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| | number = ML16054A428 | | | number = ML16054A428 |
| | issue date = 01/26/2016 | | | issue date = 01/26/2016 |
| | title = Monticello - Revision 33 to the Updated Final Safety Analysis Report, Section 14, Plant Safety Analysis | | | title = 3 to the Updated Final Safety Analysis Report, Section 14, Plant Safety Analysis |
| | author name = | | | author name = |
| | author affiliation = Northern States Power Co, Xcel Energy | | | author affiliation = Northern States Power Co, Xcel Energy |
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| =Text= | | =Text= |
| {{#Wiki_filter:SECTION 14 | | {{#Wiki_filter:}} |
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| SECTION 1414.1
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| 14.1.1 14.1.2
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| 14.1.3
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| 14.1.4
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| 14.1.5 SECTION 1414.2
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| SECTION 1414.314.3.1
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| 14.3.2
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| 14.3.3
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| 14.3.4
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| SECTION 1414.4
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| 14.4.1
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| 14.4.2
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| 14.4.3
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| 14.4.4
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| 14.4.5
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| SECTION 1414.5
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| 14.5.1
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| 14.5.2 14.5.3
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| SECTION 1414.6
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| 14.6.1 14.6.2 14.6.314.6.414.6.5
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| SECTION 1414.7
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| 14.7.1
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| 14.7.2
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| 14.7.3
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| 14.7.4
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| 14.7.5
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| 14.7.6
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| 14.7.7
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| 14.7.8
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| SECTION 1414.814.8.1
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| 14.8.2
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| SECTION 1414.1014.10.1
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| SECTION 1414.11
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| SECTION 14
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| SECTION 14AUPDATED SAFETY ANALYSIS REPORT
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| ?l 0 Xcel Energy* 2015 Xcol Enorgy Nuclear Analysi s and Desi gn Page 1 of 19 July 2015 Section Re v is ion: 0 2 19
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| Revis ion: 0 3 19
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| R ev i sion: 0 4
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| se cti ons. A RT S Average Po'vV&r R an ge Mo ni t or , Rod Bl ock M onitor, an d Techni cal Specifi cat ion #
| |
| G ard-e I OffiCi al Core Mo nit or ing S ystem fo*r M onti ce ll o MCPR M in imu m Crit i cal Po\'VG r Ratio OPRM Os cill ation Powe r Range Mon itor Revi sion: 0 5 Option A Sc r am Time rep r esen tat ive of the Tech nical Specification re qu i reme n ts
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| Revi sion: 0 0 I w lo Revi sion: 0 7 19 The fi nal core lo a ding pa ttern an alyzed in th is re port \VaS tr ansmitted to GNF in co rr esponden ce 3). described in Cycle GE14*P1 < < 13 3 781 26 2-17GZ 1 41 n {41 781 27 1 4" {4 338 1 26 ,_ JYS 00 1 04 ,.,.JYY 54 1 Number Of Bundles 0 44 56 24 24 6 Initial Avg.
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| 13 11 l1 3.91 3. 3. 3, 3.89 3.89 Rev i sion: 0 T he min i mum sh ut dovvn margin (SD M) r epo rted bek>w is b ased on mode r ator tem pe r ature of expos u re of11.849 GWD J M'TU corre s ponds to tlile min i mum pr evious cycle expos u re Operations Manua l 8.03.04 .. 05 req u ir es tha t t he m inimum torus water tempe r at u re is greater ca l cul ated SDM resu lt s be l\we n 68°F an d 6S"F is insign ificant as co m pa r ed to t he u ncerta inti es was f ou nd to be suff i cie n t. A co n servative deple ti on s tr ategy was u tilized in t he evalua t ion of st an d by l iquid co ntr ol shutdown margin. The r esuHs p resented are cornsorvatively based on an en d of t ho prevtous reactor, f rom a full po\A/er and m inimum con trol r od invento ry to a sutrc ri tica l cond rtion at any t ime in th e cycle u nder t he most reactive fr ee st ate by the i nject i on of 660 pp m boron.
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| Rev i sion: 0 9 19 This soction ide ntif ies the t ransient and accident an al yses performed as part of the cu rren t cycle the limitations and condi tions. Th ese c ycle-sp ecific H im ita t ions and are me t for Mo nti cello an other i ssue were eva l ua t ed. Th ese eve nt s are listed be l ow.
