ML20086E656
| ML20086E656 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 10/31/1991 |
| From: | Charnley J, Noble L WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20086E648 | List: |
| References | |
| 23A7128, 23A7128-R, 23A7128-R00, NUDOCS 9112020234 | |
| Download: ML20086E656 (22) | |
Text
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1 ENCLOSURO-2 BRUNSWICK STEAM ELECTRIC PIANT, UNIT 2 NRC DOCKET NO. 50 324 OPERATING LICENSE NO. DPR-62 SUPPLEMENTAL RELOAD LICENSING REPORT
'FOR BRUNSWICK STEAM ELECTRIC PIANT UNIT 2 23A7128, REVISION 0
'911202G234 911121 PDR ADOCK 05000324 PDR.
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GE Nuclear Energy 23A7128
!?S Cartner arere ggy,j Sa,.ja a cA 251:5 g g g October 1991 23A7128, Rev. 0 Supplemental lleload Licensing Itepart for llrunswick Steam Electric 151 ant Unh 2 lleload 9 Cycle 10 0
Approved
.N Apprmed S..harnley, lanager I. D. Noble, Manager Fuel Licensing lleload Nuclear Engineering
IlrunSwick 2 -
mn:s Reload 9 en o important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by General Electric Company (GE) solely for Carolina Power and Light Company (CP&L) for CP&L's use in defining operating limits for the Brunswick Steam Electric Plant Unit 2 The information contained in this report is believed by GE to be an accurate and true representation of the facts known or obtained by or provided to GE at the time this report was prepared.
The only undertakings of GE respecting information in this document are contained in the contract between CP&L and GE for nuclear fuel and related services for Brunswick Steam Electric Plant Unit 2 and nothing contained in this document shall be construed as changing said contract.
The use of this information except as defined by said contract, or for any purpose other than tnat for which it is intended. is not authorized; and with respect to any such unauthorized use, neither GE nor any of the contributors to this document makes any representation or warranty (expressed or implied) as to the completeness, accuracy or usefulness of the information contained in this document or that such use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any kind which may result from such use of such information.
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f
- Ilrunswick 2 aces Helnad e n n-n Acknowledgment The engineering and reload licensing analyses which form the technical basis of this Supple-mental Reload Licensing Report were performed by R. N. Anderson of Fuel Engineering. The Supplemental Reload Licensing Report was prepared by P. A. Lambert and verified by J. L. Rash of Fuel Licensing.
m Page 3
f Ilrtinswick 2 nous Reinnd 9 nn n The basis for this report is General Electric Standard Application for Reactor Fuel, NEDE 240ll P-A-10, February 1991; and the U.S. Supplement, NEDE-24011 P-A 10 US, hiarch 1991.
1.
Plant unique items
- Appendix A:
Analyses Values Appendix B:
N1ain Steamline Isolation Valve Out of Service Appendix C:
Reload Unique Anticipated Operational Occurrence ( AOO) Analysis input Appendix D:
Use of New Safety Limit htCPR for Cycle 10 Appendix E:
Feedwater Controller Failure Analysis Appendix F:
Staximum Extended operating Domain 2.
Reload Fuel Bundles Fuel Trot.
Cvele Immicd Etimber Irradiated:
BPSDRB299 (BPSx8R) 0 12 BP8DRB299 (BP8x8R) 7 48 GESB P8DQB323-1IGZ-80Ni 4WR 150-T(BD323A) (GE8x8EB) 8 92 GESB-PSDOB317-90Z-SOM-4WR-150-T (BD317A) (GE8x8EB) 8 92 GE9B-P8DWB330-11GZ 80N1-150 T (NBD330A)(GE8x8NB) 9 44 GE9B P8DWB329-ilGZ-80ht 150-T (NBD329A)(GE8x8NB) 9 124 New:
GElo-P8HXB329-12GZl 100M 150-T (GE8xSNB 3) 10 H3 Total 560 3.
Reference Core Londing Pattern N1Wd/ST hlWd/MT Nominal previous cycle core average exposure at end of cycle:
21,313 23,494 s
Minimum previous cycle core average exposure at end of cycle from cold shutdown considerations:
20,876 23,012 Assumed reload cycle core average exposure at beginning of cycle:
13,347 14,713 Assumed reload cycle core average exposure at end of cycle:
23,077 25,438 Core loading pattern:
Figure 1 Page 4
l fllllSMick 2 neus Reload 9 un c.
