ML20198T133
| ML20198T133 | |
| Person / Time | |
|---|---|
| Site: | Robinson, San Onofre  |
| Issue date: | 09/24/1998 |
| From: | Foglio S, Phoenix W SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| References | |
| J-SBA-023, J-SBA-023-R00, J-SBA-23, J-SBA-23-R, NUDOCS 9901120152 | |
| Download: ML20198T133 (54) | |
Text
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'- l Southern Cattrornia Edison Comp.iny CALC.NO. PAGE TOTAL NO. OF J SBA-023 fREU CcN NO. ,
INTERIM CALCULATION U NIT '
sAsE cate. nEV. cerg coNvension : . C ALC. nEY CHANGE NOTICE (ICCN)/
CALCULATION CHANGE 0 2&3 CCN NO. CCN. i 8 l NOTICE (CCN) CALCULATION SUBJECT.DNBILPD/ LOG POWER TRIP BYPASS cover PAGE ENGINEERING SYSTEM NUMBER / PRIMARY STATION SYSTEM DEslGNATOR Q class CALCULATION CROSS 4NDEX 1201 / SBA 11 New' Updated meex included
'CNTROLLED PROGRAM OR PROGRAM / DATABASE NAME (s)
) .."9.
- DATABASE ACCOROING TO VERslON/ RELEASE NO.(s) sete Programs /Procedwe impact? sC123-XXIV 5.1 O NO @ YEs AR No.080602771 O rROcRau O O^TasisE O ^'sO. 'isTEo BE'Ow
- 1. nier o c:CRMON Or ICCN / CCN; The design of the DNB/LPD/ Log Power Bypass logic and setpoint cannot satisfy the current Technical Specification 3.3.1.
Table 3.3.1-1, Notes (a) and (d) as wntten. The only setpoint which satisfies both specifications simultaneously is exactly 1E4 percent power, a precision which cannot be achieved. This is because the same bistable is used to do both functions, where the DNBR/LPD bypass is automatically removed at the bistable setpoint on an increasing power and the loganthmic power bypass is automatically removed at the bistable reset (hysteresis) on a decreasing power. As such, the two can never be equal and occur at the same time.
AnWier problem is that the original safety analysis uses 1E4% log power as the inp setpoint in both directions when evaluating CEA withdrawaltransients initiated from suDeritical and low power conditions. The Distable has only one trip setpoint. which curTently satisfies the low power conditions of the safety analysis. The subentical conditions are not bounded by the safety analysis because the actual setpoint is the bistable reset, which occurs at a value lower then 1E4% log power.
The purpose of CCN N-1 is to provide the following-a.) Estabtish the 1E4% Log Power Bistaple Decreasing Trip (Reset) Setpoint.
b.) Establish the Upper Operational and Lower Analytical Umit for the 1E4% Log Power Bistable Tnp Setpoints, c.) Calculate the Allowable Values forthe 1E4% Log Power Bistable Trip Setpointr.. I d.) Calculate Trip Setpoint Margin.
e.) Catculate Margin to Log Power Trip.
CCN N-1 is an entire document CCN for centinuity only. There is a variation in page numbering due to format changes associated with the text processing, i l
l IMTIATING DOCUMENT (DCP, FCN, OTHER) AR 980602271 R Ev. _
0 YEs @ NO OTwER ArrEcTEo OOcuuENTs Ex:sT AND ARE IDENTIFIED CN ATTACHED FORM 26 f.c3.
- 3. APPROVAL : DISC. /CSC: Controls /NEDO S. Foglio , ghh / (;pg.,, hp ORIG;NATdR (Petnf rumJlsgn/ cat FLMgnr.urwcate) OTHER (signatnante) h W. Phoenix h -( h-f2 h
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- 4. CCN'KRSION TO CCN DATE N y 48 SScseSCE CDM - SONGS s:s s.,224 *Ev.2 see tatreeca.w.toi23.xow.71s) vg g gg g gc,eyg.:4cgagegrgeg ge 20*d 90:II 66. II uer $2S2-892-6t76:Xed SMIdidd 933 bd373nN
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. Cdculation No. J-sBA-023 A
poes me output INPUTS ' OUTPUT identify culputintedece cafc1 I ,
hierface calc f I These Interfacing catculatione endfor documents Resufts and conctunions of the sutsect cafetJaison are docuwel require document CCN, DCN TCNfRev-.
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N and date YES NE00 TRAK RMB 91-019 SONGS Unit 2 & 3 Setpoint list Revision 26 O & M Manuel S023 84145, 7/83 Sub'ask 2 Sefety Channel 90030
$ Revision SONGS Unit 2 & 3 Instrtenent index Revision 42 YES NEDOTRAK RMB 98-019 0 Surve'llence Operstng Sub*ask 2 90010A Z lasteudien SO23-la-55 thru 5 a Revision 0 YES NEDOTRAM RMB 91-019 PPS Catcuration SO23-944-C50, Hevision DBD SO23 470. Excore Nuclear subtask 2 E CE NPSD-570 ; 03-P Instrumentelfen System Design Basis h
Document SONGS 2 & 3 Technical Unil 2 NO D00-SO23 470.Evnere Nudear Revision 0 Spectt cations Arnend tol hstrumentation System 0: sign Unit 3 Basis Document Amertd. 90 DBD-SO23 TR-EQ Revision 0 in bi tu M37582 Revision to E
N e i Revision 42 G 90010A cn Reafon o JS 123-103C l Und 2 SONGS 2 & 31echnical Amend.101, Spedficoltons s
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N-1 CALCULATION CROSS INDEX facTCcNuo PAGE 3 of J.SBA423 Sheet No of CCN CCN NO.CONVERSION:
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previde Input to the subject ca!cuistion. and P revised used in these inteifacing calcurn%ns and / or N number and redsfon? FtCCN cr tracMng number.
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-- ---- ---'------------- - - - - - - - - - - - - - ' YES/NO '
x FLS inhats Rev. N o. Ca'c 1 Document No Rev. No
- Calc / Document No and date 41 YES AR 9a0532271 O a M Manual SO23-941-45, 15 SONGS Unit 2 8 Sinstrument Irider m i Safety Channel 600tOA
? 3 YES AR 98063?275 CCNN4 PPS Calcu!stion 5023444 C50 3 DFIO-SO23 470. Excore Nuclear
~ Instrumentat'on System Design Basis
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NES&L DEPARTMENT ICCN NOJ PREUM. CCN NO.
j-CALCULATION SHEET PAGE d W N_
CCN CONVERSION: .
Project er DCP / FCN N/A Cak No. J SBA.023 cCN No CCN. f L
Supiect DNBAPDtOC DOWE'R Trip SYPASS ShWL No. of REVI ORIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE g c D. 8Mhance 03-1S 43 E. Quinn 03-19-83 Q g
E{!
l TABLE OF CONTENTS 1
- 1. O P u rp o s e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 l r 2. 0 Results/ Conclusions and Recommendations . . . . . . . . . . . . . . . . . . . . 0 l t i
- 3. O
~
Assumptions . . . . . . . . ........ . . . ... ............. 16 l
. 4. O Design input . . . . . . . . . . . . . . . . . . . ....... ..... .. . . 18 l S. O Methodology . . . .... . . ... . .. . . .. . ... 25 l
- 6. O References .. .. .... ... .... ...... .. . .. .. . .... 33 l l
)
- 7. O Nomenclature . . . . . . . . . . . . . . . . . ..... . . ..... ...... 35 l ;
- 8. O Calculations . . .................... .... .. ........... 36 l
- 9. O . Simplified Block Diagram . . . . .............. . .. . . 50 l i
Attachm'ent A- SONGS 2 & 3 CPC and CEAC Data Base Listing. CE NPSD-337-P.
Rev. 00-P, Dated January 1986. Pages 14 and 24 !
Attachn ent B: SCE Electronic Mail; From D. Bockhorst (SCE) to J. O'Brien (SCE). i
Subject:
Criticality Point. Dated March 18,1993.
i i l SCE 2426 REV 0 &M (REFT.RENCE SO123 XX.V-7.15) e me esg u s na m sr#.a x e a e m m com uRCDSM
, e9 -
NE,?&L DEPARTMENT ICCN NO/
Not SS CALCULATION SilEET PRM CN N . PACE S of h CCN CONVERSION:
Project or DCP / FCN N/A Calc No. J-SB A-023 _ CCN NO. CCN.
sutsect DNatPDA.OG POWER TW SYpAss sheet No. of REV ORIGINATOR DATE IRE cATE REV ORIGINATOR DATE I 1RE DATE g C O. McQuase ca.19 33 E. oue c318-83 E Et t
1.0 Purpose 1.1 Background / Purpose
- .1 Purpose I The U.S. Nuclear Regulatory Commission inspection Report (Reference 6.10) addressed the area of weakness concerning setpoints that had been improperly delineated and were not consistent with the design basis for respective systems. As a result of this inspection, SCE committed to reconstitute the design basis for all safety-related setpoints. This calculation will provide an evaluation of whether the Departure from Nucleate Boiling Ratio (DNBR) / Local Power Density (LPD)/ Log Power Trip Bypass at 10"% Reactor Power has a safety function related to it. If it is determined to have a safety function, fur'her analysis will encompass the setpoint and !otal loop uncertainty values for this bypass.
The purpose cf CCN N-1 is to provide the following:
a.) Establish the 1E-4% Log Power Bistable Decreasing Trip j (Reset) Setpoint.
b.) Establish the Upper Operational and Lower Analytical Limit for j the 1E-4% Log Power Bistable Trip Setpoints. I c.) Calculate the Allowable Values for the 1E-4% Log Power j Bistable Trip Setpoints. !
d.) Calculate Trip Setpoint Margin.
e.) - Calculate Margin to Log Power Trip. ,
.2 Background The 10"% Bistable is an operating bypass which performs three functions. Two functions of the bistable are to allow manual bypass of
. the Departure From Nucleate Boiling Ratio (DNBR) and High Local Power Density (LPD) trips. The bypasses are manually inserted by
. the operator when reactor power is less then 10"%. The bypass is automatically removed when power is greater than 10-'%. t SOE 26d26 REV 0 &S4 (REFERENCE SO123-XXN-7.15)
- er&M _EatSUL hE-__ . __ _3tCz-Ret-s&ML4 CMhtsisRALu1@O Gi
NEs&L oEPARTMENT ICCN No/ p PREuM. CCN No. PACE 6 of g CALCULATION SHEET CCN CONVERSION:
. Propct or DCP / FCN N/A Cate No. J.SBA-C23 CCN No. CCN- !
se, ounooseo cwca ea. crm.cc sh i N . or REV ORIGINATOR CATE tRE DATE REV oR;GINAToR DATE tRE DATE E e o. ur.o nim e. co.a. mm y q}n The third function of the bistable is the High Log Power Level Bypass.
This bypass disables the High Logarithmic Power Level Trip during reactor startup. - The bypass is manually inserted by the operator when reactor power is greater than 10"% and is automatically removed when power is less than 10-'%.
+
The background for CCN N-1 is provided in the following paragraphs which describe two proolems associated with setting the 1E-4%
Bistable setpoints. Supplemental information is documented in AR 980701034 and AR 980602271.
The design of the DNBILPD/ Log Power Bypass logic canrot satisfy the current Technical Specifications (TS) as written. TS 3.3.1, Table 3.3.1-1, Note (d) states the DNBRILPD bypass "shall ne automatically removed when thermal power is [ greater than or equal to) iE-4
[ percent]." TS 3.3.1, Table 3.3.1-1, Note (a) states the togariinmic power bypass "shall be automatically removed when thermal power is
[less than or equal to] 1E-4 [ percent)." The only setpoint which satisfies both specifications simultaneously is exactly 1E-4 percent power, a precision which cannot be achieved, nor is desirable. This is because the same bistable is used to dn both functions, where the DNBR/LPD bypass is automatically removed at the bistable setpoint on an increasing power and the logarithmic power bypass is automatically removed at the bistable reset (hysteresis) on a decreasing power. Hysteresis in the bistable is an important and desirable feature to prevent the bistable from chattering at the setpoint, and to prevent inherent noise from setting and resetting the bistable and triggering a spurious safety system operation. As such,
+
the two can never be equal and can not occur st the same time.
This first problem will be resclved by rewording Notes (a) and (d) in
--- -Table 3.3.1-1 of the TS to reflect the operation of the DNB/LPD/ Log
- Power Bypass logic. This will require a revision to the TS, which is not a purpose of CCN N-1. However, values calculated in CCN N-1 may be used in the TS revision.
Another problem is that the original safety analysis uses 1E 4 log power as the trip setpoint in both directions when evaluating CEA withdrawal transients initiated from suberitical and low power conditions. As discussed above, the bistable has only one trip setpoint, which currently satisfies the low power conditions of the 1 ,
set 2sats REv c sed (REFERENCE S0123-XXIV.7as)
. _ .__ _ _JA*4_ _ l'M_CllMf____3GL-R$(-DA:XM _MIRUW 93g EMTQnN. __
- _ _ _ _. _ _____m__ _ . _ . . _ . . _ _ _ _ . _ _ . _ _ _ _
NEs&L DEPARTMENT ICCN NO) p
REuM. CCN No.