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| : 1) 2) 3) 4) 7)
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| Event Pr i mary System Pressure Increase Generator loa d Reiectio n wit h Bypass Fail ure T urt:line T ri p with Bypass Fail ure Mai n Steam I sola t ion Valve CloStxe (One I All Vatves) Tu rtine T ri p with Bypass Fail ure w/o Positio n Scram 1 Main Steam I solation Valve Closure Sc ra m Loss of Condenser Vacuum Reactor Vesse l Water Temperature Decrease I nadvertent HPC I Actuat ron wrth L8 T urbine Tnp Posittve Re activity Insertion Rod Wlthdrawa J Erro r Reactor Vesse l Coolant I nventory Dec r ease Core Coolant Flow Decrease T rip ot One Recirc ula tion Pu mp or Two Rearcu!at ion Pumps Rec i rct.Jation Pump Se i zure. Core Coolant Flow I ncrease-Slow Re ci'ctJa t!on Con t rol Failure -In crease (MCP RF) Slow Reci'CIAa tio n Control Fail ure -I nc rease (MAPlHGR,)" Fas t Recircula No n Contro l Failure -I ncrease Stanup of an I dle Recuculat i on LOop Fuel Loading Errors M isp laced Boodte-Acaclen t 1 Performed ror ASME Vessel Overpressure Com pli ance. Revis ion: 0 Current
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| ./ ./ ./ ./ ./ (il SLO) ./ ./
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| Revis ion: 0 Reactor fu ll powe r i nitia l cond itions that app ly to th e lim iting transient an al ysis are summarized transio nt an alyses are fisted in Tab le 4.3. Paramete r Value Va l ue Increased Core Low COfe Fklw Flow Ra t ed Thermal Powe r 2004 46.1 Analysis Powe r I Core Flow Ana lysis Reacto r Pressure Time in Cycle Number of*SIRVs for Analysis 5 i n-serv i ce in-service two
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| Pslg low Vesse l Water L evel Scram 1 %open L ow low Vesse l Water 1 Hig h Pressure Pslg High Reac to r Vesse l Wa ter L eve 1 1 Ps ig Revi sion: 0 1 25 10915 85 85 *55 11 62 11 70 ror be t imes.
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| Op t ion 1 be be Nollimit in g be 2
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| to 3
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| Revi sion: 0 OLMCPR fo r m oasured scram in sertion ti mes. 3 5.2 1 77 1.57 1.62 core monitori ng system use s more de tailed li rrits for e ach f ue l bu nd le latt ice.
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| Rev i sion: 0 15 111 2.1.2 specifica t ion sta t es that the press ur e measu r ed in the r eactor steam dome sh all no t exceed 1 332 Psig. The p ressure safety limit of 1332 Psig as measured in tho ves sel st eam space was derived fr om t he design pr ess u res of t he r eactor pressure vesse l, st ea m space pip ing, and water spac e piping. The pressure safety lim it was ch ose n as the lowo r of th e pr ess u re 1 332 i nitial co n ditions:
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| * 100% (2004 1 105%
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| (60.5 x10 61010.0 1 170.0 1320 T ec h nical SpeciflCat i on li mi t of 1332 Ps i g. Th e calc ulated maximum st eam line pr essure of 1314 1 332 134 4 1 375 Monticello uses TRACG for the MSIV cmure-Wi too ut Position Sc r am analysis.
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| Thi s ana!y sis is rt11 at 1 00%
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| 1 (1010 psig) and uncerta i nty are applied as a pressure adde r to t he res ul t of the event to obtain the fina l r eported
| |
| | |
| Revi sion: 0 rod th ermal*mechanica l des i gn and l icens i ng basis , wit h resped to both steady state operations, and transien t and accident eve nts. Th ermal overpower lim its arc de fin ed to eva l uate t he pote nti al for fuel ce n te rlin e metting. Mec h anical overpower lim its are deftned to eva l uate the pot entia l for f ue l cladding ove rs train. Fe edwater Cont r oUe r Fa aure e vent mecha ni cal design and li oens i ng basis crite r ia for th e plant.
| |
| | |
| Revision:
| |
| 0 To pr ovide Monticello Nu cl ear Generating Pl ant -with opera t in g im pr ovemonts, expanded operating do main an:a l yses were perfor med in Refere n ce 1 fo r maximum extended l oad line lim it r eload an alyses in Reference 1.