4.
Cgeulated Core EITective.\\lultiplication and Control System Morth No Voids, 20 C Beginning of Cycle, K, Uncontrolled 1.106 Fully controlled 0.962 Strongest control rod out 0.987 R, Maximum increase in cold core reactivity with exposure into cycle. AK 0,000 Standby Liquid Control System Shutdown Capability Boron Shutdown Margin (AK)
(p_cm)
(20*C. Xenon Free) 600 0.033 6.
Reload Unique GETAB Anticipated Operational Occurrence (AOO) Analysis initial Condition Parameters -
Fuel Peakinc Factoti._
Bundle Power Bundle Flow Initial Design local Radial A11al R Factor 61Wt)
(1.000 lb/hr)
MCPR Exposure. BOC10 to EOC10 2205 mwd /MT GE8x8NB 3 1.20 1.67 1.40 1.000 7.074 112.9 1.25 GE8xSNB 1.20 1.66 1.40-1.000 7.061 112.6 1.25 GE8x8EB 1.20 1.57 1.40 1.051 6.642 119.6 1.25 BP8x8R 1.20 1,56 1.40 1.051 6.622 117.9 1.25 Exposure: EOC10 2205 mwd /MT to EOC10 GE8x8NB-3 1.20 1.61 1.40 1.000 6.822 114.3 1.30 GE8x8NB 1.20 1.60 1.40 1.000 6.810 114.0 1.30 GE8x8EB 1.20 1.51 1.40 1.051 6.405 120.9 1.30 BP8x8R 1.20 1.50 1.40 1.051 6.382 119.3 1.30 Exposure: BOC10 to EOC10 with main steam isolation valve out of service (MSIVOOS)
GE8x8NB-3 1.20 1.61 1.40 1.000 6.844 114.2 1.30 GESx8NB 1.20 1.61 1.40 1.000 6.834 113.9 1.30 GE8x8EB 1.20 1.51 1.40 1.051 6.404 120.9 1.30 BP8x8R 1.20 1.50 1.40 1.051 6.392 119.2 1.30 Page5
~
ll'runswick 2 -
acus Ranad 9 nn a 7.
Selected Margin improsement Options Recirculation pump trip:
No Rod withdrawallimiter:
No Thermal power monitor:
Yes
- Improved scram time:
No Exposure dependent limits:
Yes Exposure points analyzed:
2 (EOC10 2205 N1Wd/h1T and EOC10) 8.
Operating Flexibility Options Single loop operation:
Yes Load line limit:
Yes Extended load line limit:
Yes
~ Ntaximum extended load line limit:
Yes Incteased core flow at end of cycle:
Yes Increased core flow throughout the cycle:
Yes Flow point analyzed:
105cc Feedwater temperature reduction throughout the cycle:
No Final feedwater temperature reduction:
No Temperature reduction:
N/A ARTS Program:
Yes N1aximum extended operating domain:
Yes*
Niain steam isolation valve out of service:
Yes" l
l l
- See Appendix F.
"See Appendix B.
Page 6
.~
llrunswick 2 nas Reload 9 Rev 0 9.
Core wide AOO Ana.ysis Results Methods used: GEMl"1 and GEXL-PLUS Uncorrected 6CPR Flux Q/A Event
('"e NilR)('"r NHR)
GE8x8NIh1 GE8x8 Nil [iE8x8 Elllf8N8R Ogutt Exposure range: 110C10 to EOC10 Inadvertent 123 119 0.15 0.15 0.14 0.15 2 activation of HPCI Exposure ran2e: 110C10 to EOClo-2205 mwd /MT Load rejection 365 121 0.18 0.18 0.18 0.18 3 without bypass Exposure range: EOC10-2205 mwd /MT to EOC10 Load rejection 429 125 0.24 0.24 0.23 0.23 4 without bypass Exposure range: 110C10 to EOC10 with MSIVOOS Load rejection 396 125 0.23 0.23 0.23 0.22 5 without bypass For cold water injection event inputs, see Appendix C; for feedwater controller failure analysis, see Appendix E.
