ML20101S686

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Rev 3 to Core Operating Limits Rept for Limerick Generating Station,Unit 2,Cycle 2
ML20101S686
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 03/23/1992
From: Andres L, Carmody J, Olson A
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20101S683 List:
References
PECO-COLR-L2R1, PECO-COLR-L2R1-R03, PECO-COLR-L2R1-R3, NUDOCS 9207200004
Download: ML20101S686 (25)
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IEECO Fuol Man;.gnm:nt Section'

'PECO-COLR-L2R1-L2R1 Core op rsting Limits: Report Pags 1,- Rev. 3 Y,zG%; '

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CORE OPERATING LIMITS REPORT FOR

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PECO-COLR-L2R1 r

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SUMMARY

This report provides the' cycle-specific parameter limits for: Average Planar Linear Heat Generation Rate (APLEGR); Minimum 2 Critical = Power Ratio (MCPR); Flow-Adjustment Factor (K );-Linear f

Heat Generation Rate (LHGR) ; and Rod. Block Monitor flow biased upscaleLandJhigh flow clamped setpcints for Limerick Generating StationLUnit 2, Cycle 2.

These~ values have-been determined using

.NRC-approved methodology and are established such that all applicable' limits of the plant safety analysis are met.

This report _is submitted in accordance with' Technical Specification-6.9.1 of Reference (1).

Preparation of this report

.was-performed in.accordance with PECO Nuclear Group Procedure NP-11F122.

APLHGR LIMIT-

-The limiting APIRGR value of each' fuel type as a function of AVERAGEL PLANAR EXPOSURE is given in Figures 1 through 6.

Figures 1 through 6 are used ;as'specified in Technical Specification

=3.2.1T The reduction' factor for use_during' single recirculation

~

hyj)kloop!operationisgiven-in~ Table-1.

-These-values are documented

N. in Reference (5),
"l MCPR LIMIT IThe MCPR values.for use in Technical Specification 3.2.3 are lgiven in Figures.7 through 16.

The Kr core flow adjustment

' factor for use in Technical' Specification 3.2.3 is given in Figure 17.

.These values are' documented in Reference'(2).

The-MCPR' values given are the bounding values for Increased-Core Flow - (up to 105% flow), Feedwater Temperature-Reduction (up to' 60 degrees F)',

Power Coastdown, and a combination of all of these options.

Curves are also provided for inoperable Recirc Pump. Trip or inoperable Steam Bypass System.

ROD BLOCK < MONITOR SETPOIHT The N value for the-REM flow biazed upscale and high flow clamped setpoints for.use in Technical Specification 3.3.6 is given in Table 2.

'These values are documented in Reference (2).

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  • ;jj/' LINEAR HEAT GENERATION PATE

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j The LHGR' value for use in~ Technical Specification - 3.2.4 is given in Table 3.

-These values are documented in References.(3),

(4), andL(6).

STEAM BYPASS-SYSTEM-CPERABILITY

~

The< operability requirements for the steam bypass system for uselin-Technical _ Specifications 3.7.8 and 4.7.S.C are found in Table 4.

If these requirements cannot be met the MCPR limits for inoperable' steam bypass system must be used.

These values are

' documented'in' References (2) and (6).

OUALIFICATION FUEL BUNDLEE The MCPR: values for-the Advanced Nuclear Fuel Inc. (ANF) and

ABB Atom Inc.-(ABB)-Qualification Fuel Bundles (QFBs) are found in Figures 13-16.

The~MAPLHGR values-for.use with the ABB and ANF=QFBs arecthe' values for the fuel-type ff 4 'GE9B-P8CWD325-9GZ2-80M-150-T found in Figure 5.

The LHGR values are found in Table 3.

The-MCPR and MAPLHGR' values for the Gell

% g 'QFBs are found in Figures 11-12 and 6 respectively.

The Gell

LHGR valueLis found in Table-3.

TheGe values'are documented in References ( 2 ),- - ( 3), and -( 4 ).

LPEFERENCE 11)E" Technical Specifications and Bases for Limerick Generating Station Unit 2", : Docket = No. 50-353' Appendix A to-License No.-NPF-85.

2) " Supplemental' Reload Licensing Submittal for Limerick Generating Station Unit 2, Reload 1, Cycle 2",

23A6548, Rev.

O, April 1991'.

3)!" Limerick 2 9x9-9X+ Qualification Fuel Assembly Safety Analysis Report", ANF-90-193(P), January 1991.