CALCULATION SHEET PAGE 7 ofi Project or DOP / FCN N/4 Calc No. J.S EAE73 CCN CCN NO CCNVERSION:!
CCN.
subject ewauctoG POWER Trip BYPASS S%et No. of ORIGINATOR REV DATE 6RE DATE REV ORIGINATOR DATE 1RE DATE
)
e o.u.o a3 iu3 c. m a3.in3 g g1-safety analysis. The suberitical conditions may not bounded by the safety analysis because the actual setpoint for the subcritical ;
con'ditions is the bistable reset, which occurs at a value lower then 1 E- 7j 4% :og power.
4 This second problem will be addressed by reevaluating the safety analysis using an Upper Operational Limit (UOL) and Lower Analytical 4 Limit (AOL) that takes into consideration the total loop uncertainty for the 1E-4% log power bistable setpoint plus margin. The TLU is provided in Revision O of this calculation and is slightly modified by CCN N-1. [
.2.1 DNBR/LPD Bypass The DNBR and LPD bypass, which bypasses the low DNBR and high LPD trips from the CPC, is provided to allow system tests at low power when pressurizer pressure may be low or reactor coolant pumps may !
be off. This bypass is necessary to permit CEA withdrawal during startup because the CPCs will be in a tripped condition when the part-length CEAs or shutdown CEAs are fully inserted. The bypass may be manually initiated if power is below 10"% and is automatically i removed when power level increases above 10"%. - '
l CPC protection is not required at subcritical conoitions. The minimum l power used in the CPC for the DNBR and LPD calculations is 20% of l rated power (Reference 6.12). When the shutdown CEAs are not fully ,
withdrawn or the part-length CEAs are fully inserted, large radial l peaking factors are used in the DNBRILPD calculations which will insure a reactor trip. Therefore, the CPCs have to be bypassed to permit CEA withdrawal during startup.
.2.2 . High Log Power Trip Bypass i
The High Logarithmic Power Trip provides a reactor trip from a high neutron flux when the neutron level is at or below the minimum range of the power range nuclear instrumentation. A high flux may result, for instance, from an uncontrolled CEA withdrawal from a suberitical condition. The High Logarithmic Power Level Trip bypass is provided to allow the reactor to be brought to the power range during a reactor startup. The bypass may be manually initiated above 10"% power and is automatically removed when power decreases below 10"%. g SCE 26426 REV C SM (REFERENCE SO123-XXrM,it)
@ 04 @:H. 6L 1I Lef G492-892-6t'6:XE3 SdI6338 933 Ed3 DnN __
l NES&L CEPARTVENT ICCN NO/ gI CALCULATION SilEET PREUM. CCN NO. PAGE _e_ cf %
CCN CONVERs!ON:
Prolcet or DCF IFCN N/A Calc No. J-SBA423 CCN NO CCN. !
subject DNM PCROG POWER TRfp B19 ASS ' Siui No. of REV CRIGINATOR DATE 1RE DATE REV ORIGINATOR DATE IRE DATE g 0 D. McQuado 031SLS3 E.Cumn 03 15 93 5 52 1
This setpoint allows the high log power trip to be manually bypassed once the conditions have been established that the high log power trip function is no longer needed.
1.2 Degree of Accuracy f The results of this calculation are based on the statistical methods in accordance with SCE Engineering Standard for instrument Setpoint/ Loop Accuracy Calculation Methodology, JS-123-103C Rev. O, and Revision 2 for CCN N-1 (Reference 6.7). A 95% probability at a 95% confidence level is used.
1.3 Intended Uses/ Acceptance Criteria The results of this calculation are intended for the uses described in section 1.1, purpose of this calculation.
The voltages and values in this calculation apply only to the bistable, not to indications in the control room. The state of the bistable is displayed to operators via lights and alarms which are not directly connected to the analog control board indicators, whose accuracy is a separate issue.
This calculation /CCN involves a plant protection system operating bypass that is described by using the numerical value of the "setpoint" in the name of the function. The bistable card that performs the operating bypass function also has the "setpoint" value in its name. In addition, inis particular bypass / bistable function operates in both directions using the reset of the "setpoint" as a setpoint in the opposite direction, resulting in the function having both increasing and decreasing setpoints. For purposes of discussion, and in identifying with existing nomenclature,1E-4% will be viewed as a nominal value in the context of describing the DNBILPD/ Log Power Trip and 1E-4%
Bistable operating bypass. Actual setpoint values are clearly identified when used.
sCE 2C-426 REV 0 &S4 (REFERENCE SO12? XXN 7.15) 60 *d 90:IT 66, , UPC S262-892-6tT6: xP3 SBIdddd 933 Ed3 DnN
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NES&L DEPAR1WENT ICCN NO/
N4 PREUs. CCN NO.
CALCULATION SHEET pggg 9
- CCN CONVERSION:
Protect or DCP /FCN N/A ~ Cate No. J-SBA423 CCN NO CCN. !
Suoject DNWLPD' LOG POWER TR@ Erv9 Ass Sheet No of l REV ORIGINATOR DATE IRE DATE REV QRIGiNATOR DATE IRE DATE E 3
0- D. McQuade 03 19 93 E. Owinn 03 1S43 g E{gE 2.0 Results/ Conclusions and Recommendations I
! 2.1 Results
.1 Calculation Results g The established and calculated values associated with the High Log l Power and DNB/LPD Bypass are listed in the table below and Figure 1:
l Bistable increasing Decreasing (Reset)
Units Setpoint Setpoint
% Log Power V de 'A tog Po,wer V de l
- l. Setooint / Reset 1 E-4 3.699 7.944E-5 3.599 ]
Setting Tolerance 1.023E-4 to 0.01 8.414E-5 to 0.025 9.773E-5 7.499E-5 Allowable Value _
1.5E-4 3.875 4E-5 3.305 l
~
~
UOL'/ LAL 4.1 E-4 '4.312' 1.48E-5 2.869 }
Total Loop MsMsenja e?g ri 0.485 L g gg.y.g gg:g 0.485 MB:aEliER@=M% ggggg@$h3 Uncertainty if3PR 7/ m e n ? #5dBhs5 M R g p,<w.u m.va. , -
Setpoint Margin 92. m ,~,w, ,. . 0.128 0.245 l
! $$$$S@f5 W @ E M 6!Ni W N l I re E 9_n B M p 3 iL:C$$$E Setpoint Marg. in to ggu 2.932 E 3 '9@gjag H25Qn$s g.t,y ggg Log Power Trip pgggjgggg,;g gg.
MDd)s4.j3?f@fE(@gG f-L t
l
- SOE 2r>426 REV 0 &S4 (REFERENCE SO12SXXN 7.15) f i
OI .*d ; 60:II- 66. II uer . SASA-892-6176:xed .Sg WJde 93g 6037JON
1 NESSL DEPARTM6NT ICCN NO3 N-1 pggg j
PREuu.ecNNo. -' - ,
CALCULATION SHEET CCN CONVERSION:
Pro,ect or DCP / FCN N/A Calc No. ,1-SBA423 CCN NO. CCN. [
Satlect oNatPD/ LOG POWER Tw trvPASS Sheet No. of REV ORIGINATOR DATE IRE DATE REV CRIGINATOR DATE 1RE DATE E o D.r h n19-93 E.Cuinn 03-19-93 ,. j EjF 200% Power 10 Vdc UAL 2.0% Power 8.0 Vdc
" 0.837% Power 7.622 Vdc UAL-TLU, ,
" 0.837% - TLU 3 0.351% Power 7.244 Vdc 1
3 .
y 10"% Power
- y
- 102% Power 10 3% Power i
UOL 4.1x10d% Power 4.312 Vdc AVi 1.5x10d% Power 3.875 Vdc tsp 10d% Power 3.699 Vdc increasing Reset - - - - - - -- -
7,944,30.s% Power 3.599 Vdc Decreasing AVd l
, 4x10 5% Power 3.301 Vdc LAL 1.4Bx10*/. Power 2.869 Vdc LOL 10-5% Power Notations
. UAL: High Log Power Trip UAL LOL: High Log Power Bypass UOL LOL: Lower Operational Limit 104% Power denotes Margin to High Log Power Trip 2x10*/. Power 0Vdc tsp atTows indicate s.rgnal direction -increasing or s
decreasing
- AVi: Allowable Value increasing _
(' Setpoint Figure 1 AVd: Allowable Value Decreasing (not drawn to scale)
(Reset) Setpoint t
SCE 2926 REV 0 Ived 6tCTERENCE So12LxXV 715)
T T 'd 60:TT 66. IT UPC S2S2-89E-676:XPd $6I0330 936 803lJnN _ _ _ _ _ _ _ _ _
- . _ . - - . - ~ .
NES&L CEPARTMENT ICCN No1 PREuM. CCN No.
PAGE 11 of %L CALCULATION SHEET CCN CCNVERsioN:
Prefect or oCP / FCN N/A Calc No. J-S BA-073 CCN NO. CCN- !
subject DNM.PD/LDC DOWER Trip BYPASS sheet No. of REV ORIGINATOR DATE 1RE CATE REV ORIGINATOR oATE '
IRE '
DATE y 0 C. McCade 03.Se3 E.Qwwm 03 4 33 .; 5 y5 Figure 1 on the previous page incorporates values shown in Table 1.
Noteworthy items in Figure 1 are the Upper Analytical Limit (UAL) of 2% RTP for the High Log Power Trip less the High Log Power Trip's Total Loop Uncert#nty (TLU,) twice, and the amount of margin between the High Log Power and Bypass Trip setpoints.
The Upper Analytical Limit has the High Log Power Trip TLU, l subtracted twice to ensure adequate margin between the High Log Power Trip and the High Log Power Trip Bypass bistables. The "UAL
- TLU " term is the 2% Analytical Limit minus its associated TLU 3
(Reference 6.8), resulting in a 0.837% High Log Power Trip setpoint. l The same TLU, is then subtracted again from the 0.837% power setpoint in a conservative effort to account for the accuracy of the High Log Power Trip bistable itself. It is necessary to ensure that the uncertainty associated with the High Log Power Trip bistable does NOT overlap with the calculated uncertainty plus margin for the High Log Power Trip Bypcss setpoirit. The TLU value for the High Log 3
Power Trip already includes the bistable uncertainty component and therefore is a conservative value.
The shaded region of Figure i shows the amount of margin Detween the High log Power Trip Bypass UOL and the High log Power Trip setpoint minus TLUs. This large amount of margin. 2.932 Vdc or 29.3%
of Span, allows the operator sufficient time to perform the manual bypass of the High Log Power Trip without causing an inadvertent trip.
.2 Discussion of Results The setpoint for this bistable is currently set to permit manual bypass of the High Log Power trip and to automatically reinstate the DNBR/LPD trip at 10-'% power increasing power. This bistable also automatically reinstates the High Log Power trip and permits manual bypassing of the DNBR/LPD trip when the bistable setpoint resets on l decreasing power. The input range for the log channel is from 2 x 10' 8% to 2 x 10 2% power while the output is from o to 10 volts. The output to input sensitivity is then 1 volt per decade. Both the High Log Power trip and the High Log Power bypass receive an input signal from the same detectors and signal conditioning electronics.
Since one of the functions of the bistable is to permit a bypass and automatically reinstate the High Log Power trip, the setooint needs to SOE 26 426 REV 0 Srpe (RETREN".F SO123 XXfV 7 iS) ri '<J nT TT Ac JT Upr c>c> poc-676:xea <:;NTHJ4H 9D WTT)nN _ __
l NES&L DEMRTMENT ICCM NP N-1 g
PREuM. ,CN No. PAGE 12 CALCULATION SHEET CCN CONVERSION:
Projwc or DCP / FCN N/A Cak No. J.SBA.023 CCN NO CCN. [
[ Subint DNEAP0/ LOG POWER TR& BWASS Shed No. of j- REV ORIGINATOR DATE 1RE DATE REV CRIGINATOR DATE tRE DATE y 0 D. McQuade E1943 .E.Qumn nG93 g
l __
d*
, be set to ensure that this will occur prior to the High Log Power trip l'
setpoint which is nominally set at 0.837% powei olus the bistable uncertainty. Another aspect of the bypass setpoint is that sufficient difference between the High Log Power Trip Setpoint and the Bypass l Setpoint must exist to allow the operator sufficient margin to perform l the manual bypass without causing an inadvertent trip.
1$
~
Another function of the bistable is to automatically reinstate and permit the bypass of the DNBR/LPD trip.
Parametric analysis have indicated that the lowest initial power level of 10*% suberitical core condition results in the closest and fastest I approach to the fuel design limits during a CEA withdrawal transient.