- 10. Local Rod Withdrawal Error (With Limiting Instrument Failure) AOO Summary The rod withdrawal error event in the maximum extended operating domain was originally analyzed in General Electric BWR Licensing Report, Maximum & tended Operating Domain Analysis for Brunswick Steam Electric Plant, NEDC 31654P, dated February 1989. The MCPR limit for rod withdrawal error is bounded by the operating limit MCPRs presented in Section 11 of this report for RBM setpoints shown in Tables 10 5(a) or 10 5(b) of NEDC 31654P.
Page 7
INunswick 2 noin Hrload 9 nn n
- 11. Cycle MCPR Values Safety limit: 1.07 Single loop operation safety limit: 1.08'
'Non-prx5kittlZ.alintt events Exposure range: 110C10 to EOC10 GE8sSNil 3 Of8sRNil GE8s8 Ell llP8sHR Fuelloading errot 1.25 Inadvertent activation of IIPCI 1.22 1.22 1.21 1.22 Pressurizatim1 din 11 Ontion A Option Il GENS 8 Nil-3 GE8s8 Nil GE8s8 Ell IllysMR Gfj@'Is-3 GE8sMNil Gl% 8 Ell.lilms8R Exposure range: ilOC10 to EOC10 2205 51Wd/51T Load rejection 1.35 1.35 1.35 1.35 1.28 1.28 1.28 1.28 without bypass Exposure range: EOC10-2205 hlWd/ SIT to EOC10 Load rejection 1.36 1.36 1.36 1.36 1.32 1.32 1.32 1.32 without bypass Exposure range: 110C10 to EOC10 with AISIVOOS" Load rejection 1.36 1.36 1.35 1.35 1.32 1.32 1.31 1.31 without bypass
- 12. Overpressurization Asialysis Summnry l
i Psi Pv i Event (psic) {psig) Plant Response t htSIV closure 1253 1287 Figure 6 (flux scram) l ' Brunswick Steam Electric Plant Units 1 and 2 Single Loop Operation, NEDC 31776P, December 1989, Operating limit AICPR for two loop operation (TLO) bounds the operating limit ofCPRforsingle loop operation (SLO): DCPR(SLO) <(DCPR(TLO).01), therefore, operating limit AlCPR need not be changedfor SLO. "See discussion in Appendix B. PageH
llrunswick 2 m es Reload 9 Rn "
- 13. Loading Error Results Variable water gap misoriented bundle analysis: Yes Event ACPR
, Nii> oriented fuel bundle 0.18'
- 14. Control Rod Drop Analysis Results Brunswick Steam Electric Plant Unit 2 is a group notch plant operating in the banked positien withdrawal sequence; therefore, the control rod drop accident analysis is not required. NRC approvaiis do.umented in NEDE 240ll P A 10.US, Starch 1991,
- 15. Stability Analysis Results GE SIL-380 recommendations and GE interim corrective actions have been included in the Brunswick Steam Electric Plant Unit 2 operating procedures. Regions of restricted operation defined in Attachment I to NRC Bulletin No. 88 07 Supplement I are applicable to Brunswick 2 Reload 9 Cycle 10.
- 16. Loss of coolant Accident Results LOCA method used: SAFER /GESTR-LOCA
Reference:
Brunswick Steam Electric Piant Units 1 and 2 SAFER /GESTR LOCA Loss of Coolant Accident Analysis, NEDC-31624P Rev. 2, July 1990. The GE8x8EB LOCA analysis results presented in Sections S and 6 of NEDC 31624P conservatively bound the LOCA analysis of the GE8x8NB-3 fuel types. This analysis yielded ' a licensing basis peak clad temperature of 1537'F, a peak local oxidation fraction of <0.31c,c and a core wide metal-water reaction of 0.036cc. The most limiting and the least limiting hiAPLHORs for the GE8x8NB 3 fuel design are as follows:
- ACPR penalty of 0.02 for the tilted misoriented bundle has been applied.