' 4 ):

ABB Atom-Report BR 91-042, " Supplemental Lead Fuel Assembly. Licensing. Report, SVEA-96 LFAs for Limerick-2, Summary",

January 1991.

64 5)1" Basis for MAPLHGR Technical Specifications for Limerick

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Generating-Station Unit 2",-NEDC-31930P, April 1991.

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6) " General El ectric. Standard Application for Reactor Fuel",

NEDE-24011-P-A-9, latest approved revision.

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1 s >~-

,$9Y 1A5 1A6

'/

1.44 1.44 f

1.42 1.42 1.40 1.40 f

/

1.38 1.38 O

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 i

T MCPR VS TAU FUELTYPE ANF OFB (INCREASED CORE FLOW & FEEDWATER TEMPERATURE REDUCTION VilTH OPERABLE STEAM BYPASS) i

~>'

FIGURE 13 g

a w

r o.

4*2 " L PECO Tuel Management Section'

,PECO-COLR-L2R1 i

L2R1 Core Operating Limits Report -

-Page 18,-Rev. 3-4

'6,

g%
.y

.?,

1.e4

' 1.s4'.

THIS FIGURE IS REFERRED TO BY 1.52 1.62-

~

TECHNICAL SPECIFICATION 3.2.3 1.55-1.58-77 N lsi '10EocwpT 1.55 1.56 97 ys d W4F#T 1.54 1.54 gge smul tr

. D 1.5'2

/_

-1 u..

q.

.g;3.-o70s,

- 1,5 1.5 HP:3)

"Ik[Mk spc10 EON 1.4::

1.4e 1.46 1A5-1.44 1M

~

1.42 L

.1.42

,4 r

i i

e i

t i

i

~ i

),4 _

),4 0-0.1 0.2 0.3 0.4

- 0.5 0.6

. 0.7 0.8 0.9 1

t MCPR VS TAU FUEL TYPE ANF QFB-

- (INCREASED CORE rLOW & FEEDWATERTEMPERARIRE F. EDUCTION WITM INOPERABLE STEAM BYPASS) 2 FIGURE 14

..L..,

u 4

O er 4

-y

,-e.

s,

-e

~

W,e r,

4 s

~

,p+, h p

J'fPICOj } uslainnagement? Section' PICO-COLR-12F1 K? -~; L2RR Core - Operating _ ' Limits. Report

Page 19,-Rev. 3

..i, y

ejm~

7a u_

" y[Q$f?

^;1.

' Q:;

3 62 1

1.62 g

l

f. 1.f 3

'1.60

~

ecsW.. y I.

to. _g W-gos-1.u

-1.c..o,

.o u

1.56 3m,cirwor

- l 1.55 s:cio,--

4 t

l 1.54 1.54-h

'i 1.52l THis FIGURE IS REFERRED TO BY

{ i.52 c-l 1.:.0.

o_1-

- TECHb'ICAL SPECl?lCATION 3.2.3

, o - 1.eo -

g 2

/,,.-

1.48 1A:

0

  • 'I g,e5 at:

]

4 3 j3 -;

/ g:

.!, gj5 i

1.44,./-

! 1,,

fg

.w

/

~

nte[

J1.42) r 1A2 i

l 1 A0 y

..1AO' 7-

/

t I

8 i

t i

I 1.38-

^

8 1.55 0

0.1-0.2 0.3 - 0.4 0.5 0.6 0.7

.0.8

' O.9 1

~(

i?.

4 MCPR VSTAU

. FUEL TYPE ABB QFB

-(INCREASED CORE FLOW & FEEDWATERTEMPERATURE REDUCiiON WITH OPEPASLE SFcAM BYPASS) rw.

)

y '.

' 'R c4 4 -

7QJ FIGURE 15 9

e 8

,-n

TECO--COLR-L2R1

  • FECO Tuel Management Section L L2R1 Core Operating Limits Report Page 20, Rev. 3 n

ip 1.e4 1.e4

  • HIS FIGURE IS REFERRED TO BY 1.e2

)

1.s2

~~

TECHNICAL SPECIFICATION 3.2.3

~

1.6 1.6

-g ed5iN 1.55 1.55

/- 1.50 socioE $ g,asiworfi 1.c o-J 1.5, 1.%,.

d TTOEX

.C-EOC d g #

1.52 h l(.52 #y

'E ~

3c

'W

33 7

8-

'i[fqbi 3ccioE

, 48

, 4._:

j i.

i.

