ML20092A902

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Rev 2 to Core Operating Limits Rept for Limerick Generating Station,Unit 2,Cycle 2
ML20092A902
Person / Time
Site: Limerick Constellation icon.png
Issue date: 12/31/1991
From: Andres L, Carmody J, Olson A
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20092A898 List:
References
PECO-COLR-L2R1, PECO-COLR-L2R1-R02, PECO-COLR-L2R1-R2, NUDOCS 9202100343
Download: ML20092A902 (25)
v • d • e


Text

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P'ECO Fuel Management Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 1, Rev. 2 4

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CORE OPERATING LIMITS REPORT FOR LIHERICK GENERATING STATION UNIT 2 l CYCLE 2 1

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Prepared By:[/ 4j . ~ Date: I2[def l L. L. Andres 1 Engineer Reviewed By: - - --

Date: /2/31/4] _

( 3 /

is A. M. Olson Independent Reviewer Approved By:

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/ e Date: '*b/9 ,

J. M. Carmody supervising Engineer 9202100343 920131 .

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i PECO Fuel Management l'oction PECO-COLR-L2R1 L2R1 Core Operating LJmito Hoport Page 3, Rev. 2 ,

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PECO Fuel Management Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 3, Rev. 2  ;

lli1RQDUCTIOli AND

SUMMARY

f This report provides the cycle-specific parameter limits for: Average Planar Linear Heat Generation Rate (APLHGR); Minimum i Critical Power Ratio (MCPR); Flow Adjustment Factor (Kr); Linear Heat Generation Rate (LHGR); and Rod Block Monitor flow biased upscale and high flow clamped setpoints for Limerick Generating Station Unit 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 in submitted in accordance with Technical '

Specification 6.9.1 of Reference (1). Preparation of this report van performed in accordance with PEco Nuc1 car Group Procedure

- NP-11F122.

APLHGR LIMIT The limiting APLHGR "alue of each fuel type as a function of AVERAGE PLANAR EXPOSURE is given in Figures 1 through 6. Figures 1 through 6 are used t.s specified in Technical Specification 3.2.1. The reduction factor for use during single recirculation i loop operation is given in Table 1. These values are documented i in Reference (5). l t

4 MCPR LIMIT The MCPR values for use in Technical Specification 3.2.3 are given 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).

j The MCPR values given are the bounding values for Increased Core Flow (up to 105% power), 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 Dypass System.

t R DLOCK_. MONITOR SETPOINT

- The N value for the RBM flow biased 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).

L

_ . - - - . , . . _ . . . - ~ . , _ . , . . _ . . _ _ , , _ - . _ , , _ _ . _ . . . - . .._ ,_,._,._ . _ _....._.. __.,, ..,_,,,. _ ..m . . _ _ _ . . , .

lECO i Tuol Management Section PECO-Cout-L2R1 L2R1 Coro operating Limits Report Pago 4, Rev. 2 ,

L,llEAR llEAT_QEllERATION R1hTE The U1GR value for use in Technical Specification 3.2.4 is i given in Tablo 3. These values are documented in Hoforences (3), t (4), and (6) .  !

SIEN4 BYPASS SYSTD1_QEEEABILITY

~The operability requirements for the steam bypass system for use 1n Technical Specifications 3.7.8 and 4.7.8.C are found in Table 4. If those requirements cannot be act the MCPR limits for inoperable steam bypass system inust be used. These values are  !

documented in References (2) and (6).

1 QUALIFICATIOli FUEL 11MllDLES,  !

The MCPR values for the Advanced Nuclear Fuel Inc. (ANF) and 3 ABB Atom-Inc. (ABB) -Qualification Fuel Bundles (QFDs) are found

/ in~Figuros 13-16. The MAPulGR values for use with-the ABB and

ANF QFBs are tho values for the fuel type GE9B-P8CWB325-9GZ2-80M-150-T found in Figure 5. The u!GR values

? are found in Table-3. The MCPR and MAPU!GR values for the Gell l- QFDs are found-in Figuros 11-12 and 6 respectively. The Gell UIGR value is found in Table 3. These values are documented in References (2), (3), and (4).

'l ,

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J REFEREl[QE 1; "Tochnical Specifications and Bases for Limerick '

l Generating Station Unit 2", Docket No. 50-353 Appendix A to

License No. NPT-85. -
2) " Supplemental Roload Licensing Submittal for Limerick i Generating Station Unit 2, Roload 1, Cycle 2", 23A6548, Rev. O, April 1991. ,
3) " Limerick 2 9x9-9X+ Qualification Fuel' Assembly Safety Analysis Report", ANFOO-193 (P) , January 1991.
4) ABB Atom Report BR 91-042, " Supplemental Lead Fuel L-Assembly Licensing Report, SVEA-96 LFAs for Limerick-2, Summary",

January 1991.

