRS$(9E P C FF EFFFEfFFEE PP PCC PPCCC FEEE P $PP F LS $ps YT TTTT TTY 7ihYT iTiTTY TTT 1?T TTi YYITTTTT 7TTTiiiTTTY TTTT i TTIy 1
1j4S67 c 0123 1 11 $471 012345 222222 99 22 Rf5pNM0 4 234 s769O1$ 44I444S$ $SS 5 4 SM7 n01234 5 666666 66677 8901 77SM3aig 4 7 l j c l o i' iI i' l l - l iI l 73 I t - l e 's i ii 3 i' ' 'g gI I' g' y' i I1 j u 4, P s s j l s
. ll i1 li o _
j _ P i' 'I j
.P l
m v
,s j
l
= ,
H v e s s c l M e t l 33 e * ,*"* ] f>T y.c# f ,= 6 zC m ~Oyb**AW
- A <O~~ N. T>3 N lIl ,'l' 1
ll' 1llJllilll1l;llli' kE a32 E X - C C X XX XX XX XX XX X T XX XX XX XX XX XX - U CCXCCXXCCXCCXXXXCCXCCXXXX XC CCXXCCXCCXXXXCCXCCXXXXXXXFX O EEFEEFFEEFEEFFSSEEFEEFFSSkEeEEFFEEFEEFFSSEEFEEFFSSLSSOS - TTTTTTTTTTTTTTiTTTTTTTTiT TT;TTTTTTTTTTTTTTTTTTTTTiiTiTT f 123456789012345678901234567 2n333333333444444444455555555 1 123456789 012345 8 0 0123M5678M222222 1 T1 1111 1 l M l S H P O l O P L l S C ii ii ii ii ,i ii ii ,a ii ,< ii ,i P L l V f- !! v P S f , P S g SI f 8 V R S 1 l S H l] il jl l1 D A l lj 1i R l A S P O l V S P1 O l B V R S 2 l N S M l v S p v O l V SJ G l S C E F C l X A E 5 80%re b e ;ryy'r H'S <2.
.:2PJ ; ZCW DsIw l
iI i- ,' .t 'r 6' g g -H - ta o C K m m m m K K KKK KK 0 =+CfSeee55So55gs55.m mO0 K K KK O e $S5e5$SeSsse m o5sses$ 0
+ 5I30C*CIS+00C 83 0 0 e S5S00e e[S$5 _
YTT 7YT Trr TTT iT Y T YIT 7 yT 77T YYT TT' TiTT yTTT 1 1 4S6789 0123 6 e e Q E V1Eca5b ss2222 1 2$ E33 12 N33333N2345676901 56789 4444444455 g55355
.5 66666yM6M9 12345 .
S l M T 5 e 0 _ h _ P e m ' < a ,' . P l 1 1 U , ' ; ; I ! .' I' 3 N l m
,i l l l l l i' l I' Ii l
T N E v . l h S , C l C F S , l
= "
O S T1 C l T C P O P O O l T C
= h T
C T S L a**
"h W
l * = s - ." = e." W. C e -*= eu E 1 1 -
..TF.
=l.
l s e m.c:%"". a.~
. . y.e. **
g.. .
- e. .
2 s. ,-
- C w
e s
- Cm e g *= _
ia e e yA5 %LM(A NO d@et 1 ZCMtOsON5*" T 4 ". Un3 "s N _
, ECNP iSTCT CTGOP OPICT CTISN OPSPM SPMUN SPMKN EOSTM SEO # OUTCONE . E N a b 1 eCK cbsed 2 T SNP 3 T SNP
, 4 e0K i '
I 5 T SNP closed 6 T SNP
. 7 e0K
* " "9" 8 T CCN 9T SNP 10 T SNP open s e , 11 *OK 3
= """* 12 T CCN 13 T SNP
$ 14 T SNP
' , 15 eOK 16 T SNP
'I* km closed 17 T SNP 18 *0K Qm *"*" 19 T CCN 20 T SNP H " " ' "
21 T SNP 3 , 22 eOK i ' 23 T CCN 24 T SNP 25 T SNP
" 5.#erNs'd'It ovi'2gc gve u gw, cgt ougtic,s tree.
E o- % ,0... % ,a ,ocr a mm o se u t,e. [~ s E 1
1 T t< ag Cn o C R KKK K K KKK K K KKKP kKKP KKK K K KKKP KKKP O I
+*e SSe S+ P000P P0PPP0PPP000CPPP00O(PPP000PPP0PPP0PPP000C 00CTPPOTPP0PTSe*+SPS*SSSeSSS*+*CSSSe*oCSSSee*SSS*SSS+SSS+*+C7PPO00CPTT SSo**C TTT TTT TTT TTT tit TTT TTTT TTiT TTT TTT TTT T7TT TTTT .
f 1234567891012O145678N222222222233333333334444444444555555555566666666M67 1 Q E 1 1111 012345678901234567890123456789012345678901234567 90 S l u T S O E l P
* ' v' Pr S
f 1 W P
' ' ' ' l l I' _
S _ l _ W _ P . S ,i l l l i l ,, l 'i f* I' P 0 l T N E V l T _ N V P 0 l 5 C l C P S l O S T C l T C P O l P 0 0 T C l T C T G f P C E 3oCQ s Z**Lq MO"U q,e4 C aM4. At.