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| | |
| Revi sion: 0 A reload DSS.CO eva lu ation h as beo n performxt in accorda n ce Volith t ho l icensing rnGthodolog y 0) tr ip l in ear segment.
| |
| povve r int ercop t WasP.. TRIP Was.p.sREAK RDF-Rec i rc u la ti on Drive F'low
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| | |
| Revi sion: 0 SECTION 14
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| SECTION 1414.1
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| 14.1.1 14.1.2
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| 14.1.3
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| 14.1.4
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| 14.1.5 SECTION 1414.2
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| SECTION 1414.314.3.1
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| 14.3.2
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| 14.3.3
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| 14.3.4
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| SECTION 1414.4
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| 14.4.1
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| 14.4.2
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| 14.4.3
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| 14.4.4
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| 14.4.5
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| SECTION 1414.5
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| 14.5.1
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| 14.5.2 14.5.3
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| SECTION 1414.6
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| 14.6.1 14.6.2 14.6.314.6.414.6.5
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| SECTION 1414.7
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| 14.7.1
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| 14.7.2
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| 14.7.3
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| 14.7.4
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| 14.7.5
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| 14.7.6
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| 14.7.7
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| 14.7.8
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| SECTION 1414.814.8.1
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| 14.8.2
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| | |
| SECTION 1414.1014.10.1
| |
| | |
| SECTION 1414.11
| |
| | |
| SECTION 14
| |
| | |
| SECTION 14AUPDATED SAFETY ANALYSIS REPORT
| |
| ?l 0 Xcel Energy* 2015 Xcol Enorgy Nuclear Analysi s and Desi gn Page 1 of 19 July 2015 Section Re v is ion: 0 2 19
| |
| | |
| Revis ion: 0 3 19
| |
| | |
| R ev i sion: 0 4
| |
| se cti ons. A RT S Average Po'vV&r R an ge Mo ni t or , Rod Bl ock M onitor, an d Techni cal Specifi cat ion #
| |
| G ard-e I OffiCi al Core Mo nit or ing S ystem fo*r M onti ce ll o MCPR M in imu m Crit i cal Po\'VG r Ratio OPRM Os cill ation Powe r Range Mon itor Revi sion: 0 5 Option A Sc r am Time rep r esen tat ive of the Tech nical Specification re qu i reme n ts
| |
| | |
| Revi sion: 0 0 I w lo Revi sion: 0 7 19 The fi nal core lo a ding pa ttern an alyzed in th is re port \VaS tr ansmitted to GNF in co rr esponden ce 3). described in Cycle GE14*P1 < < 13 3 781 26 2-17GZ 1 41 n {41 781 27 1 4" {4 338 1 26 ,_ JYS 00 1 04 ,.,.JYY 54 1 Number Of Bundles 0 44 56 24 24 6 Initial Avg.
| |
| 13 11 l1 3.91 3. 3. 3, 3.89 3.89 Rev i sion: 0 T he min i mum sh ut dovvn margin (SD M) r epo rted bek>w is b ased on mode r ator tem pe r ature of expos u re of11.849 GWD J M'TU corre s ponds to tlile min i mum pr evious cycle expos u re Operations Manua l 8.03.04 .. 05 req u ir es tha t t he m inimum torus water tempe r at u re is greater ca l cul ated SDM resu lt s be l\we n 68°F an d 6S"F is insign ificant as co m pa r ed to t he u ncerta inti es was f ou nd to be suff i cie n t. A co n servative deple ti on s tr ategy was u tilized in t he evalua t ion of st an d by l iquid co ntr ol shutdown margin. The r esuHs p resented are cornsorvatively based on an en d of t ho prevtous reactor, f rom a full po\A/er and m inimum con trol r od invento ry to a sutrc ri tica l cond rtion at any t ime in th e cycle u nder t he most reactive fr ee st ate by the i nject i on of 660 pp m boron.
| |
| | |
| Rev i sion: 0 9 19 This soction ide ntif ies the t ransient and accident an al yses performed as part of the cu rren t cycle the limitations and condi tions. Th ese c ycle-sp ecific H im ita t ions and are me t for Mo nti cello an other i ssue were eva l ua t ed. Th ese eve nt s are listed be l ow.