5) " Basis for MAPU!GR Technical Specifications for Limerick Generating Station _ Unit 2", NEDC-31930P, April 1991.
6) "Goneral Electric Standard Application for Reactor Fuel",

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

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P$'CO Tuel Hanngement Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 5, Rev. 3 _

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PECO Iuol !!anagement Section PECO-COLR-L2 R1 L2R1 Core Operating Limits Report Page 11, nev. 2 1,44 - -

1.44 1.42 THIS FIGURE IS REFERRED TO BY 1.42 TECHNICAL SPECIFICATION 3.2.3

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MCPR VS TAU FUEL TYPES BP8X8R (INCREASED CORE FLOW & FEEDWATER TEMPERATURE REDUCTION WITH OPERABLE STEAM BYPASS)

FIGURE 7 4

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D: el %pr:Vment Section PECO-COLR-L2R1 W L; Lore. Operat "g Lirits Report Page 12, Rev. 2

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1.42 N Y ;HNICAL SPECIFICATION 3.2.3 1.4 - 1.4

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MCPR VS TAU FUELTYPES BP8X8R (INCREASED CORE FLOW & FEEDWATERTEMPERATURE REDUCTION WITH INOPERABLE STEAM BYPASS)

FIGURE 8

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  • PECO Fuci Management Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 13, Rev. 2 3 1,44 1.44 1.42 .

THIS FIGURE IS REFERRED TO BY 1.42

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TECHNICAL SPECIFICATION 3.2.3 1.4 1.4 1,38 EP 1.38

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1.34 1.34 g - .

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1.22 1.22 1.2 1.2 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 TWES GEBX8NB (INCREASED CORE FLOW & FEEDWATER TEMPERATURE REDUCTICN WITH OPERABLE STEAM BYFASS) i FIGURE 9 7.

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  • e PECO Fucl Management- - Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 14, Rev. 2 3

1.44

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- 1,42 THIS FIGURE IS REFERRED TO BY 1A2 TECHNICAL SPECIFICATION 3.2,3

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PECO Fuel Management Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 15, Rev. 2 9

1.50 1,50 1.48 THIS FIGURE IS REFERRED TO BY 1.48 TECHNICAL SPECIFICATION 3.2,3 1.46 - 1gg too.:nuwc/srtotocw/oy 1.44 --

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MCPR VS TAU

[ FUEL TYPE GE11

-(INCRE ASED CORE FLOW & FEEDWATER TEMPERATURE REDUCTION WITH OPERABLE STEAM BYPASS)

FIGURE 11 i:

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PECO Fuel' ManagcTent Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 16, Rev. 2 1.54- 1.54 1.52 THIS FIGURE IS REFERRED TO BY 1.52

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I TECHNICAL SPECIFICATION 3.2.3 1.5 1.5

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MCPR VS TAU

~ - FUELTYPE GE11 I

(INCREASED CORE FLOW & FEEDWATERTEMPERATURE REDUCTION WITHINOPERABLE STEAM DYPASS)

FIGURE 12

- ~. . . ._. .- - ---_ .. -

PECO: Fuel Management Section PECO-COLR-L2R1 L'2R1 Core Operating Limits Report- Page 17, Rev. 2 1.62 1.62

. 1.60 THIS FIGURE I.S REFERRED TO BY 1.60 TECHNICAL SPECIFICATION 3.2.3 1.58 __

1.58 myoisTM 1.56 1.56 .

1.F' "/ glsTW N" - 1.64 j -

1.52 -

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N 1.46 1.46 "MpgD ij

. 1.44 - 1.44 1,42

/- 1.42

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MCPR VS TAU FUELTYPE ANF QFB <

(INCREASED CORE FLOW & FEEDWATER TEMPERATURE REDUCTION W:TH OPERABLE STEAM BYPASS)

FIGURE 13

. _ . .,_ . _ _ . - . - - ,, v-..,....... . . .-_ _ _ , _ _ _ . .

l

  • PECO Fuel Management-Section .

PECO-COLR-L2R1 L2R1 Coro Operating Limits Report Page 18, Rev. 2 4

No n

1,64 1.64 THIS FIGURE IS REFERRED TO BY 1.62 1.62

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i TECHNICAL SPECIFICATION 3.2.3 1.6 1.6 ,

1.58 1.58 1.56

. 1.56-1.54

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D.,. r MCPR VS TAU

} FUELTYPE ANF QFB

, (INCREASED CORE FLOW & FEEDWATER TEMPERATURE REDUCTION WITH INOPERABLE STF14A BYPASS)

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._ . .- .. . . ~ . . . - _ - . - . - . - .- -- -- .._

PECO. Fuel Management Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 19, Rev. 2

~

1,62 -

1.62 1.60 1.60

~

LoewtonPT

.1.50 ., gno!513 1.58 1.56' , gung, - 1.56 1.54 1.54 1.52 1.52 THIS FIGURE IS REFERRED TG 3Y

g. . .

TECHNICAL SPECIFICATION 3.2.3 3,3g

$ 1.50 -

2 -

. 1.48 1.48 p 110 @ .

1.46 0 1.46

/ -

1.44 1.4,a i _

1.42- ,oto# 1.42

- 1.40 1.40

/y- .

