ML20086E355: Difference between revisions
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| number = ML20086E355 | | number = ML20086E355 | ||
| issue date = 11/30/1991 | | issue date = 11/30/1991 | ||
| title = Rev 0 to Ei Hatch Nuclear Plant Unit 1,Core Operating Limits Rept for Operating Cycle 14 | | title = Rev 0 to Ei Hatch Nuclear Plant Unit 1,Core Operating Limits Rept for Operating Cycle 14 | ||
| author name = Bethay S | | author name = Bethay S | ||
| author affiliation = GEORGIA POWER CO. | | author affiliation = GEORGIA POWER CO. | ||
Latest revision as of 07:26, 16 April 2020
| ML20086E355 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/30/1991 |
| From: | Bethay S GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20086E354 | List: |
| References | |
| NUDOCS 9112020024 | |
| Download: ML20086E355 (17) | |
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, , c. 1 . p h. by gy:, c t q 7 8;n v igj , r* yy:D. F.. %, .;;4, )a: gum e -f-n+y@1WW, , m.c s y a n,, , , <f;; L ;y4 ,g <.q;mre *Qr . . - dipja s si;gAJf %q.m 'w 1 , f A:g,, j# ~.. Mh M. sOK f ? ; me , 1 Qq #' w: g' . Nsj b "'t 'd Qh . Q. .c'yn eb g'd@y:Sq%, ; .CM u?qs.6 +w q@;Nf(_{, ey e '; 3;_ h j,7w n QW;h'-l ys ,< f_._ ni v- _ l - y . y4i* v s c ' og eN ,&"we ;a 2 7 r 1ge y mm ,34 a m y, e_ a4 ~ meggm # - i 4 n>s u-o < a m Ace lg/b w.~ _ ay3. . - + w + ~ . . g m 1, - ay4 g gA ,eypk .m %mwa f }f Qy} @, %Mb yyy ;pdr J ? NOVEMBER)996.gd% u w w%;;,w ;mn, - , + > c~ . , , .~ . ;r - ~ w.n g. w, m v np., w no%.nw:y a n my wy w&n~y~rgreyw/m x n an v t w wc< .~y n . LWfl _ , m ye I interoffico Correspondence ( wist h m t ! lO I < 'TE: November 4, 1991 RE: Core Operating Limits Report for llatch I Cycle 14 fuel Cycle Technical I file: Log: HL-1912 _ FROM: S. J. Bethay fj g _ 2 10: All Unit 1 Technical Spe fications Holders l By Amendment 168 to the Unit 1 Technical Specifications (IS), the NRC 3 authorized relocation of certain fuel-related limits from the Technical Specifications to the adjunct Core Operating Limits Report (COLR). This letter transmits to all Unit 1 Technical Specifications holders a copy of I Revision 0 of the Core Operating Limits Report for Hatch 1 Cycle 14. This document should be utilized in conjunction with the Unit I lechnical Specification as referred to in the Specifications. Normally, the shift I technical advisor (STA) or reactor engineer will utilize this report. necessary, the fuel limits from the COLR have been included in plant procedures, Where if changes to the core operating limits contained in this report are required, a complete revised COLR will be issued and the appropriate procedures revised, if there are any questions regarding this report, please contact me at extension 8-821-7392 or telephone number (205) 877-7392. SRP/cr 002462 Attachment cc: NORMS I I f I EO le i le GEORGIA POWER COMPANY EDWIN 1. HATCH NUCLEAR PLANT UNIT 1 FUEL CYCLE 14 CORE OPERATlHG LlHITS REPORT REVISION 0 I le i I I le SOUTHERN NUCLEAR OPERATING COMPANY POST OFFICE BOX 1295 BIRMINGHAM, ALABAMA 35201 == L EDWIN 1. HATCH NUCLEAR PLANT 3 UNIT 1 FUEL CYCLE 14 CORE OPERATING LIMITS REPORT
1.0 INTRODUCTION
The Core Operating Limits Report (COLR) for Plant Hatch Unit 1 Cycle 14 is prepared in accordance with the requirements of Technical Specification 6.9.1.11. The core operating limits presented herein were developed using NRC-approved methods (References 1 and 2). Results from the reload analyses for the General Electric (GE) fuel in Unit 1 Cycle 14 are documented in References 3 and 4. The following cycle-specific core operating limits are included in I this report:
- a. Operation with a Limiting Control Rod Pattern (for a Rod Withdrawal Error (RWE)) - Technical Specification 3.3.F.