Page9 l l
Ilrunswick 2 n n:s hisd 9 un a 16. Loss of coolant Accident Results (continued) ilundle Ty pe: GE10 P8tiXil32912GZl.100.NI 150 T (GESsSNil 3) Average Planar Exnosure \\1 API 11G R (kwitt i ! GWd /ST) (GWd / NIT) Niost 1.imiting I east Limiting 0.00 0.00 10.52 11.37 0.20 0.20 10 57 l 1.44 1.00 1.10 10.70 11.56 2.00 2.20 10.92 11.70 3.00 3.30 11.17 11.86 4.00 4.40 11.35 12.02 5.00 5.51 11.53 12.IS 6.00 6.61 11.71 12.35 7.00 7.72 11.90 12.53 S.00 8.82 12.12 12.75 9.00 9.92 12.37 12.99 10.00 11.02 12.63 13.20 12.50 13.78 12.32 13.14 15.00 16.53 12.65 12.81 20.00 22.05 12.13 12.15 25.00 27.56 11.47 11.63 35.00 38.58 10.20 10.40 45.00 49.60 S 63 9.05 50.50 55.67 5.90 6.25 50.54 55.71 6.23 50.93 56.14 6.03 51.06 56.28 5.97 Page 10
-Brunswick 2 .m-Reload 9 a TJTJT8C8@E 52 2 50 IDE @E E 8 60 2 0 46 ES ELw EJ ELO 85 BJ @J @IJ '46 E@8@C@sCe@G808C@GEmO @B DJ E@ @iD ED DB @B Dx@ @To sc @r G @tD 44 se@sfs@>o@s@wesome e 42 8 @ S C Sn 8 @ GJ E @ @J @ 1 A w2 e @c @s @'@ @s ce @+E @To es @J CJ @J 40 @e se@@se 3e 36-ELO 8x0 @tw @ DJ @ DJ O @ J @ J @ @ ELE 34-@s @s cr @s @c Qs em e @ ce ss er 8s ts 32-0 0 OJ E@ E0 8 @ EO EJ O EE 0J @G 03 EG A 1 30-0E cs @Ts Fe es c7 es e c ETO esFC em Fe 0 25-DE 5E- @@m @er@ D8@ @es @s @s @f Y @S @J 26-Fe s Q c e @c@8@s@ers 24-CE DE @E ODE DJ 0 00 00 0 5 0 Em E@ EQ 8 0 22-C C 70 b@IC QC 8 C Es D @ @4 Y@ Y8 68 68 Y 4 t 4 8C 20-EQ @E DE DE @C QE @G E@ DG E0 DE 500 D@ 18-60 8 @ f@ f@ O O 60 ff06@ ETO 68 FC 78 0 8 7 T 7 16 8@E@EE@@GOEE@EDE00EEQQEE -14 ' ET@ TD T@ ET@ fw Te ETS FE @Te D 5 TD T E E @J Cn3 @p@ @J @4@ 8 @ CJ E Q 8 G E T 12 @T@@@EC@ EG@@@s@@@Y @1C 78 4 t3 10 @@f @DDJ DJ@TE ce @s we esEEJEx@@JDJ e cmemseerE 6 l E0@@JOJE@@g8' 4 1 1 ' Os EC DE D'E @ 0 2 l l l l 11IIIIi 1 3 5 7 9111315171921232527293133353739414345474951 FUEL TYPE l A = GE8B-P8008323-llGZ-80M-4WR-150-T E = BP80RB299 (Cycle 7) B --GE10-P8HXB329-12GZl-100M-150 T F = GE98-P80WB330 IlGZ-80M-150-T C = GEBB-P8DQB317-9GZ-80M-4WR-150-T G = GE9B-P80WB329-llGZ-80M 150-T D = BP80RB299 (Cycle 6) l Figure 1 Core Loading Pattern Page il
_ - ~ - _ _ NrtJflSMICN 2
- i e ;.
Reload 9 e-i i k .i [ f 't tes r u I 4, Stara <af ;rm
- yy sg port oS I al,C; e g'og' rP
/ , N h $' f + (LM l
- S 4
s'i> 'A <I 7 3. .w e 's e 'o- .g i / [ _. _ i h,... i g ~l E. }~ l ,l 4- ..i. tid (5tcacs) tid (r:ses) I ES$lt(ic.orr.sg o.5xRT) [YEL iy 0 orActivity 1 sty &dj0w t4
- j Ril Fuet j E 5' jCitv41Y
.mn -? { -#1 ~ ~, x ..a h m E = U... m.. / -8 '.. Ild (E0305) fld (203CS) L: Figure 2 Plant Response to inadvertent Activation of HPCI (BOC10 to EOC10) Page 12 3 ,,-,..n...
ilrunswick 2 Beinad 9 ., e :s a., Y Or I cx,~a$ I* It
- s i cc [,
.I,f(3,P5') at rm , rta ac. se i.;,r.g-wa I m.,- Ykn 5 s, i N, N / 4 \\ u,i ( . e. me: - c.