- Initially subcritical, zero power CEA withdrawal transients are
! terminated by the High Log Power trip. Analysis has also shown that, l for CEA withdrawal transients initiated from a power level of 1E-5% l and higher, the accident is terminated by either the DNBR/LPD trips or a high Pressurizer Pressure trip. From the accident analysis it can be l seen that above 1E-5% power the protective function of the High Log Power trip is not required to protect the core once the neutron flux has been stabilized. However, it is important that the High Log Power Trip Bypass not be set any lower than a power level at which the core is to be considered unstable. Historically for SONGS 2/3, the power level at which neutron flux level is considered stabilized has occurred at approximately 10'5% power (Attachment B). This CCN N-1 uses a Lower Analytical Limit (LAL) of 1.48E-5% to ensure that the accident i analysis limit is not exceeded. Also, the analysis considers that the DNBRILPD trips have been insened above 4.1E-4% power. Although not a safety limit, the 4.1E-4% power serves as an Upper Operational l Umit (UOL) when analyzing low power conditions. It funher ensures sufficient margin for manual bypass operation.
~ Therefore, a bypass setpoint of 10"% for this trip function is 7 acceptable from a safety analysis point. Also, as stated above, the bypass setpoint must be set such that the operator has sufficient time to manually bypass the High Log trip without causing an inadvertent
' trip. If the calculated uncertainties for the bistable are applied to the setpoint, sufficient margin must be allowed for the manual bypass
[ operation. In the case where too small a margin exists, adcitional l-
! margin would have to be added to allow the operator to perform this operation without causing an inadvertent trip. l l s E 26 66 REV 0 &S4 (REFERENCE $012%XXV 7.15) i
!- EIld 01:II 66._II urf S2S2-892-6tT6:x0 SdIdad 933 203 DM
_ - - = - - - -
NEsn oEPAR W ENT ICCN N U
"'I 3 CALCULATION Sl1EET PREuM CCN No. PAGE 13 o CCN CoNVERSloN:
Prcncet or oCP I FCN N/A Cac No J-SRA.073 CCN NO. CCN. !
IWD,cCt DNEWPD/ LOC POWEst MS' BYPASS shed No. of REv ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE l DATE 8 D D.McQuade 03-tM3 E. Quim CS1M3 Eji Based on the above, the present bistable increasing setpoint of 10"% l is acceptable. This setpoint allows the operator sufficient margin for implementing the manual bypass without causing an inadvertent trip. ,
The decreasing setpoint, or reset of the increasing setpoint, will l reinstate the High Log Power trip when it is required by the accident analysis to provide core protection for CEA withdrawal transients initiated from subcritical conditions.
2.2 Conc!usions The existing setpoints for the High Log Power and DNB/LPD trip bypass are l sufficiently conservative to meet its functional requirement. /.ccording to the Combustion Engineering Plant Protection System Setpoint Calculation (Reference 6.8), the High Log Power trip of 0.837% corresponds to 7.622 volts while the calibration procedure for the bypass bistable (Reference 6.5) indicates that the 10"% setpoint corresponds to 3.699 volts. There is approximately 3 decades of power between the two setpoints. This is sufficiently conservative to allow the operator time to perform the manual bypass while also automatically reinserting the High Log Power trip protection (on reset) when required by the safety analysis. In the case oi the DNB/LPD l trip bypass there is also sufficient margin between the bypass setpoint and the point at which the CPC's use actual neutron power to calculate the DNB/LPD trip.
2.3 Recommendations it is recommended that the following documents be revised to include this calculation as a reference:
DELETED l SONGS Unit 2 & 3 instrument index: Report No. 90010A
- The current setpoints are accepts ble for the bistable to perform its intended function. It is recommended that the present setpoints not be revised.
2.4 Limitation and Verification This calculation should only be used for the purpose described in secticn 1.
SCI 2926 REV 0 E94 (REFERENCE SC123 XXV.715)
P} *A DJ'TJ AA, TT UPf C)Cl-900-ApA:XPJ cyTW.uq 03w NA qqq
i NEs&L DEPARTMENT ICCN NO/ '3 PRELM CCN No.
"^
CALCULATION SHEET PAGE_j4 of
, " ;N CONVERslON: i rivei.c4 or DCD / CCN M/A Ca:e No, J.C D A.023 ceu Ho CCM.
s# WatPD40G #0WER TRJ8 BYPASS sheet No. of YEV oRIGINATCR DATE tRE DATE l REV ORIGINATOR DATE tRE DATE y '
e e. ucouw as-u42 e. osna ca.is 2 I s I kI l 1
No special tests are required to confirm the results of this calculation.
This calculation does evaluate for seismic conditions.
This calculation does not apply to loop uncertainties which may result from
, harsh environmental conditions.
The parametric analysis of the CEA withdrawal transient assumed that 1E-5% l l
would be the point at which the protection system would switch from the High Log Power Trip to the CPCs for protective action to prevent core damage for this transient. This CCN N-1 uses a Lower Analytical Limit (LAL) of 1.48E-5%
to ensure that the accident analysis limit is not exceeded. It'also considers 4.1E-4% the point at which the switch has occurred by. Revising the setpoints in this CCN N-1 may require reanalyzing the transient to assure satisfactory results.
2.5 Interfacing Catculations, Documents and Drawings Interfacing calculations, documents and drawings are listed in the calculation Cross-Index and section 6.0, references.
The Excore Nuclear Instrumentation System Design Basis Document (reference 6.6) will require updating to include the decreasing (reset) trip setpoint for the 1E-4% bistable. AR 980602271 will track this update.
Final Safety Analysis Report, Section 7.2, will be affected. Changes to thi.s report will result from Licencing Proposed Change Number 498 (PCNA98).
Units 2 & 3 Technical Specifications, Table 3.3.1-1, Notes (a) and (d) are affected. Licencing Proposed Change Number 498 (PCN-498) wil' initiate and track this change.
SONGS 2/3 instrument Index, SCE Dwg. 90010A Rev. 42, will require updating to include the trip setpoint allowable values and the decreasing
- (reset) trip setooint for the 1E-4% bistable. AR 980602271 will track this update.
Update I&C Calibration Procedures S023-11-5.1 thru 5.8 with calcule un results. AR 980602271 will track this update.
2.6 Interfacing Organizations i s:E 2H26 REV 0 &S4 (REFEctENCE SO123 xxN-7.ts)
GD1 UL:JG #A, fR uwc QQ-[gg-ggg: xN SE%MM 936 W3 UnN
_ _ - _ _ - - . . , - - .----au...a----;------------------------------- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
NESaL CEPARTMENT IOCN NO/ '3 PREUM. CCN NO.
"^
CALCULATION SHEET PAGE 15 W __ _
CCN CONVERSION:
Project er DCP / FCN N/A Calc No. J-SBAE CCN No. CCN- [
SJbICCf DNM.PD/ LOG POWER TRIA BY9 ASS Sktt No. of REV ORIGINATOR DATE IRE DATE REV CRIGINATOR DATE IRE DATE g 0 D. McCanoe 03-1943 E. Ovinn 03 19 93 g
- }hm Per the requirement of NES&L SO123-XXIV-7.15, Sections 3,4, and 6 of this calculation have been sent to the responsible System Design Engineer and NGS Maintenance Engineering.
Other affected disciplines as identified and documented on the Document Review Form (Design Verification Fonn for CCN N-1) SCE 26-422-1 are l included in the review process.
-~
i sCE 25 426 REV 0 ILs4 (REFERENCE E01:3-xXV-7.15)
{
Of 'd {}*(( 6%, CPI C)C 1-RQ7-6f;6:XPq $NTHJ46 C)% Nd]T)pN
, - -........: . = = = - i NEs&L CEPARTMENT 3CCN NOJ $.7
- CALCULATION SHEET ' " E'" ' C" " - "^*' ' ' # %
CCN CONVERSION: Propet or DCP / FCN N/A Cale No. J.SBA-023 CCN NO. CCN. [ j- Subject DNMPMOG POWER Tap BYPASS Stwet No. of REV ORiclNAToR DATE 1RE CATE REV ORIG!NAToR DATE IRE DATE 3 O C.McQuase 03-19 90 E. CWan 0>1bS3 g 15 g 3.0 Assumptions , 3.1 Assumptions Which Do Not Require Verification
.1 Radiation Error (Re,)
, The effects for normal non-accident radiation doses for the device in this calculation is assumed to be included in the drift allowance per section 3.6.1.5 of reference 6.7.
.2 Drift Error (Da,)
For devices with no vendor drift data specified, a drift value equal to the stated accuracy for a 30 month period will be applied. This is considered conservative based on engineering judgement, since it is assumed that actual drift values were so small as to be considered insignificant by the vendors or that the vendors encompassed drift data in other published specifications. j l
.3 Ambient Pressure Sensitivity (Pe3)
~
The components evaluated in this calculation are not sensitive to the ambient pressure variations exhibited at their locations.
.4 Power Supply Effect (Ps,)
The power supply effects are assumed to be included within the performance specification.
.5 Temperature Effect (Te,) l
- -- - - For the NT-4 bistable the specification for reproducibility stated by the '
. manufacturer is assumed to include the effects of ambient temperature variations.
L I 9 SCE 2H26 RCV 0 SS4 (REFERENCE SO123 XXfV.7.15) W QM g
m _._ NES4L DEPARTVENT ICCN No/ -3 CALCULATION SilEET PREUM. CCN No. PAGE 17 o' $ CCN CCNVERS CN: Prw or DCP / FCN N/A Calc No. J.5BA4/3 CCN NO CCN.' ! S@ ject DNBtPEROG POWER TR$e BYPASS Sheet No. of REV oRIGWAToR DATE IRE DATE REV CRIGINAToR DATE I 1RE DATE y o c.unounde os.1:Nr3 E.oA es.1643 g
}ym
.6 Area B Temperatures Per the UFSAR, the minimum normal temperature of the control room complex (including the control room cabinet area) is 70*F. The peak temperature for this area per table 0-1 of Reference 6.3 is 75'F. It is i assumed that a 2.5'F control band exists about the minimum and
'- peak temperatures yielding a 67.5*F to 77.5'F (10*F) temperature band. This 10*F temperature band will be used to calculate ambient temperature effects on equipment located in these areas.
3.2 Assumptions Which Require Verification There are no assumptions used in this calculation which require verification. 1 l SCE 1926 REV 0 $$4 (REFERENCE SO123-XJJV-7.* 5)
NE3&L DEPAE2TMENT 10CN No/ PREUM. CCN NO. 3J CALCULATION SHEET PACE i s _of __ % CCH CONVT.RSION: ! Prom or oCP / FCN N/A Calc No. J.SBA 073 CCN No CCN. [ Sutiect DNERPutoC DOWER 79P BY8 ASS sheet No. of REV ORIGINATOR DATE 1RE oATE REV oRtGINATCR DATE IRE DATE % o o wo.a as-sm ' e. os.i ca.sm ,. $ 4a 6 4.0 Design input
~
4.1 The Upper Analytical Limit for the High Log Power Trip setpoint has been l determined to be the Analytical Limit for the High Log Power Trip at 2% Power less twice the TLU for the High Log Power Trip (Reference 6.8). l I 4.2 For increasing power, the point at which an operator may bypass the High Log } l Power Trip is a power level where the core is considered to stabilized and low l power transients or excursions are unlikely. For decreasing power, the l operator bypass will need to be reinserted prior to a power level where low l power transients become increasingly difficult to control with the High Log Power Trip in bypass. The resulting value which meets both of these criteria l will be 1E-5% RTP (Attachment B), which is defined as the Lower Operational i Limit (LOL). 4.3 The operating characteristics of the Excore Safety Channels are provided by the Operation and Maintenance Manual prepared by ABB/CE (reference 6.4). f L 4.4 The design input for this calculation is included in forms 1 through 4. 4.5 The data obtained from the Technical Specifications is used for information i and does not provide numerical input for the TLU calculation. 4.6 The attached Calculation Cross index lists all reports and documents that provide numerical input for this calculation 4.7 . Where reference is made to the UFSAR this is the best source for the required data. 4.8 The Upper Operational Analytical Limit (UOL) and the Lower Analytical Limit (LAL) for the DNB/LPD/ Log Power Trip Bypass Setpoints are established at _4,1E-4% and 1.48E _S% Log Power respectively (Reference 6.14). i 4.9 The DNB/L PD/ Log Power Trip Bypass bistable trips on an increasing power.
- The trip setpoint is adjustable. The bistable trip setpoint resets on a
- decreasing power at a fixed hysteresis of 0.1 V (Reference 6.4). The trip setpoint is referred to as the " increasing setpoint" and the reset is referred to
~ as the " decreasing setpoint". i n 4.10 The PPS Cabinet Signal Calibration Uncertainty, abbreviated CUA in Section 8, Form 11, Sheet 2,is the combination of Calibration Uncertainty, Detector ,, SCE '6 426 REV O 454 (REPERENCE SO123-XXN 7.s!) ! 6fd. 21:11 66,IIyer S2S2 ,89E-6176:xed Sbl6330 933 303 OnM
NES&t. DEPARTMENT 3CCN NOl ~~ 3,
"^
PREW. CCN NO. PAGE 19 0 14. CALCULATION SHEET CCN CONVERSION Protect c' OcP / FCN N/A Calc No. .l-S B A423 CCN NO. CCN- ! Subject DNStPD/ LOG POWER TRIP K@ ASS Sheet No. of
'REV ORIGINATOR DATE l IRE DATE REV CRIGlNATOR DATE IRE DATE 5 0 0. McQuade C3.1Ss3 E.Cumn 03-1 4S3
$g!