I Average Planar Linear Heat Generation Rate (APLHGR) - b. Technical Specification 3 ll. A.
- c. Minimum Critical Power Ratio (MCPR) - Technical I Specifications 3.11.C and 4.ll.C.
- d. Linear Heat Generation Rate (LHGR) - Technical Specification 3.ll.B.
I LIMITING CONTROL R00 PATTERN (Technical Specification 3.3.F) 2.0 Both Rod Block Monitor (RBM) channels shall be operable as specified in Technical Specification 3.3.F and when: Revision 0 1 000484
PLANT llATCil UNIT 1 FUEL CYCLE 14 CORE OPERATING LlHITS REI - O I a. TilERMAL POWER is ( 90% of RATED lilERMAL POWER and the MCPR is < l.70, or i
- b. TilERMAL POWER is 2 90% of RATED THERMAL POWER and the MCPR is <
l.40. I 3.0 APLilGR LlHli (Technical Specification 3.ll. A) The APlilGR limit is given by the applicable rated-power, rated-flow limit taken from figures 3-3 through 3-7, multiplied by the smaller of either:
- a. The factor given by figure 3-1, or l b. The factor givtn by figure 3-2.
For the fuel types whose APlllGR limits are shown in figures 3-3 through 3-7, the APlilGR limit shall be applied to each axial location in the fuel assembly. As required by GESTAR Amendment 19, the hand calculated APLHGR values
~
for a multi-lattice (i.e., GE8-BD296) fuel must be less than or equal to the APLHGR limits shown in Figure 3-5. When APlllGR values are l determined by the process computer, the lattice-dependent APlllGR limits are used. Under these conditions, some axial locations may have APLHGR values exceeding the values shown in figure 3-5. 4.0 MCPR LlHIT (Technical Specifications 3.11 C and 4.11.C) I The MCPR operating limit (0LMCPR) is a function of fuel design, average scram time, core flow, number of opersting recirculation loops, and core power. I Revision 0 2 000484 5
I . PLANT HATCH UNIT 1 FUEL CYCLE 14 CORE OPERATING LlHITS REPORT O 4.1 luo Recirculation tegn Operation for 25% $ power < 30%, the OLMCPR is given in figure 4 1. For power 2 30%, the OlMCPR is the greater of either: I a. 1he applicable limit determined from figure 4-2, or
- b. The appropriate Kp given in figure 4-1, multiplied by ~
the appropriete limit from figure 4-3 where the scram time dependence is given in Technical Specification 4.ll.C.2. 4.2 Sinale Recirculation Lqqn DPfr_411RD for single loop operation, the MCPR operating limit shall be 0.01 greater than the two-loop value which is determined as specified in Section 4.1. 5.0 LHGR LlHIT (Technical Specification 3.11.B) The LHGR limit is 13.4 kW/f t for all GE7 fuel. The LHGR for GE8 and . GE9 fuel is 14.4 kW/ft. There is no corresponding limit for ANF 9x9 fuel. I D I I [ Revision 0 000484 _ . o
PLANT HATCH UNIT 1 FUit CYCLE 14 CORE OPERATING LlHITS REPORT
6.0 REFERENCES
- 1. " General Electric Standard Application for Reactor Fuel,"
NEDE-24011-P-A-9, September 1988.