- q.
tic <xcocs) enc <xcue) 3,,pMt (INCN-Air-SCP-SART) / t / 3pc.m%pvifva @.m.," 1 v010 ACAC .3 jy0% 5 u 1 1- +t f i /, '=a m. ..a j J a = e LJ ..I ?;2: E.... - = =.. t. -a s. 2. Tiw (ucaos) tiw (ucacs) Figure 3 Plant Response to Generator lead Rejection Without Bypass (BOC10 to EOC10 2205 mwd /MT) Page 13
B Brunswick 2 .n ma, i ,.ef.:,, m ,.E_
- gaf();..-s.,,.s,'
i ' a.E SJral -{at rwx va3( c, l 3 C7E <NLEf} rLOW 3 lEp;(r. g p;. va i 1 5...d~ A N N i N / x s 3 [ \\
- l 1
4 4W 1. -i;
- d.
3. Tid (WC;POS) fit (ECMA) 1L Da"MF-SEP-SKR T ) ivoi0 Activi ty 1%diW iW}Gl!!!" o ( \\} / = i. / l J /_ I V = . i+,1: =x + i.. s. t. i. f ed (ECDOS) Tit (200c5) Figure 4 Plant Response to Generator Load Rejection Without Bypass (EOC10 2205 mwd /MT to EOC10) l 1 Page 14 l
lirunswick 2
- n :,-
-c.-- Erjaad 9 ' a-4 -t i 14 tow ru ,.q .m . er.3 3 g,g:p,,43 1,lf; l l 1 4 e I - 1' : E,N E,r.447 r ;x S srag. e i ga l y.44., r.. i ,,l l l i e W y m. I s 7-E N 1 :. a. h x 4 m ss. a. ex. - - - - - .c v tiw <x:mes) > >w <x:xs> IL I<N . SED.5KRT) ~ ivity 2S Sir ow 2 Otivity t 3t rgf Lov g 3 ivi y-t er is 1 _ +& n ni v V I f l ...a ) Dm / { -- -s s \\ b U.. .f k .=%,. is. t. -riw cuc>esi t>< <x:oes Figure 5-Plant Response to Generator Load Rejection Without Bypass with MSIVOOS (BOC10 to EOC10) Page13 -... ~.,
= ~ ' ltrunswick 2 c Helnad 9 uc .v i w=xrwx { 5a/;;,e. =cs3 erM:ps: i,te } j :a*E $#Fsit {AT FLUt , FL .ec.q. q 4(i i t J
- gh, wt u t rt
- v
.w, I \\ ptp ,f- -4s h.=.J \\g [ s 3 ,\\\\ y s e E N / .) i 1 I i f., ,i m,,_. o%. e x,. i. 714 (Cws) t:d (20c45) 1 LEvil
- /0iD DE4'TIviTv 2 vtssa(likH-#EF.5EP.SxRT)
A
- OC i
/ j f } m;# R E4 P PCilviTV l so(ip1 ~w)LCW ow 3 TURgif r R 4 FFA tiVifY S a ef te m _a irrr s .y.u = 2 > =. g' ..u 2 % k j ,e h / i .$ h... n%. s. tis (ucoes) tid (scoes) Figure 6 Plant Response to MSIV Closure, Flux Scram Pagein . _. ~.
Ilrunswick 2 nven Heload 9 un n Appendix A Analyses Values
- To reflect actual plant parameters accurately, the values shown in Table A 1 were used this cycle.
Table A 1 Parameter Analysis Values Thermal power, MWt 2436 Dome pressure, psig 1005 Steam flow,- Mlb/hr 10.47 Turbine pressure, psig 950 Core flow, Mlb/hr 80.85' Reactor pressure, psia 1036 Inlet enthalpy, Btu /lb 523 Nr. fuel power fraction 0.038 Number of S/RVs" 9 Lowest setpoint, psig i116 Recire pump power source On site"* Turbine control valves Full arc""
- At increased (105?c) core flow.