1.4S 1.46 1.4 1.44 1.42

^ 1.42 1.4 1.4 0

0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1

T MCPR VS TAIJ FUELTYPE ABB QFB (INCREASED CORE FLOW & FEEDWATERTEMPERKfURE REQUCE.ON WITH INOPERABLE STENA BYPASS)

~

FIGURE 16

p
  1. "' ?ECO Fuel Management. Section PECO-COLR-L2R1 4

- L2R1-Core Operating Limits Report -

Page 21, Rev. 3 "4_%,'

1 e

OO I

y 7 CO CD y Od Z

C O O

w-o C 1<--

Cw0 LL

~u,,

W-c'O uj

_O

$2 C. -

CD 5

w 5

C J Dh O

12 4

_o it sa 6,

/

ba

, y.

/

a

b P-E,

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u O

_o t

Ov a-.

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age o-e to o c,b gggg O

3 s k,.i E

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4 3

11==

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=

c6

)

{ n%

v g

g

._ O

=

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// Vl.

/'

o 1

i I

l i N CS,

-t, co, CN!

r, r

T-T-

T-r-

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.I

,,.g..

,1

- ;.m o.

. >d PECO-Fuc1; Management Section PECO-COLR-L2R1

L2R1 Core'.; Operating Limits Report Paga 22, Rev. 3 X

gn;

17e, 3

T TABLE 1

' SINGLE. LOOP REDUCTION FACTOR

'yg.

, kj.[f:

i 0.88 1

5 r

I e

THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFlCATION 3.2.1 ha

. nem'.

' !. QJ#'

$g; I f' b

i.'

i

m; e-

g-n

,. ;s.

1:

u, ' {,_ b.,

1 -

9+'i g-.

FECO 4McT Menas, eras. Section PEco-c0LR-L2 Q,

lL2R1 Core lOpent.ing Limits Report Pega 23, Rev.-

n.

l, "I ;. I fh*

i..a

,1 s <; f

  • i

)

f I'

I k

i 1

? i.

f' l

t nLLILt

)

Y I

ROD DLOCK MONITOR SETPOINT i

3 N~ m

ygg w

4 F

I THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.3.6 EL".

(

['-

h I

w-

  • y,y

s l<s'a PECO Fual Montgamont Scction PECO-COLR-L2R1 a.

. /:

L2R3_ Coro Oparating Liraita R: port Pago 24s Fev. 3

)

- if~7.,

[

t

.,4 m

l TMILE_?.

A LINEAR HEAT GENERATION RATE LIMIT

!QXIEl'.M VALilE Fuel TV.pn Jdait f W/FT)

P c

BP8X8R 13.4 Lt, f. '

GE8X8HB 14.4 Gell QFB 14.4 ANF.QFB 14.4 ABB QFB 14.4 s

1 1HIS FIGURtiIS REFERRED TO BY TECHNICAL SPECIFICATION 3,2.4 -

4 9

f.-

m..

u i

f

>-++we

~

_, _+

i - <.

.m

.;.} :1,,

h, a +. o PECO Puol / Management ' Section1 PEco-COLR-L2 R1 D

.-L2R1 Core t 0porating / Limits Report Page 25, Rev, 3
i?)M o

?

jf Glll p,7- %, w lW TAILLI I

- f.

TURBINE P' PASS VALVE PARAMETERS

.,c 4

l TURBINE BYPASS _ SYSJJE RESPONSE TIME F-Maximum delay tino before 0.1 sec g!

- start.of bypass. valve opening following generation of the turbino bypasri valve flow N

signal-y

- Maximum time after. generation 0.3 see i

-:-p,g:,,

l

- of'a turbine: bypass valve flow.

si nal forfbypass valve

- ll3ygg r 4

, w/T

- posit on to; reach 80% of full M

stroko (includes the'above delay -time) a

_t

liINIMUM REOUIRED BYPASS VAINES TO MAINTAIN LS_l'SIEM OPERABILITY

,.s

f.

,1

' Number'of' valves = 7-

~

M 1l 1

.a h-,-

h T

THIS FIGURE IS REFERRED TO BY.

h

[. TECHNICAL $PECIFICATIONS 3.7.8 & 4,7,8.C ey

. 3l)lfl

}

{ f- '.-}',

_ _a

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