- 2. Letter, L. P. Crocker (NRC) to J. P. O'Reilly (GPC), " Issuance of Amendment flos. 151 and 89 to Facility Operating Licenses DPR-57 and flPF Edwin 1. Hatch fluclear Plant Units 1 and 2 (TACS 66524/66525)," January 22, 1988.
I 3. " Supplemental Reload Licensing Submittal for Edwin 1. Hatch Nuclear Plant Unit 1, Reload 13, Cycle 14," General Electric Document 23A7131, Revision 0, September 1991.
- 4. "Edwin 1. Hatch Nuclear Plant Units ) and 2 SAFER /GESTR-LOCA Loss-of-Coolant Accident Analysis," (((DC-31376-P, December 1986.
- 5. Bases for Specifications 3.3.F, 3.ll.A, 3.11.8, and 3.11.C, Edwin I Hatch fluclear Plant Unit 1 Technical _ Specifications.
l l I le I Revision 0 4 000484
- nm
[ E mE
, oo 5 -t
- 102 5% h
-1070% f$
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- uAPFACp . ufNiuUM(urncOp.uAPuutTi p 8 uAPuut.T .1.0 FOR F10w > 61%
- aM FOn Ftp 5 6t%
0 70 - 3: uFnPor (F) - M *'uuusi.0.*F
- OFF) o F . FRACT10N or RATEO CORE FLOW.
g AND Ar.Op ARE FUEL TYPE DEPENDENT c: O CONST ANTS GIVEN BEL OW 3
~
uAatuou CORE FLOW A I RI (% RATE D) 102.5 0.4861 0.6784 107.0 0.45 r4 0.6758 112.0 0 4214 0.6Por 117.0 0.3A28 Offte6 0 50 - I I I I I I j 0 en 40 100 1'O 70 80 30 40 50 40l si CORE FLOW (% RATED) FIGURE 3-1 MAh F
W M 4M %M El U M M M IM M M I ME m' M O - tc o m.-' oy w a
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! 2.0 11.2 8.7 i l ;
l 4.0 11.5 9.0 i OPERATION !j i 't . l 6.0 11.8 9.2 i . j l N, N l 8.0 12.1 9.5 ! , ; 7 06 L E +- . 9- ~- J 10.0 12.3 9.6 ! ~ i i 12.5 12.4 9.7 . FUELTYPE[BW6RB2 4H,P86RB284HR I x i ! AND 9 X 9 LFA'S i! 8.5 O i i 80 - MIL CHANNELS i ! (6.6)* l l ' 628 a- . l, ; , , ,, 4 . ,, 0 5 10 15 20 25 30 35 40 45 AVERAGE PLANAR EXPOSURE (GWd/st) NOTES: c r uo,ca t,v::s roa 3 x 3 tras.! FIGURE 3-3 AVERAGE PLANAR LINEAR e x s muts cc.ut " TO $/FSOR22S4H FUEt. LINEAR HEAT GENERATION RATE LIMIT vs. AVERAGE PLANAR EXPOSURE y
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5... ..,, .....,,......... ...... . 0 5 10 15 20 25 30 35 40 45 50 AVERAGE PLANAR EXPOSURE (GWd/st) FIGURE 3-4 AVERAGE PLANAR LINEAR HEAT GENERATION LIMIT vs AVERAGE PLANAR EXPOSURE
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f l 80 MIL CHANNELS . , x , I l i i i i , , s.3s f 5 .. ,....,, ,. .. . . , , , AVERAGE PLANAR EXPOSURE (GWd/st) TH:S 15 THE APLHGR Ltu:I FOR THt , u05i LiviTt!4G LATT!Ct A3 A FUi4CTiCN or AvtaAct euma t eosuRt. i LINEAR HEAT GENERATION LIMIT vs l AVERAGE PLANAR EXPOSURE 1