Sensitivity, Accuracy, and Neutron Flux Uncertainty. The resulting voltage is 10.345 V (see Section 4.2, 'High Logarithmic Power Level Setpoints' of Reference 6.8). This uncertainty applies to the at-power calibration of the nuclear channel and i' other uncertainties in the nuclear detector and nuclear channel. It is taken as ' a design input. The effect of the uncertainty is assessed by calculating the voltage for 100% power, oubtracting 0.345 V, and calculating the power for the resulting voltage. The calculation is: The formulas are: % Power = 2 x 10 N -8) or, V = 8 Volts + log (% Power / 2) Volts Calculating voltage from 100% power: V = 8 Volts + log (% Power / 2) Volts V = 8 Volts + log (100%/2) Volts = 8 Volts + 1.699 Volts V = 9.699 Volts @ 100% Power Subtracting 0.345 V: New V = 9.699 V - 0.345 V = 9.354 V Calculating power from Voltage:
% Power = 2 x 10w.e 3%
% Power = 2 x 10 ("" 8)% = 2 x 22.594%
% Power = 45.189%
The difference between the two power levels is: Difference = 100% -45.189 % Difference = 54.811% Corresponds to Voltage Uncertainty of 0.345V As mentioned above, this uncertainty applies to the nuclear channel and its adjustment and is therefore taken as a design input. SOE 26-426 REV O 8,94 (REFEPENCE SOUMXN 7.15) 02 M ET:II 66. II UEf $2S2-892-6t76:xed $31633S 933 Ed37]nN _ _ _
L l NES&t. DEPARTMENT ICCN HO/
$3 CALCULATION SHEET PREUM. CCN NO.
PACE 20 of _% CCN CONVERSION: ! Protact or DCP / FCN ' WA Cale No. J4BA-023 CCN NO CCN. [
. Subject DNEGOLOG POWER Tmp evpAss Shcct No. of REV ORIGINATOR DATE IRE DATE REV: ORIGINATOR I DATE 1RE DATE 3 0 D. MsQuase 9319.y3 E. Quinn CD.19 83 h qi l . As.used in this calculation, the value of *0.345 V is squared to produce 0.119 V 2; 1 this value is used as CUA in Section 8, Form 11, Sheet 2.
l l l r - _ l l l n. l !CE 2926 REVO E14 (REFERENCE SO1&KXN 7.15) l It 'd 6I:II 66. II uPC S252-892-676:xe3 SMISidd 933 bO3 DON l
l NES&L DEPARTMENT ICCN NO/ PREUM. CCN NO. p CALCULATION SHEET PAGE 21 o' _ % CCN CONVERSION: f Prorect or DCP / FCN N/A CaleNo. J-SBA423 -. CCN NO CCN. [ Sub gt ONG1.PCAOG POWER TRp BYPASS SPmmit No. q# REV l ORIGINATOR DATE IRE CATE REV ORIGINATOR DATE IRE DATE y C D.McQuede 121943 E. W nn 03-1S40 g y ElI , FORM 1: LOOP / PROCESS DATA SHEET l DATA REFERENCE Loop Number 2(3)JY-K099-1,-2,-3,-4 6.6 l Service Description High Log Power Bypass 6.6 , l l Technical 3.3.1, Table 3.3.1-1 6.2 Specification Upper Operational Limit 4.1E-4% Log Power Sec. 4.8, 5.4
- Lower Analytical Limit 1.48E-5% Log Power Process Measurement Rod shadowing Sec. 5.2 l
Uncertainty (Pma) Temperature Decalibration , l Azimuthal Tilt Normal Operation 100% Reactor Power 6.4 i j Upper Limit ! Normal Operation 10d% Reactor Power 6.4 l Lower Limit , l Applicable UFSAR CEA Withdrawal Transients 6.1 : Events Low RCS Flow ! ! Cable Type N/A N/A ] l (Harsh Environ Only) I I 1 SOE 26-426 REV 0194 (REFERENCE SO123J00V 7.15) ' 5252
- A R9fLA15LJRf . ___.___ fJfJ_o_JRGR=($fe$*RRsi__3v1TM_asM__ciWXM
__ _ . . . . . . - _ . . _ . . _ _ . . _ _ _ _ , . . . _ . _ _ _ . _ _ _ __.-___.__.__.m _ . . _ _ . . _ _ . _ . .y._.~.___. ,m. e e. l l NES&L DEPARTMENT ICCN NOJ PREUM. CCN NO.
" Q
' CALCULATION SHEET PAGE 22 of_ %
CCN CONVERSION: Project or DCP / FCN N/A Calc No. J.SSA423 CCN No. CCN- [ i Subject DNSUDLOG PCPNER 'UUP BYPASS Shoot No. of l REV ORIGINATOR DATE IRE DATE REV ORIGINa TOR DATE tRE DATE 5 l C D. ucQuede in 1km E. Qan 03-1M3 g h . 4I ) FORM 2: INSTRUMENT DATA SHEET (DEVICE 1) DATA REFERENCE
;. . Tag Number 2(3)JY K099-1,-2,-3,-4 6.6 ,
- s. 1 Manufacturer General Atomic Company 6.4 Model Number NT-4 Bistable 6A l -
Location Control Room 6.11 Service Description High Log Power Trip 6.6 Bypass i ( Quality Class 11 6.11 Environmental - NO 6.11 Qualification
~ ~
input Range. Min.- 0V 6A Input Range. Max. 10 V 6A i L Output Range. Min. OV 6.4 i Output Range, Max. 13 V 6.4 i- Surveillance / S023-il-5.1 through 5.8 6.5 l Calib. Procedure Calibration interval 31 Days 6.5 Setting Tolerance 0.01 V 6.5
- * ~ ~ ' -
Allowance (St)i l !- . Setting Tolerance 0.025 V ' 6.8 ! , Allowance (St.) g.. s-
- SCE 26 426 REV O 848 (REFERENCE SO123 30W.7.t!)
L. - - . . u .$ r d. . EI;IT 66._TI uer _ S2S2-892-6p6:xed . SdIbiid 933 363 OnN _
o NES&L DEPARTMENT ICCN NO/
"4 #"3 CALCULATION SHEET ?R. euu CCN NO. Pace _n _ i s.
l Proget or DOP / FCN N/A C3:C NO. J.SBA.0D CCN CONWR510N; CCN NO CCN. [ i Sutsed DNwtMWLoG pcWER TmP UYPASS _ Sneet No. of REV CRIGINATOR DATE IRE DATE REV ORIGINATOR l DATE IRE DATE E I. o o.uco euo is oram ons.sa 5 i EI l FORM 3: MAKE/MODEL DATA SHEET (Device 1) i t'
- . DATA REFERENCE
! ay o Type Bistable 6.4 ib 4' l Manufacturer General Atomic Company 6.4 Model NT-4 6.4 Accuracy (As,) 0.5% = 0.05 V 6.4. Drift (Da,) t 0.5% = 0.05 V 6.4. 3.1.2 Calibration AF/AL N/A N/A Data Analysis (Dan,) l: Ambient Temperature 0.2% = 0.02 V 6.4, 3.1.5 Sensitivity (Te.)
' ~
Ambient Pressure N/A' 3.1.3 , Sensitivity (Pe,) Power Supply N/A 3.1.4 Sensitivity (Ps,) Radiation N/A 3.1.1 Sensitivity (Re,) Seismic Oncertainty N/A 6.13 j L , (Se.) , j .-- - . - - __
' Static Pressure N/A N/A' #
% Sensitivity (Sspz) Readability N/A N/A l
- - (Rd3 )
Reset Hysteresis (BH) 0.1 V 6.4 l i l SCE 2926 REV 0 SS4 (REFERENCE SO123 XXN.715) Pfd fI:II 66, II uer S2S2-892-676:xed _SdI63 J 938 E03 OnN
. _ . . -- : : - ': w.
^ : : . ' = :~ ^ ~ ^ ^ ^ ~ ^ ' ' ~'
NES&L. DEPART' AENT ICCN NO/ PRE'lu, CCN NO. N4 "3 CALCULATION SHEET . PAGE 24 of _%_ CCN CONVERSION: Project w DCP / FCN N/A Calc No. J-SSA423 CCN NO CCN. Subject DNQUOLOG WJt 'fRt> IrYPASS Sheet No. of REV ORIGINATOR DATE IRE DATE REV ORJGINATOR DATE IRE I DATE 5 0 0. "" - 03194t3 E. ch 031343 h
$E 3 l
FORM 4: ENVIRONMENTAL CONDITIONS DATA SHEET Area BS: Cabinet Area of Control Room
$ DATA REFERENCE Normal Temperature 70 'F 12.5 6.1 Minimum, 'F Table 9.4-4 3.1.6 Normal Temperature 75 'F e2.5 6.1 Maximum, 'F Table 9.4-4 3.1.6 Normal Radiation < 1.0E4 RAD TID per 40 yrs 6.3 Value, gamma Rads Table 0-1 Normal Pressure . O psig 6.3 Minimum, psig Table 0-1 Normal Pressure o psig 6.3 Maximum. psig Table 0-1 Accident Temperature 80*F (Cabinet Area) 6.3 Maximum. *F Figure C-5 Accident Radiation < 1 10' Rad 6.3 Value, Rads gamma Accident Radiation < 1*10' Rad 6.3 Value. Rads beta Accident Pressure O psig 6.3 Maximum, psig Table 0-1 w.#
[ I t l SCE 26 426 REV 0 &S4 (RETERENCE SC123 XXN-7.15)
.M2LA M (P -. % W L-R@ t-%
.- -.- ~ . . . . . . . _ . .. _ . . . - .
NES&L DEPARTMENT ICCN Nol g3 CALCULATION SHEET PRENCN No. DAGE 25 cf A CCN CONVERSION: Project or oCP / FCN N/A Calc Nc. J-SBA.C23 CCN No. CCN. [. sub;cc DNatPDACG POWUt TRS trYPA$$ Sheet No. of
- REV oRlGINAToR DATE ' 1RE DATE REVI ORIGINATOR '
DATE IRE DATE 'c; o D. McQuade 00 19 93 E. Quinn 03 1S-93 0 kI
; 5.0 Methodology i .
- 5.1 This calculation will determine the instrument uncertainty and associated setpoints for the DNB/LPD/ LOG Power Bypass. This calculation is performed l
,g consistent with the requirements of SCE Design Standard, JS-123-103C, Rev
'f 0 and Revision 2 for CCN N-1 (reference 6.7). l The input uncertainties associated with the 10"% bistable input are identical to those associated with the input to the High Log Power trip. These functions
- receive their input from the same Excore circuits and therefore, any uncertainties associated with the input signal will affect both functions the i same way. As such, the setpoints of the 10d% bistable will consider the l uncertainties associated with the bistable only. l l
I l S.2 Process Measurement Uncertainties i 4 The excore instruments are susceptible to decalibration due to process measurement effects. The effects to be considered are those that affect the power shape of the core (rod shadowing, radial xenon distribution, and burnup), and those that affect the number of neutrons arriving at the detectors from the core (temperature shadowing and boron shadowing of water in the reactor vessel downcomer). l In this calculation, only the power being immediately produced by the fission and delayed neutrons is assumed to produce a signal at the detectors. The effect of other neutrons associated with sources that do not reflect the instantaneously change in power level, for instance photo neutrons resulting from the decay of fission products or neutrons from neutron sources, are l ignored because at the bistable setpoint, the number of these neutrons is smaller than the fission neutrons by many orders of magnitude. The bistable setpoint is based on the power being produced by fissions
- because the nuclear instruments are used to control the existing core power.