. a
.a- 1oo -
2 )b
<O -* N.
- lI ,l.l'll.I ,i i
1 t<8 T . ,I t r o C < K K (KC K ( KKK CKKx K(( K ( KKKx K Kx 5 XOXxxO00 XX0C0 SeSSSe+*TSSeeeESSS***5SS*SSS*SSS+++CSSS*XrX0O0xXX0XXr0xxx000CXXr060CXX eCSSS l O 0&*SSS+SSS*SSSe+eSSS*xxx0Xxx0XXXO0OXXX0 YTT TTT TTT TTT TT TTT IT T TTTi TTT T7T TTY T7Ti iTTT i 1 123456769 67 01 45679901 O E 0T234611sB22 t11 22222233E333333444444444455555555S$66656666667456789012345678901234567S901234567890 S - l W T S Q l E
? 1 <' i'
u F S l t u *' '* -* '* pu 2' l S i'
', '1 l 'i 3* 5' m l l } [
l 0 T N E V l r N v p - l O - S C l C P S l O S TI C f T C I P 0 l P O C T l C T C T 5 l X C E l 0 NMC@ =*"h9MlX f d2f a <E M. ,p3 9 * *b@ ZCWmO~ :cb .% 1
Event Trees 5 $$$&&$$$1&E$$$&E$$$EEESS$$$&&$$$EEE$$$&Ebbb&&ESSS$S l o """'**"**s:DesoweseR&RPARRRRR8642488488?;7030307083 W { -- -- -- __ -- _ - g _ __ - . _ _-. __ - . . _ __ __ g __ . - . ._ __ _._ __ _-. . - _ b d g - . - - l $ i 6 Ib Figure 11.149 EP Tree NUREG/CR-6143 }{-50 Vol. 2, Part 2
m V S W P - O V S u S I - S _ C E O X E _ _ 3**C2 " ,*$ M#' H{ <bN.:au -* *. ZCMmQB0be 2
z y C M S 8 F OPFLD ISMSV OFMSV MSV 2SRV OP1SV iSRV SSWXT FW SEO # OUTCOME H n N l I w a
, 1 T FC '
o- Operator instructed to close trXs before FLOOD tra t , 2 T FC 3 T S p 4 T FC cw i ,-' 5 T FC 6 T S 7 T S 2 8 T S 2 9 T FC l , 10 T FC 11 T S 12 T FC c' **d ] , U T FC 14 T S 15 T S 3 open open 16 T S ai5 4 17 T S 3
- one., , 18 T OF 4
~ i , 19 T OF ,
20 T S 3 g { 21 T S s 1 transfer to cont. t tree for ROOD d 9 2: WXs closed. No operated in re6ef.
- 3. Operator es c= ore that t4V4 we pen, he wa not
$ otterrpt floodng Go to STEAW e 4tWs open and floo6ng works.
4: g or nog 5 Oper or not o ore UWs open, but ficodng fckts
- 6. Operator does not atteryt ROOD, Go to STEAM.
.E a
N
,' ,;l i' i
(e :I; a= s 4 45 E 2 2 33 M i O C T KKKK K KKKK L k K KKKK K U _ 0OO0COC00 OOC 0COCOC000OC0CCC O +**+C*C++**C+C*C*C+++*C+CCC T T T T T T T TTT f 2345678 901234D67E9122222222 01234567 1 1 O 1 111 11 E S e e r t M C T S .' ,' d i
'o e:
ot O coN E e r o. T cma M C ,' ,' ite C ,' s P y O t u od e t.b n gr o T C mu c dq e N o r ii ii n e E V f ic e t d we te tb n n eo v u* or f em o r N tPS V P t o
;N o tmgg O~ .
s r
.e F
oM
#rt S
l to n d C of c. dnto
&c o
boie t C f td eo P ub - S edf .e e O tut M sqe ues w c y d e w c 7 ' n r S I c a e T C ' ip u tsm c q ye n e bt s T C i s c e4 m T *i t d eb y I m P O b c e d u ry o o d e n P a s r - p o4 7 Y,fio c o te n O C V 5 hd,a t4 e ne n-T W 7g r r ,. p , C a wu qq
" e ee T
C T c Tt nn nn gg eh e oocc S I r cc c
.t.ee r r n oo
'eco CC .-
45 C h3 F 3RE" ,* ?U mO H3 < " 22O YU Z 1Q' T t 6Iw j
W q1 E M O C T U KKKKPKPKKKKPKPKPKPKKKKPKPPP O C00OC0C0000C0C0C0C0OO0COCCC
*++eC+C++++C+C*C+C+*e+C*CCC T T T T T T T TTT 1 9 2345678 012345678901234567 1
O 1 1111111 122222222 E S M T S ,' ,' O E T M C ,' ,' .' ,' ,' ,' P O T N ,i ,i ,i E V T - N V P O S C C P !) S 0 - 6 - T C T C P O P O C T C T . C T G P C F 1
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