" Cycle 10 analyses performed assuming 2 S/RVs out of service except for the MSIVOOS analysis.
- " Bounds operation _with off site power source for reload licensing events for Cycle 10.
"" Bounds operation with partial are turbine control valves and results in generator load rejection without bypass bounding the turbine trip without bypass event. Page 17
Ilrunswick 2 m,us Reinad 9 pn n Appendix 11 Main Steamline Isolation Valve Out of Service . Reference B 1 provided a basis for operation of Brunswick Steam Electric Plant (BSEP) with one hiain Steamline Isolation Valve Out of Service (hislVOOS)(three steamline operation) and all S/RVs in service. For this mode of operation in BSEP Unit 2 throughout Cycle 10, the EOC10 2205 htWd/h1T to EOC10 StCPR limits presenter;in Section 11 of the body of this report are bounding and should be applied when operating in the htSIVOOS mode at any time during the cycle. The peak steam line and peak vessel pressures for the limiting overpressurization event (htSIV closure with flux scram) in the A1SIVOOS mode are 1219 psig and 1260 psig, respectively. Reference B-l. Main Steamline. Isolation Valve Out of Service for Brunswick Steam Electric Plant, EAS Il7-0987, GE Nuclear Energy April 1988. l l l i Page 18
' lirunswick 2 uuna lldnad 9 Rev 0 Appendix C Reload Unique Anticipated Operational Occurrence (AOO) Analysis Input (Cold water injection events only) 110C10 Void fraction, Tc 52.39 Average fuel temperature,
- F 1095 Void coefficient N/A*, t/rc Rg
-9.80/-12.25 Doppler coefficient N/A*, /*F 0.204/ 0.194 Scram worth N/A*, $ EOC10 Void fraction, Oc 46.08 Average fuel temperature, 'F 1095 Void coefficient N/A*, /rc Rg 9.37/ 11.71 Doppler coefficient N/A*, //
- F
-0.240/-0.228 Scram worth N/A*, S
- N = Nuclear input data; A = Used in transient analysis.
" Generic ext asure independent values are used in General Electric Stamfard Application for Reactor Fuel, NEDE-240ll-P-A-10, February 1991. Page 19
Ikrunswick 2 n ei:s Ihbad 9 h'3 Appendis D l Use of New Safety Limit MCPit for Cycle 10 The analyses required for this c> ele were performed with a safety limit MCPR of 1.07 instead of tne previous cycle's safety limit MCPR of 1.06. lne implerventation of this safety limit is a result of the uti'ization of the OE8x8NU 3 fuel type as provided by Amendment 21 to OESTAR ll (NEDE 24011 P-A). t L + 1 Page 20 I .... _... _ _. - ~. - - _.,. _ _....., _ -. - - -. _..., -..
t lirunsukk 2 nna m.ad e un-Appendix E Feedwater Controller Failure Analysis , The Feedwater Controuer Failure analysis (FWCF)(masimum demand) ADO is an increase f in coolant imenterv event normally checked on a cycle by cyck basis to Mermine if this AOO could potentiauy alter the cycle MCPR operating limit. This analysis was run for Cycle 8 and provided resultant Option 13 ACPR values of less than 0.08 The limiting AOO for Cycles 9 and 10 was load rejection without bypass with Option 13 ACPRs of 0.19 and 0.21. respectively. The cycle to cycle variations of the feedwater controller failure event's ACPRs and of the load rejectior2 event's ACPRs are smaller than the rol tively large differences between the feedwater controller failure event's and load rejection event's ACPRs. Furthermore, this trend is not af fected by the OEk8 Nil.1 fuel design. Therefore, this AOO will not be limiting for Cycle 10 and was not analyzed. 7 Page :1
6 lirunswick 2
- wm Rtbad 9 kn Appentil\\ l' Masimum I:stended Operating Domain Reference F.1 provided a basis for operat..
..I the Brunswick Steam Electric l'lant in the Ntasimum Extended Operating Domain ($11:OD). The reload licensing analysis performed for Cycle 10 and documented herein is consistent with and proside the cycle specifie update to the reference F 1 analysis. Reference F.I Maurnurrs Ettended Operating Dorrtain Analpis for Dntnsuick Stcarts Electnc l'lant NEDC.T1654P, GE Nuclear Energy (Proprietary) February 1980 Page 22 (linal) .}}