Even though the calibration of the log power channels is based on core average thermal power, the setpoint is not based on core thermal power, which is a combination of the power being produced by fissions and decay heat. Decay heat can be considered a reflection of power that was produced in the past. At the bistable setpoint, core thermal power due to decay heat
,CEICd* 4V C Flu (REFERENCE SO113 XM.7.iS)
%2 'd U:301 WtM C)$2 D - KM 9hThitLA~4LMG'DnN
NEST.L DEPARTMENT ICCN NO/
"^ '3 CALCULATION SHEET PREUM CCN NO. PAGE 26 of CCN CONVER$lCN:
Project or DCP / FCN N/A Calc Nc, J-$BA 023 CCN NO CCN. f Sutwact D68RPDADG POWER Tne evPAss Sheet No. of REVI CRIGINATOR DATE IRE DATE REV ORIGNATOR DATE IRE DATE 3 o o. mw. cn is-sa E. e,= ca. sus g qls can be expected to be a nearly constant source of heat that is several orders of magnitude greater than the power being produced by fissions. The detectors, which are located outside the reactor vessel, produce their signals from neutrons produced mainly in the outermost assemblies. These neutrons are produced mainly by fission, and the number of fissions is directly proportional to the amount of power being produced by fissions within an assembly. Changes in the core power shape are important because the core power shape determines the power of the outermost assemblies relative to the average core power level. The core power shape is changed by insertion of control rods (called ' rod shadowing), the radial concentration of xenon, and burnup. The number of neutrons reaching the detectors is also affected by the density of water in the downcomer of the reactor vessel. The effect of boron concentration will not be considered separately from the temperature effects because the neutrons arriving at the detectors are high-energy, whereas the high cross section of boron absorbs thermal (Iow energy) neutrons. Each effect is discussed also below. The first three effects considered below are in conjunction with the core power shape: 5.2.1. Rod Shadowing Core power shape is affected by the position of the control rods, and core power around the rods is depressed by insertion of control rods. If the control rods are inserted in the region of the core that supplies neutrons to detectors, there is a reduction in the number of neutrons to the detectors. This effect is called ' rod shadowing' T e nuclear detectors can be expected to be increasingly shadowed _a the rods are inserted. In practice, the rods can be expected to be nearly fully withdrawn during the calibration at full power, for zero rod shadowing. It is possible for the reactor to be significantly rodded at low power levels. i in Revision 0 to this calculation, the expected value for rod shadowing was 13.5%, and in order to ensure conservatism, the value that is actually used was conservatively chosen to be a two-sided 23%. The factor for rod shadowing therefore becomes: CE 26-426 REV 0 4/94 (REFERENCE 50123 xxN-7.1s)
. [d . . PI*II. 66. II Wf . .
S252-892-6P6:XPJ SdIdddd 936 ad3 DnN
NEs&L DEPARTMENT ICCN NOJ N4 of %g PREuM. CCN NO. PAGE ' ~l7 CALCULATION SHEET CCN CONVERSION: Pic3ect or oCP / FCN N/A Calc No. J.SBA423 CCN No. CCN. f saojerr. DNett.pMcG powsm Two BYPAES Smeet No. of REV ORIGINATOR oATE I 1RE DATE REV ORIGINATOR CATE IRE DATE g C D.Machasse c3-1643 E. b an 031S4J .O hI__ FNaOS = 23 % T 5.2.2. Radial Xenon Power Shift i The wide range instrument channels are calibrated and calibration checked at full power, with a radial power distribution that can differ from the distribution at the power levels where the bistable is used. This transient effect is most pronounced if thc core has been at high power levels prior to a trip, and a reactor startup is timed so criticality occurs at the peak of the xenon build-in and decay curve. Startups can be expected to occur when the xenon concentration is at its peak, approximately 16 to 18 hours following a trip. The radial power distribution changes because, for example, at high power before a trip the middle of the core can be operating at a higher than average power and be producing more fissions. The greater number of fissions produces more xenon atoms after a trip, when xenon builds-in. The greater number of xenon atoms depresses the power in the middle of the core, which shifts power to the periphery if the core is brought critical with appreciable ( xenon still in the core. Conversely, the pre-trip power shape at high power can have the flux in the : middle of the core depressed and result in a relatively low post-trip peripheral
~
power shape. A value of 10% is chosen by engineering judgement for the change in signnt due to xenon redistribution at the bistable setpoint following a trip from high power. r FmN = 110% l i
- The radial xenon power shift is independent of rods and core burn-up and !
depends on the basic physics of xenon build-in and decay. _ _ _ f
+
( L 5.2.3. Core Bum-Up 1 ! The wide range channels are normslly calibrated once every cycle at the beginning of each cycle. The radial power shape changes from beginning to end of cycle as fuel and burnable poisons are consumed. The change due to
- j. shape has been calculated to be 10% (Section 8.2.5 of Reference 6.16).
l 30E 26 426 REV e e/94 (REPERENCE SO123-XJIN 7.1$) L 82 'd _ PI:II. 66.IIu?f _ S2Sl-89E-6tr62.W3 SMIdddd 938 E6313nN
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I
- - - . . . : u :.= :. = * ': ^ ~ ^ ^ " '^ "
l l NES&L DEPARTMENT 60CN tso> PREW CCN NO. N.1 5 l CALCULATION SHEET pag { 25 of g CCN CONVERSION: l Pro 3ect or DCP / FCN N/A Cate No J-SBA-023 _ CCN NO. CCN- /
' Sut>get twatpWLoo powta TR* trypAss i Sheet No. of
~
(i REV oR!GINATOR ' A DATE tRE ' DATE REV: ORIGINATOR DATE IRE DATE % j l o o. e os.ss-s2 g.Osan o>im S
. l 45 FauRuu,= 10%
Because the net effect of the changes due to rod shadowing, radial xenon power shift, and core burn-up are independent, they will be treated as the Sum of Root Sum Squared (SRSS): Net Effectc.,,% = ( (Fyo33)2 ,(p,g,w)2+ (psuRNue)'f* [ Net Effectc.,,% = (( 23%)2 + ( 10%)2 + ( 10%)2 ) 5 = ( 729 % ) S l Net Effecte % = 27% 5.2.4. Temperature Shadowing. ;
- l. '
The neutrons from the core pass through water in the reactor vessel downcomer which attenuates and scatters some of the neutrons and thereby reduces the neutron signal at the detectors. Decreasing the temperature of the water increases the density of the water and results in fewer neutrons reaching the detectors. This effect is called ' temperature shadowing' and is , an effect that has been measured. i The temperature limits for actuation of the bypass and the reset are assumed to be the analysis temperature limits for criticality at 0% power. The Reload Ground Rules for Cycle 10, Unit 2, (Reference 6.15), whicn reflect present and future cperation of the plant, specify a Transient Analysis (TA) L temperature range Tcold of 520'F to 560*F in RGR Figure 111-2 for o power, a range of 40*F. The new reduced operating limits for criticality, by Technical Specifications, are a Teo!d of 522'F to 558'F. Ternperatures outside the limits for criticality will not be considered because the bypass is a maqual operation and is operated under close observation and carefully controlled conditions. It would be operated only under Mode 2 ' conditions, with the reactor at very low power level. The reset is enabled following a reactor trip. The range of normal operation following a reactor trip is also assumed to be within the limits for criticality. The instruments could be calibrated at, for instance, the highest teriperature and then used at the lowest. The maximum increase or decrease in scE 292s Rev o em (RersneNCE sOtra-av-7.is) l I l
l l NESAL DEPARTNENT ICCN NOJ MEuM CCN NO. 3 CALCULATION SHEET PAGE 29 q_ g CCN CONvCRSION: P oject or DCP / FCN N/A SWcet DN&tPC, TOG POWER Trip BYPASS Calc No. J-SBA423 CCN NO. CcN. ! Shuct No. of REV CRIGINATOR DATE < IRE DATE REV ORIGINATOR DATE I 1RE " DATE e o D. McQuade OM%s3 E.Chann 03-1H3 3 .$ q! temperature to the limits would be 40'F. The uncertainty of the CPC cold leg instruments of 3.0*F (Section Vill, item Vill.001 of Reference 6.15) must be added to the change of 40*F, for a total that will be taken to be 43*F. The measured temperature shadowing effect is approximately 0.6%/'F. For conservatism, the temperature shadowing effect will be assumed to be 0.8 of signal / *F. The temperature shadowing uncertainty is the temperature shadowing etTect multiplied by the change in signal, or: Tsau = 0.8% indication / 'F x 43 *F T sv = m.W. 5.2.6 Summing The Effects The four effects listed above are independent and the sum of the effects will be taken as the SRSS: Net = ((Net Effect C .,,%)2 + ( T sv F F Net = (( 127% ,2 + ( 34.4% )2 yes = (1912.36% ) 5 Net = 143.7% Revision 0 of this calculation used an uncertainty of 53.4%, which will be used in CCN N-1. The difference between 53.4% and 43.7% is 9.7%, a margin that is reserved in this calculation to ensure that the Process Measurement Effects are conservative and satisfies the intent of a margin of sit least iO.5% as required in the Calculation Standard (Reference 6.7, Revi.f ion 2). , 5.3 Calculation of 10"% Bistable Process Measurement Effects The Net effect in Section 5.2.5 must be converted to a voltage from a percentage of full scale. The resulting voltage applies to the entire ccale, at full power or at the bistable setpoint of 10"% power. There is cne decade per volt for 10 decades of full scale, from 2 x 104 % power tc 2 x 102 3CE 26426 REV O E94 (REFERENCE SO123-XXN-7.15) OR A e9.99 R R__$l5LJur-# 6
NES&L DEPARTMENT ICCN NO/
*1 p CALCULATION SHEET PREUM. CCN No. PAGE 30 of scL CCN CONVERSION:
Pmiect or oCP / FCN N/A Calc No. J-SBAW3 _CCN NO. CCtJ. ! Subl ed DNBtPOA.oc POWER TRLD BvPAss Sheet No. of REV l ORIGINATOR DATE IRE DATE REV ORIGINATOR oATE IRE DATE E C O. M =4 03. % 93 E. Oam c31No g 5 yH i power. The basic equation for the log power channels is:
% Power = 2 x 10* 8) Where V = Volts signal l Rearranging: V = 8 + Log (% Power / 2)
De Voltage at 100% power is: V,oo, = 8 + Log (100 / 2) = 9.699 V The decalibration of 53.4% is calculated from 100%. The percent power at the decalibration is 100% - 53.4 % = 46.6% V f,, = 8 + Log ( 46.6 / 2) = 9.367 V The difference in voltages is: Ve=w n = V,oes - V .sg Vw,% = 9.699 V - 9.367 V V,mm = 0.332 V decalibration Thus, the decalibration is 0.332 V, or 0.332 decade, and applies to any part of the instrument range. ; 5.4 Conversion of Engineering Units l
~ ~
6.4.1 Because the wide range excore is a logarithmic channel, the calculations will be performed in volts, and then converted to a percent power value for T
- i. the log scale. In determining the allowable setpoints for this bistable, two cases were examined. For a decreasing power, the point at which the High l
Log Power Trip should NOT be in bypass becomes the basis. The High , Log Power Trip cannot be bypassed at a power level which the low power transients are difficult to be controlled without the High Log Power Trip in place. Typically, SONGS 2/3 is considered stabilized for increasing power SCE M26 REV 0 8/94 (REFERENCE $O123 XXN.7.1!) 12 'd - ST:II 66. II ver S2S2-892-676:xed S3Idd30 938 803 DON
NES&L DEPARTMENT icCN No/ PREUM CCN NO. 63 PAGE 31 v 3, CALCULATION SilEET ccu ccNvtRsion: Proioci or DCP / FCN N/A Calc No, J.RBA 073 CCN NO CCN. ! Subject CN&tPD&OG POWER TPJP BYPASS Sheet No. of REV' ORIGINATOR DATE RE DATE REV CRIGINATOR DATE tRE DATE y 0 D. Mcchmule obis 43 E. Cmen C3-443 ,
.t.
at approximately 10.s% RTP. For an increasing power, the power level at which the High Log Power Trip can be bypassed is a power level that the neutron flux level is considered to be stabilized. When evaluating an increasing signal for this function, the p High Log Power Trip must also be considered. The High Log Power Trip - setpoint is 0.837% power. The High Log Power Trip TLU has been subtracted again to be conservative in accounting for the High Log Power Trip bistable uncertainty. This trip function must be bypassed in order to bring the reactor to full power. The voltage used in the calculation for this power level was derived as follows:
%PWR = 2 x 10" (Base equation for log channel)
Let (v-8) = X 0.351 = 2 x 10* 0.1755 = 10* Log 0.1755 = X Log 10 X =-0.7557 If X =-0.7557, then (v-8) = -0.7557 V = 7.244 volts Similarly, the 104% RTP voltage used in the calculation was derived as follows:
% PWR = 2 x 10" r 104= 2 x 10*
5 x 104 = 10* Log 5 x 104 = X Log 10 ACE 25-426 REV C 694 (REFERENCE SO123-XXV.7.15) ; C MT-SM WA SNIdddd 93s ad37 D
NES5L DEPARTNENT ICCN NO/ PREuM. CCN NO. 53 CALCULATION SHEET PAGE 32 of JL CCN CONVERSION: Protect or oCP / FCN N/A Ca.C No. J.SBA C73 CCN NO CCN. f Subject DNIULPD/ LOG POWER Trip BYPASS Sheet No. v, REVi oRIGINATCR DATE IRE DATE REV ORIGINATOR DATE IRE DATE y 0 D. McQuece 03 19-93 C. Qwan 0315H0 g Ej }E X =-5.301 If X =-5.301, then (v-8) = -5.301 V = 2.699 volts t CCN N-1 establishes an Upper Operational Limit and Lower Analytical Limit for the DNB/LPD/ Log Power Trip Bypass Seipoints as set forth in Design input 4.8. The above derived voltages are not directly used in CCN N-1. The voltages for the new limits used in CCN N-1 are derived as follows:
% PWR = 2 x 10M or V = 8 + Log (%PWR/2)
For the Upper Operational Limit of 4E-4% Power - V = 8 + Log (4E-4%/2) V = 4.301 Volts For the Lower Analytical Limit of 1.5E-5% Power - V = 8 + Log (1.5E-5%/2) V = 2.875 Volts 5.5 Word Processing Disclaimer This document was produced using Wordperfect 5.1. All computations were performed and verified with a hand-held calculator. Wordperfect did not perform any computations in this design calculation.