'1.38 1.38 0 0.1 0.2 - 0.3 0.4 0.5 0.6 - 0.7 0.8 0.9 1 T

y i MCPR VS TAU FUEL TYPE ABB QFB (INCREASED CORE FLOW & FEEDWATER TEMPERATURE REDUCTION WITH OPERABLE STEAM BYPASS)

FIGURE 15

PECO Fuel-Hanagement Section- ..

PECO-COLR-L2R1 L2R1 Core Operating Limits Poport Page 20, Rev. 2

1,64 1.64

~

THIS FIGURE IS i'.EFERRED TO BY 1.62 1.62

~

TECHNICAL SPECIFICATION 3.2.3 -

1.6 1.6 tec 8-1.58 1.58 .

_p -

1.56

-1.56 g,guestw;oBP1 1.54 1 54

. g gW 51otoc -

1.52

_1.52 _

I 1.5 1.5 -

soc 10 E#

1,48 1.48

  1. y .

1.46 1A6'

' 1,44.

1.44 j -

1.42 1.42 ,

i i 1 i e i g,4 3,4 _i -

  • = -0 0.1 - - 0.2 0.3 0.4 0.5 - 0.6 0.7 0.8 0.9 1 4

T

..-~

?!

MCPR VS TAU ei . FilELTYPE ABB OFB 1 (INCREASED CORE FL7W & FEEDW/.TERTEMPERATURE REDUCTION WITH INOPERABLE STEAM BYPASS) i.

I FIGURE 16

-[ . --

~,

-m.:. . . . . . . . , . . . . . . . . . . . . . . . , . . - - . . . -

.. ~ .

4 e7

Kf Factordvs;Oo'sFlow- .

1.4. 92 M.O

.: o - O >';

1 N 's . -

THIS FIGURE IS REFERRED TO BY ya 1.3  : ~7 TECHNICAL SPECIFICATION 3.2. 3 lI$  :

s 30 tQ D rt M

pg ,

.1.2 -

o-O I-

K '

e'

%D i

N \ $-

Secop7the Sept cam 8ert Poe'doned SoThat

- WNx N h,

Ftr < Aamban = 102.5%

a1 _- Th. s Maxhmt = 107.0%  % ,

~

FEw L6fmum = 112.0%

Tbw Ab! mum = 117.0% 7

-m te M

.a n 0.9 i i i i i o ?l  ;

un 20 30 40 50' 60 70 80 90 100 ro 5

Core Flow % of flated wi

.Em- C ,

FIGUI.'i 17 y

+

Ya

. , _ - . -.. .~ . .- .- . .- . . . . .

NECO Fuel Management Section PECO-COLR-L2R1 '

L2R1-Coro Opurating Limito Report-Pcgo 22, Rev. 2 TADLE_.1 I

SINGLE LOOP REDUCTION FACTOR O.98

j. ;

1 :.

i .

r i

THIS FIGURE IS REFERRED TO BY

- TECHNICAL SPECIFICATION 3.2.1 i.

L I

l

, c

+

PECO Fuel Management Section PEco-COLR-L2R1 L2R1- Core' Operating Limits Report Page 23,-Rev. 2 4

2 4

6 a

M. .

.g. ,

4 TAD.LE_1

- ROD BLnCK MONITOR SETPOINT 9

N=107

}

d L

l -

~

i THIS FIGURE IS REFERREDTO BY l' TECHNICA' SFECIFICATION 3.3.6 l

l:

t.,

I ..

t

.+, - - - , . _ . -

a PECO Fuel' Management Section PECO-COLR-L2R1 L2R1 Coro Operating Limits Report Page 24, Rev. 2

.tc IADLE_1 LINEAR HEAT GENERATION RATE LIMIT 5-

'f - MAXIMUM VALUE

. ruel Tvne Ilmit; (KW/IT1

.5 4- BP8X8R 13.4 l

GE8X8NB 14.4 Gell QFB 14.4 t, '

Q- ANF QFB 14.4

ABB.QFB .14.4 e

{

!?

g .

'THIS FIGURE IS REFERRED TO BY TECHNICAL SPECIFICATION 3.2.4 Y

T J'

4

'PECO Fuel Management Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 25, Rev. 2 1 ThkkK._A i

TURDINE BYPASS VALVE PARAMETEFS i

IUPSTNE BYPASS SYSTEM RESPONSE TIME _

b Maximum delay time bef'oro 0.1 see '

start of bypass valve apening '

j following generation of the ,

turbine bypass valve flow

> signal i

I Maximum time after generation 0.3 sec of a turbine bypass valve flow

/' sig'nl for bypass valve position to reach 80% of full

. stroke (includes the above I delay tiiae)

MINIr4UM REQQTRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITY i

j Number of valves = 7

?

I

$3 I -

2 THIS FIGURE IS REFERRED TO BY

? TECHNICAL SPECIFICATIONS 3.7.8 & 4.7.8.C l

\

s

- - - - - - ,

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