| |
| : 1) 2) 3) 4) 7)
| |
| Event Pr i mary System Pressure Increase Generator loa d Reiectio n wit h Bypass Fail ure T urt:line T ri p with Bypass Fail ure Mai n Steam I sola t ion Valve CloStxe (One I All Vatves) Tu rtine T ri p with Bypass Fail ure w/o Positio n Scram 1 Main Steam I solation Valve Closure Sc ra m Loss of Condenser Vacuum Reactor Vesse l Water Temperature Decrease I nadvertent HPC I Actuat ron wrth L8 T urbine Tnp Posittve Re activity Insertion Rod Wlthdrawa J Erro r Reactor Vesse l Coolant I nventory Dec r ease Core Coolant Flow Decrease T rip ot One Recirc ula tion Pu mp or Two Rearcu!at ion Pumps Rec i rct.Jation Pump Se i zure. Core Coolant Flow I ncrease-Slow Re ci'ctJa t!on Con t rol Failure -In crease (MCP RF) Slow Reci'CIAa tio n Control Fail ure -I nc rease (MAPlHGR,)" Fas t Recircula No n Contro l Failure -I ncrease Stanup of an I dle Recuculat i on LOop Fuel Loading Errors M isp laced Boodte-Acaclen t 1 Performed ror ASME Vessel Overpressure Com pli ance. Revis ion: 0 Current
| |
| ./ ./ ./ ./ ./ (il SLO) ./ ./
| |
| Revis ion: 0 Reactor fu ll powe r i nitia l cond itions that app ly to th e lim iting transient an al ysis are summarized transio nt an alyses are fisted in Tab le 4.3. Paramete r Value Va l ue Increased Core Low COfe Fklw Flow Ra t ed Thermal Powe r 2004 46.1 Analysis Powe r I Core Flow Ana lysis Reacto r Pressure Time in Cycle Number of*SIRVs for Analysis 5 i n-serv i ce in-service two
| |
| | |
| Pslg low Vesse l Water L evel Scram 1 %open L ow low Vesse l Water 1 Hig h Pressure Pslg High Reac to r Vesse l Wa ter L eve 1 1 Ps ig Revi sion: 0 1 25 10915 85 85 *55 11 62 11 70 ror be t imes.
| |
| Op t ion 1 be be Nollimit in g be 2
| |
| to 3
| |
| | |
| Revi sion: 0 OLMCPR fo r m oasured scram in sertion ti mes. 3 5.2 1 77 1.57 1.62 core monitori ng system use s more de tailed li rrits for e ach f ue l bu nd le latt ice.
| |
| Rev i sion: 0 15 111 2.1.2 specifica t ion sta t es that the press ur e measu r ed in the r eactor steam dome sh all no t exceed 1 332 Psig. The p ressure safety limit of 1332 Psig as measured in tho ves sel st eam space was derived fr om t he design pr ess u res of t he r eactor pressure vesse l, st ea m space pip ing, and water spac e piping. The pressure safety lim it was ch ose n as the lowo r of th e pr ess u re 1 332 i nitial co n ditions:
| |
| * 100% (2004 1 105%
| |
| (60.5 x10 61010.0 1 170.0 1320 T ec h nical SpeciflCat i on li mi t of 1332 Ps i g. Th e calc ulated maximum st eam line pr essure of 1314 1 332 134 4 1 375 Monticello uses TRACG for the MSIV cmure-Wi too ut Position Sc r am analysis.
| |
| Thi s ana!y sis is rt11 at 1 00%
| |
| 1 (1010 psig) and uncerta i nty are applied as a pressure adde r to t he res ul t of the event to obtain the fina l r eported
| |
| | |
| Revi sion: 0 rod th ermal*mechanica l des i gn and l icens i ng basis , wit h resped to both steady state operations, and transien t and accident eve nts. Th ermal overpower lim its arc de fin ed to eva l uate t he pote nti al for fuel ce n te rlin e metting. Mec h anical overpower lim its are deftned to eva l uate the pot entia l for f ue l cladding ove rs train. Fe edwater Cont r oUe r Fa aure e vent mecha ni cal design and li oens i ng basis crite r ia for th e plant.
| |
| | |
| Revision:
| |
| 0 To pr ovide Monticello Nu cl ear Generating Pl ant -with opera t in g im pr ovemonts, expanded operating do main an:a l yses were perfor med in Refere n ce 1 fo r maximum extended l oad line lim it r eload an alyses in Reference 1.
| |
| | |
| Revi sion: 0 A reload DSS.CO eva lu ation h as beo n performxt in accorda n ce Volith t ho l icensing rnGthodolog y 0) tr ip l in ear segment.
| |
| povve r int ercop t WasP.. TRIP Was.p.sREAK RDF-Rec i rc u la ti on Drive F'low
| |
| | |
| Revi sion: 0}}
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