~
'.CE 26-425 REV c ES4 (REFERENCE SO123-XyN-7.15)
EE 'd 91:II 66, II cef $2S2-892-676:XEJ S610330 933 dd37]nN
NESib DEPARTMEr(T ICCN NOJ PREuM. CCN NO. N4 p CALCULATION SHEET PACE 33 or g Project or DCP / FCN N/A CCN CONVERSION: f Cat No. J.SBAE CCN NO. CCN- ( suejcet eNatpuoc PowtR TRJP syPAss Shed No. of REV l ORIGINATOR DATE l IRE DATE REV ORIGINATOR DATE IRE DATE 8 o D. m co-um l E. Osa obse3 g I 43 6.0 References 6.1 SONGS 2&3 Final Safety Analysis Report (FSAR), Rev. 8, and Revision 13 for CCN N-1. p 6.2 Unit 2 Technical Specifications (Amendment 104) and Unit 3 Technical Specifications (Amendment 95), and TS Amendments 127 and 116, respectively, for CCN N-1. 6.3 Environmental Qualification Topical Report, Design Bases Document, DBD-SO23-TR-EO, Rev. O. 6.4 Safety Channel- Operation and Maintenance Manual, Prepared for Combustion Engineering Inc. for San Onofre Nuclear Generating Station, Units 2 & 3, General Atomic Company, July 1983. SO23-941-45. 6.5 Surveillance Requirement , Nuclear instrumentation Safety Channel; SO23-11-5.1 thru 5.8. 6.6 Excore Nuclear Instrumentation System Design Bases Document; DBD-SO23-470, Rev. O, and Revision 3 for CCN N-1. l 6.7 SCE Setpoint Methodology Standard, JS-123-103C, Rev. O. and Revision 2 for CCN N-1. 6.8 CE-NPSD-570-P Rev. 03-P, Plant Protection System Setpoint Calculation, (SO23-944-C50-0). SO23-944-C50-3 for CCN N-1. l 6.9 1992 Design Basis Document Program Plan, Rev. 6, February 92, page B2. 6.10 Letter from U.S. NRC dated 1/12/90, NRC inspection of SONGS Units 2/3, Report NO. 50361 and 362/89-200. i 6.11 SONGS Electronic Data Base - PEDM, Verified 8-29-86. 6.12 SONGS Units 2 & 3 CPC and CEAC Data Base Listing. CE NPSD-337-P, Rev. 00-P, Dated January 1986. set 2426 REV O 854 (REFERENCE SO1210N-715) . . . . . . . . . . 172 'd 91:11 66 li uPr S2S2-892-6tT6:XPd ..._ SdIdddd 933 Bd3 DnN
NES&L CEPARTMENT ICCN NO/ p$
"^
CALCULATION SHEET ""'"" CC" " - PAGE 34 __ m I CCN CONVERSION: Prmoct or DCP / FCN N/A Calc No. J.SBA.023 . CCN NO. CON- ! Subject DNBr.pO/ LOG DOWER TRIP BYPASS Sheet No. of REV ORIGINATCR DATE tR6 DATE REV ORIGINATOR DATE IRE DATE g 0 D. McQuade 03 1S43 E. Quinn 03-t143 g h
- q z 6.13 Test Report, Seismic Testing of Safety Channel Electronic Chassis Type ELE 304-3000, Report NO. E-115-539, dated February 1976 6.14 SCE Nuclear Fuels Management Calculation NFM-2/3-TA-0008. l e 6.15 Unit 2 Cycle 10 Reload Ground Rules, RGR-U2-C10, Revision 0 l 6.16 Neutron Flux Level Startup Channel Removal Signal. J-SEA-023, Revision 0
,CE 26-425 RTV O ES4 (REFERENCE S0123-XXN-7.15)
Cf *J OT TT FA TT Upr c>c> coe_Anc.xpa cwTwaay 07w pwayphj
NES&L DEPARTMENT ICCN NOJ PREW CCN NO. "d $ CALCULATION SHEET PAGE 35 & Project or oCP / FCN N/A Cak;No. J SBA 023 CCN CONVERSloN: / CCMNO CCN. / SAject ONBUCAOG POWER Trip SYPASS Sheet No. of REV ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE DATE 5 o D.Moouses os.t>.ss E. ov nn ca.i>sa j i 15 !
-7.0 Nomenclature i
7.1 Safety Functions (Reference 6.9) Those systems, structures or topical issue functions'that directly or indirectly support one or more of the following plant nuclear safety I performance goals: l l
- 1) Maintain reactor coolant pressure boundary integrity.
- 2) Provide capability to shutdown the reactor and maintain the safe shutdcwn condition. 1
- 3) Prevent or mitigate the consequences of accidents which could potentially result in off-site exposures comparable to 10CFR Part 100 guidelines.
The term " safety related" applies to the prevention or mitigation of the consequences of postulated accidents that could cause undue risk to the health and safety of the public. Important-to-safety relates to " plant safety". 7.2 Additional terms used in this calculation: - - AV i - Allowable Value for increasing setpoint l AV,- Allowable Value for decreasing setpoint l CPC - Core Protection Calculator l DNB(R) - Departure from Nucleate Boiling (Ratio) l _. .ELFP - Effective Linear Full Power _ _ o LOL - Lower Operational Limit (section 4.2) l LPD - Local Power Density l UOL - Upper Operational Limit I
;ct 292s REv o see (REFERENCE $0123-XXIV-715) 92*d .9i:II .66. II.uer $2S2-892-6176:xed S3IO336 933 8031]nN
m _ - _ . . ~. _ _ . . . ' NES&L DEPARTMENT CALCULATION SHEET llCCN NO/ 1PREUM. CCN NO. PAGE 36
') E. ,
CCN COWERSION: Project or DCP / FCN N/A Calc No. J.SBA 023 7 CCN NO. CCN- f Sutvect DNR/LPS/ LOG POWER TRsi swAss Shoet P.o. of REV ORIGlNATOR DATE IRE DATE REV ORIGINATOR DATE 1RE CATE E 0 yaf D. McQuade 03 19 93 ' E. Quinn $319.a3 g I 8.0 Calculations 8.1 Design Basis of 10"% Bistable Setting The withdraw of CEAs from suberitical or low power conditions adds T reactivity to the reactor core, causing both the core power level and the core heat flux to increase together with corresponding increases in reactor coolant temperatures and reactor coolant system (RCS) pressure. The withdraw motion of CEAs also produces a time dependent redistribution of core power. These transient variations in core thermal parameters result in the system's approach to the specified fuel design limits and RCS and secondary system pressure limits, thereby requiring the protective action of the reactor protection systems. At suberitical and low power conditions, the normal reactor feedback mechanisms do not occur until power generation in the core is large enough to cause changes in the fuel and moderator temperatures. The reactivity insertion rate due to the CEA withdraw rate and the rod worth determines the rate of approach to the fuel design limits. Parametric analyses have indicated that the lowest initial power level of 10'% _ , _ _ suberitical core condition, results in the closest and fastest approach to the _ _ fuel design limits during the CEA withdrawal transient. Initially suberitical, zero power CEA withdrawal transients are terminated by the High Log Power Trip wiule those initiated from a power level just above the High Log Power trip bypass of 1 E.5% power are terminated by the CPC low DNBR l (VOPT) trip or the high LPD trip. Parametric analysis has shown that at power levels above 1E-5%, reactivity feedback mechanisms prevail and l provide a dampening effact on the severity of the transient. The uncontrolled CEA withdrawal from suberitical conditions resulted in a power spike. The minimum DNBR calculated for this event was greater than the design limit. The peak linear heat generation rate was calculated ,
. to be 25.5 kw/ft which is in excess of the steady state acceptable fuel centerline melt limit of 21kw/ft. However, the fuel center line temperature ~
was less than 4900*F and, thus, the fuel is not predicted to melt. Since the power increase for this transient was so fast, a power spike of over 60% power, the instrument uncertainties on the trip bypass setpoint would not affect the results of the transient. Based on engineering judgement, no instrument uncertainties were needed in determining the bypass setpoint. LCE 26426 REV 0 8/94 (REFERENCE SQ123400V.7.15) v&-.' n Mh29 tvL 5L57 -.upt eJuT L4ct-8MLo1;FU @XTJMALMM 3%G* DOM .
__ . . . - - - . - . . _ _ _ . - . _ _ _ ~ -._. m. _ i
~
i NEs&L DEPARTMEWT ICCNfeOl - N4 l CALCULATION SHEET PRELIM. CCN NO. PAGE 37 of ! Protect or DCP / FCN N/A C&&c No. J-$8A423 CCN CONVERSION: j CCN No CCN. f subject CNWLPOILOG POWER 'rRip BYPASS sheed No. of , REv ORIGINATOR DATE IRE DATE REV: ORIGINATOR DATE 1RE DATE E o D.McQwam 031M E. QWne 03-tm S qz l, This CCN F uses a Lower Analytical Limit (LAL) of 1.48E-5% to ensure that the accident analysis limit is not exceeded. Also, the analysis !. considers that the DNBR/LPD trips have been inserted above 4.1E-4% ll power. Although not a safety limit, the 4.1E-4% power serves as an Upper
~
Operational Limit (UOL) when analyzing low power conditions. It further ensures sufficient margin for manual bypass operation. lf. - 8.2 Setpoint Selection The primary functions of the 10"% bistable setpoints are to permit a manual l bypass of the High Log Power trip and the DNBR/LPD trip functions and to automatically reinstate these trip functions when required. In the case of the High Log Power trip the bistable setpoint must meet two requirements. The setpoint for enabling the High Log Power trip must be set at a point were the protection this function provides is required to protect the reactor against CEA withdrawal transients. Parametric analysis has shown that i this prctection is required for CEA withdrawal transients initiated from l power levels below 1E-5% power. The setpoint must also allow for l l sufficient margin between the bypass setting and the High Log Power trip setpoint to allow the operator sufficient margin to perform the manual bypass without causing an inadvertent unit trip. With the present bistable l setpoint, approximately three decades of reactor power separates the l bistable trip setpoint and the High Log Power trip setpoint. Experience has shown that this is sufficient margin for the operator to perform the manual bypass prior to reaching the trip setpoint. 8.2.1 Basis For Setpoint 10^ Increasing
- 1. Bypass permissive, Hign Log Power - The bistable action permits the high log power trip to be bypassed. This function is not significant from a nuclear safety perspective since failure to bypass r the high log power trip would result in a reactor trip as power was increased. It is recognized that inadvertent reactor trips present i challenges to safety systems and shou d be avoided. This is accomplished by administrative controls and establishing the bypass setpoint below the high log power trip setpoint.
CE 26426 REV C &S4 (RETERENCE SO123 XLV-7.1S) 8E 'd 4I:II 66. II Uef $252-892-676:XP3 SdIO330 033 303TnN
NES&L CEPARWENT , ICCN NO/ Gj CALCULATION SHEET '"'""CNN . PACE 38 of _h CCN CONVERSION: Pre;cct or DCP / FCN N/A Calc No. J-SBA423 CCN No. CCN-Sutect CPP>L*ty.OC POWER TMP SYPASS Sheet No. of REV oR:GINATOR oATE IRE DATE REV l ORIGINATOR DATE 1RE DATE 5 o c.ueouw. os.tses E.c a n o3.em Dl
- 2. Auto bypass cancel, DNBR/LPD trips and Low Reactor Flow trips -
This bistable action is safety related. If this " Auto Bypass Cancel" I action fails, The safety functions (DNBR/LPD and Low Reactor Coolant Flow trips) are prevented from operating in a mode where
, they are credited by the accident analysis. Though the High Log l Power Level trip might protect the reactor by being active in this i mode (it is normally bypassed), that cannot be credited because it is not analyzed.
10"% Decreasing
- 1. Auto Bypass Cancel, High Log Power Level trip -This bistable action is safety related. If this " Auto Bypass Cancel" action fails, the safety function (High Log Power Level trip) is prevented from operating in a mode where it is credited by the accident analyses.
- 2. Bypass Permissive, DNBR/LPD and Low Reactor Coolant Flow Trips - This bistable action perinits these trip functions to be bypassed. This function is not significant from a nuclear safety perspective since the failure to bypass would result in a reactor trip once the shutdown or part length CEAs were inserted or a reactor coolant pump was secured.