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7- - 8.0 13.24 yj --- l \ 9.0 13.31 10.0 13.41
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FUEL TYPE:
' i
\:0 6- 12.5 13.50 GE9B-P8DWB315-8G4.0-80M-150 5.86 at 51.6 l t i ; l GWd/st
.,,.i... ,,,. ......,,,... ,,,
5,i ...,,,,2 .4 ..,,,.. 15 20 25 30 35 40 45 50 0 5 10 AVERAGE PLANAR EXPOSURE (GWd/st) l FIGURE 3-6 AVERAGE PLANAR LINEAR HEAT GENERATION LIMIT vs AVERAGE PLANAR EXPOSURE g
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ULI L> 8? A!!E 2.6 , , , , , , yh
$ > 50% FLOW , 7 OPERATING LIMIT MCPR(P) = Kp
- OPERATING LIMIT MCPR(100) %
g ~ FOR P < 25% : NO THERMAL LIMITS MONITORING REQUIRED 5g O _ , NO LIMITS SPECIFIED ,Q o g 2.4 N! (WHERE P ems = 30% FOR HNP -1,2) @.- gg _. : FOR 25% $ P < P emss Kp = (Km + 0.02(30%- P))/OLMCPR(100) Q O A< 2.3-. ' AND :oP K, = 2.00 FOR < 50% CORE FLOW [ g ( @n. 2.2- - 250% FLOW 7
" , = 40 FOR > 50% CORE ROW j Vi o n. 2.1-FOR 30% < P < 45% : j s
~
EE .
- Kp = 1.20 + 0.0134 (45%-P) l L
cc $ 2.0- l FOR 45% $ P < 60% : O3 b- ,1 s d ' FOR 60% < P : Kp = 1.15 + 0.00867 (60% - P) I'- 9: 1.5 Kp = 1.0 + 0.00375 (100%P) {g y$1.4 - t l l l l j _: o 1 l ~ l O P' i .3 - i
- 1'
~*~
~
1.2 - j I 1.1
' %YPASS " .
i 1.0 , , , l . . , , . , , I . , 20 25 30 40 50 60 70 80 90 100 POWER (% RATED) FIGURE 4-1 POWER-DEPENDENT MCPR MULTIPLIER (Kp)
M M E8 ME+ o o 1.7 ' 55 Q MAXIMUM FLOW RATE = 5N g FOR Wc (% RATED CORE FLOW) > 40% 5 , 117 % MCPR(F)= MAX (1.20, AfWc/100+Bf) [
*5
/< 112%
At Bf
/ /p r 107% MAX FLOW
/ // 102.5% 117.0 -0.632 1.609 d2 112.0 -0.602 1.747 :op 1.5 -> / ! - 107.0 -0.586 1.697 3Q j
\ ,
102.5 -0.571 1.655 @m l 3 84 1 1.3- - x y + - i 1.2 -
-+ * ~ - ' -
; x FOR We (% RATED CORE FLOW) < 40%
MCPR(F)=(AfWc/100+ Bf)
*[1 + 0.0032(40-Wc)]
1.1 , ,
,!,, 4 l , , . l . , .l , , . . , , . . , , < < ,
30 40 50 60 70 80 90 100 110 120 CORE FLOW (% rated) FIGURE 4-2 FLOW-DEPENDENT MCPR LIMITS, MCPR(F)
I' . PLANT HATCH UNIT 1 FUEL CYCLE 14 CORE OPERATING LIMITS REPORT O I MCPR LIMIT AS FUNCTION l OF AVERAGE SCRAM TIME g 1.3 1.29 + J I
=
0 J 1 28 -- -+ -
----e -+
Q
$ 1.27 -- - - --- -) - ,
t/ -- I 5 1.26 "M- - - - r, a. / ' L, 1.25 7 I CC 1.24 _-r 7-
-+ . - - _ __ _ . . _
1.23 ----- !--- !- d _ J : 1 I b I 1.22
-- + + - -
{ O E - - - " - 1.21 -- L3 1.2 i 1 o.o o.1 o.2 o.3 o.4 o.s o.e o.7 o.8 o.9 1.o g p rau l FIGURE 4-3 REVISION o I _}}