8.3 TLU Calculation for the High Log Power Bypass Setpoint The following forms 5-11 contain data for the High Log Power Bypass bistable. The TLU is calculated for this bistable. - p ._ 3CE 2u26 REv c &T,4 (REFERENCE. SO123.XXN.7.15) [ ISR 'd h f UPf GLGt-19R-6AG:XEd B M isH 93N AH3iTIN
l NES&L DEPAQWENT ICCN NO3
"^ '3 PREUM. CCN NO. PAGE 39 L CALCULATION SHEET CCN CONVERSION:
Propet or DCP / FCN N/A Calc No. J.SBA423 CCN NO. CCN- [ Suciect DNM.PoAoc powrm Tsup onAss Sheet No. of REV' ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE 1RE DATE E D O. McQuade 03-1643 E. QWnn (01993 .b B 1I
- F.ORrA 5: NORMAL CONDITIONS ENVIRONMENTAL ALLOWANCE Tag Device 1 Temp. Min. 67.S'F 1 i
Temp. Max. 77.5* F Temperature
- 0.2% ELFP l Sensitivity Temperature 0.2% ELFP l Effect Te, SUM of Te,'s 0.02 v i
for common l location i i Square of 0.0004 v sum Te.2 SUM OF SQUARES, TE, = 0 0004 v2 T Press Min. O esig l Press Max. O psig Pressure N/A Sensitivity Pressure l N/A Effect Pe. i SUM of Pen 's N/A l for common
~
- Location a <
Souare Pe,2 N/A SUM OF SQUARES, PE, = N/A 4
.;CE tu26 REV o Es4 (REFERENCE SO123JXV 7.15) b GCd itXIXL _J i 71 UEf MM 89E-676:XE3 SEIddid 933 ad3 OnN
NES&L DEPARTMENT ACCN N01 Nd 59 ! CALCULATION SHEET PRELIM. CCN NO. PeGF e of 1_ l CCN CONVERSION. Progt or DCP / FCN N/A Calc No. J $8A@ CCN No. CON. ! SubiM DWtPD/ LOG DOWER TRIP BYPASS Sheet No, g( REV ORIGINATOR CATE IRE DATE REV ORIGINATCR DATE IRE DATE "g C D. MuQuase 061HS E. Owenn C3.a e-s3 g y qf FORM 6; ACCIDENT CONDITIONS ENVIRONMENTAL ALLOWANCE ! l Tag Device 1 1: Temp. Min. 67.5'F Temp. Max. 77.5' F l Temperature N/A L Sensitivity Temperature N/A' , Effect Te. SUM of Te/s N/A l for common i location i Square of N/A i l sums Te 2 _ i l SUM of Squares, TE,= N/A i
~
l Press. Min. O psig ! Press. Max. O psig I l Pressure N/A Sensitivity Pressure N/A Effect Pe, SUM of Peis for N/A common - , location Square Pe,2 N/A 4 . SUM OF SQUARES, PE, = N/A CE 26426 REV 0 t/94 MREN;l:E 50123-xxlV-7.15) 1 l. L
.IPTd. ,._81:II. _66. II,UFC ..
. . _ _ .S252-892-606:x?J .SMIdidd 933 d E ]GN
NES&L t EPARTMENT ICCN NOJ PREW. CCN NO. 6} CALCULATION SHEET PAGE M of & , CCN CONVERSION: i Project or DCP / FCN N/A Cak: No. J.SBA423 CCN NO CCN. sutyxt owtutPC/ LOG POWER TR9 m9 Ass Stret No. of REVl ORIGINATOR DATE 1RE DATE REV1 ORIGINATOR DATE I 1RE DATE "g e o. m . an.im E. e-a as.im gj 4s FORM 7: SEISMIC ALLOWANCE Tag. Device 1 Max. Seismic N/A Acceleration Seismic N/A Sensitivity Seismic N/A Effect (Sc) Square N/A SUM OF SQUARES, SEISMIC ALLOWANCE, SA = N/A RADIATION ALLOWANCE i Tag Device 1 Max. Total <1.0E4 Rad Integrated Dose Radiation N/A Sensitivity Radiation N/A Effect SUM of N/A common locations Souare N/A e SUM OF SQUARES, RADIATION ALLOWANCE, RA = N/A JCE 26426 REV 0 654 (REFERENCE SCC 3-XXW 15) Wd 81:II 66. II uer $2S2-892-676:XP3 SbI6idd 938 88313nN
NES&L DEPARTMENT ICCN NQ1 } l CALCULATION SHEET psu cCN N . ,eAce .2 em-CCN CJNVERSION: Pro;ces or DCP / FCN N/A Ca.c No. J-S B AE CCN NO- CCN. / seso oNs.uotoc power wia 8'WA$$ Short No. of REV ORIGINATOR DATE 1RE DATE REV ORIGINATOR CATE tRE DATE E C D.Mco m C31943 E. Quinn 03.1493 h
!3 FORM 8: CAllBRATION ALLOWANCE Tag Device 1 _
Input Cal Device Accuraev i O.5% ELFP,0.05 v Output Cal Device Accuracy N/A Setting Tolerance for 0.1% ELFP Increasing Setpoint (St,) 0.01 V Decroasing ScipOint (St ) *0.2E% ELFP 0.025 V Sum of Squares for 0.026% ELFP increasing Setpoint (CA,) 0.0026 V Sum of Squares for 0.0313% ELFP Decreasing Setpoint LC_A-) 0.0_0313 V SUM OF SQUARES, CAllBRATION ALLOWANCE (CA,) = 0.0026 V 2 (increasinal SUM OF SQUARES, CAllBRATION ALLOWANCE (CA,) = 0 00313 V2 (decreasina) POWER SUPPLY ALLOWANCE Tag Device 1 Min. Voltage N/A Max. Voltage N/A Power Supply Sensitivity N/A Power Supply Effect N/A , SUM of common Supplies N/A Square N/A SUM OF SQUARES, POWER SUPPLY ALLOWANCE, PSA = N/A 2CE 26 426 REV c &94 (REFERENCE SC123-XXN-7.iS) EP *d 81:11 66. II uer $252-89E-606:xP3 SBIdiid 933 ad313nN
. . _ ._ _ . _ _ _ _ . . _ _- . _ .. _ .. _ ._ _._ _ _ _ . _ . _ _ . . . _ . . .. . . _ . . . = _ .
NESOL DEPARTMENT ICCN NO/ . j CALCULATION SHEET """""**""- " CCN CCNVERSION: Project or DCP / FCN . N/A CWc No. J-S B A-023 CCN NO. CCN. [
. Suhect . DNB/LPQtOG DOWER Trip BYPASS Shmt No, of REV ORIGINATOR DATE IRE i DATE REV ORIGINATOR DATE I 1R E DATE "o ;
O O.McQ aee 031583 E. Qvinn 011&s3 g L El {E FORM 9: DRIFT /AF-AL ALLOWANCE Tag Device 1 ,
. Calibration 31 DAYS Interval Drift Rate 0.5% ELFP Drift over 0.5% ELFP Cat Interval 0.05 v Squares 0.0025 v I
SUM OF SQUARES,' DRIFT ALLOWANCE, DA = 0 0025 v2 l. FORM 10: CABLE LEAKA E ALLOWANCE ' DescriptionNatue Reference Remarks Cable Leakage N/A _ _ (Ci) Terminal N/A _ ._._ j Block Leakage (Ti) . Penetration N/A _ _ Leakage (Pi) Splice .N/A _ _ I. 4 Leakage (Si) L l- Sealing N/A _ ._._ . i Leakaoe (Di) } f ;Cz zwa Rsvo am eteeneweE sei:nsne L l l Ec.) @I: II. 66, p ceg _ gggg-89g-6t76 PP3 . SNI6330 933 803 OnN
. _ . - _ _ = - . _ . .
NES&LDEPARTMENT lCCW NOJ
* $ 'f PREUM. CON NO.
CALCULATION SHEET PAGE 44 ct _% CCN CONVERSION: Preject or DCP / FCN N/A Cale No. J-$84-023 CCN NO. CCN. ! Subject DwJMoo POWER Trap 8Y9 ASS Sheet No. , of REV ORIGINATOR CATE tRE DATE REV ORIGINATOR DATE tRE CATE 5 C D. McQuade 121943 E. Ownn c319 33
~
,. h Ej k FORM 11, SHEET 1: CALCULATION
SUMMARY
(for the High Log Power Bypass Value)
- 1. PRONRK ALT _fWANCE (PA) (frcm Forin 1)
PA = (Pma)2 ). . PA (0. 3 32 v._) 2 PA = 3 115 V8
- 2. A"NCY AT.TAWANcE (AA) (from Form 3)
AA s ( Aa3 ) AA = ( ,,,Q i O S V ) E AA = 1 0025 V8 3, E!ICJT TANEctTE AIT OWANCE (!!A) 2 MA u (Ma:1 MA = ( ll/JL.) #
. MA = .ji/.A
- 4. ENVIROSwNTAt> AT30WAMCE (r.A) (from Forms S, 6 & 7) 4A. Norm 7 Cmdiiu (EA.)
EA. = TE, + HE, + PE,
.m_-. g.; ,
. EA., = 0.0004 V 8 -+ WA., -+ N/A . - - -- ..--
Ae 0.0004 V' 7CE 26-426 REV 0 Ese (REFERENOE SOGXXIV 7.15) DLd C782-[8k-[$8[M 2 XIM $2dMM 953 M M
t l NES&L DEPARTMEMT ICCN NO/ ! ""'" CC" " -
"^ "^ C '5 CALCULATION SHEET CCN CONVERSION:
Project or DCP i FCN N/A Cais No. J-SBAE CCN h;O CCN- ! Subject DN&tPOtoG POWE1:t *Rtp BYPASS $hert No. of _ REV1 ORIGINATOR DATE IRE DATE REV ORIGINATOR DATE tRE CAT 8E "o 0 0.McQuade 03-1453 E. Qu;fm CMbio g D EjE FORM 11 SHEET 2: CALCUIATION
SUMMARY
- 5. CALTERATION ALIMWANCE (CA) (frCC FoIM 8) 5A. Squared calibration allowances for an increasing setpoint,
,?' CA., a AA + TS g CA, m 0.0026 V a j SB. Squared calibration s11owancec for a decreasing setpoint, CA. = AA + ST. CAe s 0.00313 p ,, _
- 6. PPS PARTNET SIGNAL CALTBPA"' ION UNCERTA*1 TTY I
CUA = Squared log power icvel signal processing uncertainty (Reference 6.S; Calibration Error: RSS (A, B, C ,D) = +/-0.345} (See section 4.10) l CaA . O mv
)
7 DRTM ALLOWANCE (DA) (from Form 9} DA = Squared drifC allowances from Form 9 DA = 0 0025 V'
- 8. pCWER SUPPLY ALLOWMtCE (PSA) (from Form 8) i PSA s Squared power supply 2,11owances from Form B
' O PSA s. JCE 26-426 REV O B/94 (REFERENCE soc 3-XXN-7.15) i D $f
- KL M QM-29R-$[f$:XEd $NRdjftj 93 ggj]"OflN
NESOL DEDARTMENT ICCN NOJ N-1 3-CALCULATION SHEET PRELN. CCN NO. PAGE 46_ % CCN CCNVERSION: Pmeet or DCP / FCN . N/A Calc No. J.S BA 473
)
CCN NC. CCN- i S41 tWBtD0 FLOC POWEA TR!P BYPASS Sheet No. of REV ORIGINATOR DATE tRE DATE REV ORIGINATOR DATE DATE 4RE 5 0 Q.McQuade 0119-93 E. Qwnn 031kS3 boE
-P i 6, FORM 11, SHEET 3: CALCUIATION
SUMMARY
3, cTT<c TTT 'RarAnn A?.?nWANCE (La) (from Form 10) ,I 1 La m Ci + Ti + Pi + Si + Di j La n/a + w/A . n/A . n/a + ,,,,gl,p_ La m N/A
- 10. -oTAL Loop t?NcrRTATnry (TLUa) for Normal Environment Conditions TLU is the total loop uncertainty for the DNB/LPD/ Log Power Trip Bypass NOTE: IN DETERMINING TLUs, IME CALIBRATICN ALIDWANCE FOR THE DECREASING SETPOI!rf (CA ) IS USED BECAUSE IT IS CCNSERVATIVE AND ELItCNATES THE NEED TO CALCUIATE A SEPARATE TLU FOR THE INCREASING AND DECREASING SETPOINTS, THUS SIMPLIFYING THE CALCULATICN.
#2
- A' EA + CA. + PA + DA
+ CUA l i
_ TLU = tv g_coe4 e_co,3, n_13e o_ cogs. , g,,,;,1,g l M 8
" *# o.23E03 l TLU = 2 0 485 V l
t NOTE: ANY TERES, OR PORTIONS OF TERMS, UNDER THE RADICAL WHICH AE2 I' BIASES SHOULD BE MOVED FROM UNDER THE RADICAL AND ADDED TO THE TOTAL LOCP l UNCERTAINTi. ?- . - - - - i sCE 26 426 REV O t/94 (REFERENCE S012SXMJ 7.15) ) -_ t I 29 'd 61:II 66, II uer S2S2-89E-6P6:xeJ SdI6d?J 933 8037DnN
4 NES&L DEPARTMENT 1CCN NOJ j3 CALCULATION SHEET PRELIM. CCN NO. PAGE 47 of h , Project of DCP / FCN N/A Calc No. J4EA 023 CCN CONVERS:CN. [ CON NO. CCN-6 subjw: eNatwortoc POWER Tw SYpASS Simt No. of REV ORIGINATOR DATE tRE DATE REV ORIGINATOR DATE IRE I DATE E o D.ueounde osins E. un os.1s.m h blQ FORM 11. SHEET 4: CALCULATION
SUMMARY
- 11. TRIP EETPOINT 11.A . FOR INCREASING SETPCINT:
E- T S ,; a 1E-tv Log Power, or TS,, = 8 + Log (%PWR/2)
- TS,s S + Log (IE-4%/2)
TS,i = 3.699 V llB. FOR DECREASING (RESET) SETPOINT: Note: The decreasing scepcint is the reset of the increasing setpcint, and is based on'the fixed hysteresis of the bistable. TS p a = 7.944E-5% Log Power, or TS,. = 8 + Log (%PWR/2 )
- ~ - TS,. . e 8 + Log (7.944E-5%/2) _
TS,e s 3.599 V
- 12. KARGIN 12A. MARGIN FOR INCREASING SETPOINT: l Margin is calculated to be the difference between the Upper Operational Limit and the Trip Serpoint TLU .
MARGIN, = UOL - TS, - TLU c.4as v _ l '^ MARGINS = 4 112 V - 3 699 V - MARGIN; e 0 1?P V ACE 2f-426 REV 0 894 (REFERENCE SC123.XXN 7.15)
' 87 'd 6I:II-
- 66. II uer S252-892-606:XP.:1 S8Ibidd 933 bO373fN - _ -
w . . . - . .. ... NES&L DEPARTMENT LCCN NO/
"d y ';
CALCULATION SHEET PRELIM. CCN NO. PAGE 48 WW CCN CONVERSION: / Project or DOP i FCN ' N/A cale No. J-SBA4/3 CCN NO. CCN- ! Subsect DNEUUFtMOC, POWE1t TRS gypASS Sheet No, _ of REV ORIGINATOR DATE IRE DATE REV OR:G:NATOR CATE 4RE DATE E o D. h a- c>tsa2 E. Qinm 03 1493 d aa s {u FORM 11, SHEET 5: CALCUIATION
SUMMARY
l 125. MARGIN FOR DECREASING SETPOINT: l Margin is calculated to be the difference between the Lower Analytical Limit and the Trip Setpoint TLD minus hysteresis. Note: BH denotes Bistable Hysteresis for Bistable Reset (from Form 3). l , MARGIN. = TS, - BH - TLU2 - LAL MARGIN,a _?.C99 V - 0 100 V - O_4AS V - 7.469 V l MARGIN. m 0 24c V l l-12C. MARGIN TO-LOG POWER TRIP (High Log Powcr Trip Setpoint, Ref. 6.8) i Margin is calculated to be the difference between the High Los Power Trip Setpoint gTLUS and the Upper Operational Limit. MARGIN t , = (Log Power TS, - TLU ) - UOL 3 MARGINg, m ( 7.622 V - 0 *J 7 9 V ) - 4.312 VI l MARGIN., . a S 912 V
- 13. AL* 0W3Tr VALtr2 i 65 Surveillance or Calibration Procedure Reference :
Note: Values for DA a.nd ST must be relative to the ref erenced { l procedures. l 13A. FOR INCREASING SETPOINI: _ _ _.- ~ AVr = - TS . r + ^ - - - - - . -
+ MARGIN j -
DA + STg
-~~ ~ --,, ..
l avg a 3.599 v + F 0.0025 vr+ _0_0001 V' + 0 12 g _y Avg a 3_979 v or i _ E 1 Tr - 4 fc Pewer Avg = 1 P7s v er 1. 5 E - 4 *< Power rounded denm l l 3CE 292s REv o w @EFERENCE sow XXM-U5) ! 6Td 61:11 66. II uer S2S2-892-6P6:xed S8Ibidd 938 863 00N
i l I i NES&L DEPARTMENT ICCN NQ/ } CALCULATION SHEET PRELIM. CCN NO. PACE 49 __. } CCN CONVERSION: Project or DCP / FCN . ,N/A Calc No J.SBA-023 CCN NO. CCN. [ l
' Sutject DNatro/ Loc Powem TRso svpass SNxt No. of l REVl CRIGINATOR DATE IRE DATE REV ORIGINATOR DATE IRE CATE y i c o.Mccued. mises E. Quinn c3 ts-e3 ,. g Eja I
FORM 11, SKEET 6: CALCULATION
SUMMARY
13B. FOR DECREASING SETPOIlfr: AV. n TS, - BH - V DA'+ ST. - MARGIN AV. e ?.C99 v - 0.1 V - V , 0.0025 Vi+ 0.000E29 Y - 0 24m V { l Av. . ? 29s v er 3 .
- 72r - st powe r Av. = _3 301 V cr 4E-54 Power _ rounded up l i
i
\
i I l 1 1 1 l i o, b m ., 1
,CE 26426 REV o t/94 (REFERENCE S0123 XXN-7.15) 05 'd 03:II 66. II cer S252-892-636:XP3 SdId330 933 ad31]nN
- .. . . _ _ _ _ . _ . . . . . . . . . ... . . _ _ . . . . _ _ . = _ . . _ . . ___
ACCN NO/ 2 NES&L DEPARTMENT N-1 PRELIM.CCh NO. PAGE S0 of CALCULATION SHEET CCN CONVERSION: y l Pryect or DCP / FCN N/A Cape No. J-SBA@ CON NO. CCN- / Sheet No. of Subs.c 0844.70103 POWER Tae sv> Ass REV ORIGINATOR DATE IRE DATE I REV ORIGINATOR DATE l 1RE i DATE' 5 E 9 D.Maouses 03-1s.83 L Quina 03 19-s2 ,. g Ij is Staplified Stock Diagram
-- FIGURE 1
- L 4
NI LOG CHANNEL l i NI LCQ CMANNEL
. ---)
COUNT !
- I
! MATE i
'i PPsw LcG
' PWRTRP LOG j Lp3 gggjg, l muup -
8/S
- $UMMER
-. CAMP '00 8# "88 CETECTOR i i
0 i ASSEwSLY f 1CE-4% i l l l l_ l s i i_ _ 1 l.
- . . . . . . _ . . . ._m, . , , , , , , . , . _ , , . , , _ . , , , , . _ _ , .._. _ , , , _ ,_ _. ,
I , - ) l i !- ;CE 26426 REV O &S4 (stEFERENCE $O123 XXN 7.15) i j i ! l l TS *d 02:IT 66. II ver SLG2-892-606:xed SWI6336 938 80313nN j
j 5 / of 5's C.C M / J-SBA-023 l hI ' Attachment A Pagel/2 j
- l 1
s DDCENCIONI.ESS
'# DNBR AND LPD PENALTY FACIOR II.AST l SIGNIFicA!c BITS FOR SCALE TIFES. O AND 1-DLSB(1-2) 1 2 329 0.0078125 0.0625
? tSB(1-2 ) 1 2 331 0.03125 0.25 '
t
- SECOND RPC PLAG TIMER SKIPOINT IN CPC )
(ADDRESSAB M CONSTANI) TCBSP 1 1 333 0.0
- SECOND CPCB EXECUTION TDOL DTB- 1 1 334 0.1 DELAY TIME IN CatiPARING BOTE CEACS : SECOND FOR RFCS TSOTH 1 1 335 0.5
- FERCENT POWER PUHF DEPENDENT FILTER C0FEFICIElfIS FOR / DECREE F DYN/MIC THERMAL POWER CALCULATION 0.0 0.0 0.0 0.0 APD(1-6) 1 6 382 0.0 0.0 0.0 3 388 0.0 0.0 APD(7-9) 1
- Cot 1NIS I SIGNAL 3IAS FACTOR "
OFFSTTC 1 1 397 200.0 ' OFFSTIB 1 1 398 200.0 g' OFFSTF1 1 1 399 0.0 ' W OFFSTD '1 1 400 0.0 , MODUM 2- -
- DIMENSIONLESS
- COLD LEG TDiPERATUILE FILTEL COEFFICIEtGS A2F,A17 1 2 410 -3.1567 -3.1867 * - -
A3F, A2S 1 2 41'2 0.9700 -0.3924
-A15,A35 1 2 414 0.4350 0.9574
- IEG F**-1 TDEERATURE SHADOWING FACIOR COEFFICIENTS C1,C2 1 1 416 0.0015 0.0080
- DEGREE F ERROR ON MAXIMtti COLD-LEG TEMPERATURE TCERiL 1 1 418 0.0 ,
- DEGREE F ERROE ON MINIMIM COLD-GG TEMPERATURE TOER .
1 1 419 0.0 _ , 1 NEUIRON FLUI-TO-IEEBliAL POWEK CALIB C0hSTA
- DDENSIONLESS (ADDRESSABLE CONSTANI)
KCAL 1 1 420 1.0 DEGREE F TEMyERATURE SHADOWING REFERENCE TEMPERTURE : (ADDRESSABLE CONSTANT) TCREF 1 1 421 S57.0 L: ;v,,.,,
.T YACE l' REVISION 00-P CE NPSD-337-P
+ 2G 'd 02:II 66. II uPf S252-892-606:XPJ Salbiid 933 3031]nN
-e-o ..e SD ors 3' '
s. 6CH J-SBA-023 PCCN AM , Attacee A raEe 2n j i MODUm 4 . . - - - PART LENGIH ROD ACTIVE LENGTH : PERCE}TI 0F COE HEIGHT
. PLROD 1 1 900 50.0 I NUM3ER OF COLUMNS IN THE FCS AND FFK TABES: DDiENSIONLESS NCOL 1 1 901 3.0 NUMBER OF CEA REGUIATING GLOUPS
- DDd.ENSIONESS ' l I
NREG 1 1 902 6. . CONSTANI TO DEFINE PART ION OF TEE : DDiESSIONLESS I FCS AND FPR TABES 4
. ICOL 1 1 903 2.
- DDCENSIONLESS MULTI? LIERS FOR THE FPR PLANAE EADIALS TABC (ADDRESSABLE CONSTANI) 5 905 1.0 1.0 1.0 1.0 1.0 ARM 1-ARM S 1.
- DIMENSIONLESS l'.ULTIPLIEES FOR THE FCS SBADOWING FACTORS TABE '( ADDRESSABLE CONSTA!C )
As2-Am 5 1 4 912 1.0 1.0 1.0 1.0
- DIMENSIONE SS CEA SHAD 0VING PACTORS UNRODDED - PL1 OE PL2 - SHUTDOWN 5.I UNRODDED
- RIG.6
- REG.6+5
- EEG. 6 +S M
- REG.6+54 +3 ~*
REG . 6 +54 +3 +2
- REG.6+54 +3+2+1
- FCS(1- 3) 1 3 918 1.00 1.05 1.00 3 921 1.075 1.135 1.00 (4- 6) 1 1.00 (7- 9) 1 3 924 1.00 1.00 3 U7 1.00 1.00 1.00 (10-12') 1 1.00 (13-15 ) 1 3 930 1.00 1.00 3 933 1.00 1.00 1.00 (16-18) 1 1.00 (19-21) 1 3 936 1.00 1.00 ,
4
,e vs.n ~nm es -mmn h.s .
PAGE 24 CE NPSD-33/-P REVISION 00rP fS 'd 0{:II 66. II uPT S2S2-892-6F6:XPJ $3I0ii8 938 30313nN
$cyj./ J-SSA 3
[84} From: DICK BOCKHORST 3/18/93 1:05PM (852 bytes: 13 in) M Atl1M6hY 8 Ie Io: JOHN W O'BRIEN > -
Subject:
Critical'.y point >
. (, ............................... F o rwarde d - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - l Fiun: MIKE MCDEVITT at AWS3 3/18/93 10:48AM (704 bytes: 13 in)
To: DICK BOCKHORST at MESA ., cc: - DAVID 'JJ4ENDICK, MIKE MCDEVITT
Subject:
Criticality point
- . . . . .. . . . . . . . . . . . . . . . . . . - - - - - - - - Me s s ag e Cont e nt s - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
j Dick, In response to your question regarding the point where we go critical, the answer is that we typically go critical no higher than 1 x 10-5 t i . power. There are variables which cause this to change from one
.) startup to the ne.xt, but as a rule we do not expect criticality 2 comming above 1x10-5 percent power.
- I have confirmed this with Dave Ramendick. - Mike Mcdevitt t t i I i i 1 i i i
)
i i ([ , d PS 'd 12:II_ 66.II"4 SLSI-892-676:W3 S8I6d3S 938 BOTOnN j}}