ML20082M827

Rev 1 to Core Operating Limits Rept for Limerick Generating Station Unit 2,Cycle 2

ML20082M827
Person / Time
Site:	Limerick
Issue date:	08/09/1991
From:	Carmody J, Dennin E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20082M812	List: ML20082M810 ML20082M817 ML20082M823 ML20082M827
References
PECO-COLR-L2R1, PECO-COLR-L2R1-R01, PECO-COLR-L2R1-R1, NUDOCS 9109060026
Download: ML20082M827 (25)

Text

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ENCLOSURE PECO Fugl Management Section PECO-COLR-L2 R1 L2R1 Coro Operating Limits Report Page 1; Rev. 1 CORE OPERATING LIMITS REPORT FOR LIMERICK GENERATING STATION UNIT 2 CYCLE 2 2 l5 lbj f_ .t 1

Prepared By: 'C"~~. Date: 1/ <

E.P. Dennin Engineer Reviewed 3y: ./ // ~ Date:

r-Independent Rev12wer Jl/4!QL l

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"'a' -<'

Approved By: 'O*U' i . ~ d' Date:

V < -i J.M. Carm6'dy supervising Engineer 9109060026 DR 010327 ADOCK 05000352 PDR

......,,i...

4 PECO Fue A Management Secticn PECO-COLR-L2R1 L2R1 Core operating Limito Report Pago 2, Rev. 1 i

i:

LIST OF EFFECTREhQES Page(s) Revision 1-25 1 l

PECO ruel Management Section PEco-COLR-L2R1 L2RL Core operating Limits Report Page 3, Rev. 1 IHIRQDUCTIQ}i_AND

SUMMARY

This report provides the cycle-specific parameter limits for-. Average Planar Linear Heat Gencration Rate (APLHGR); Minimum Critical Power Ratio (MCPR): Flow Adjuntment Factor (Kr); Linear Heat Generation Rate (LHGR); and Rod Block Mcnitor 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 not.

This report-is submitted in accordance with Technical Specification 6.9.1 of Referenca (1). Preparation of this report was performed in accordance with PECO Nuclear Group Procedure NP-11F122.

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

MCPR LIMIT The MCPR values for use in Technical Specification 3.2.3 are given in Figures 7 through 16. The Kg 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% power), Feedwater Temperature Reduction (up to 60 degrees F), Power Coastdown, and a combil.ation of all of these options. Curves are also provided for inoperable Recirc Pump Trip or inoperable Steam Bypass System.

ROD BLOCK 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).

4 PECO Fuel Management Section PECO-COLR-L2R1 l L2RI Core Operating Limits Peport Page 4, Rev. 1 LUjgbR HEAT _,fiENERATION BATI The LHGR value for use in Technical Specification 3.2.4 is given in Table 3~. These values are documented in References (3),

(4), and (6).

STEAM BYPA "' STEM OPERABILITY The operability requirements for the steam bypass system for use in-Technical Specifications 3.7.8 and 4.7.8.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 BUNDLES 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 are the values for the fuel type GE9B-p8CWB325-9GZ2-80M-150-T found in Figure 5. The LHGR values are-found in Table 3. The MCPR and MAPLHGR values for the Gell QFBs are found in Figures 11-12 and 6-respectively. The GEli LHGR value is found in Table 3. Thes values are documented in References (2), (3), and (4).

REFERENCES

1) " 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-CX+ 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.

5)L" Basis for MAPLHGR Technical Specifications-for Limerick l

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

6)_" General Electric Standard Application for Reactor Fuel",

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

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FIGURE 13

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MCPR VS TAU FUEL TYPE ABB QFB (INCREASED CCRE FLOW & FEEDWATER TEMPERATURE REDUCT! A WITH INOPERABt E STEAM BYPASS)

FIGURE 16

em tJ M r

Ke Factor vs Core Flow 58 I om  ;

1.4 OC NO l

2H f OX  ;

s - -

T, 3m  :

1.3 -

\[ss THIS FIGURE IS REFERRED TO BY 23 CI x xN'NN's TECHNICAL SPECIFICATION 3.2.3 u.

'g

.N N .

L tQ 3

. yN et

'N \ ,'\N,\

s pm Nxs xx s so ,

s.' ro  ;

\x \

• ft d s'x 1.2 - 'x 'N N s~

N

=-

O sN s.., 's y3 i N s 'N . m s

N [

Kf ~

x s xxx, s 8,

's N 'x N s s N. x o

1.1 - - 'N'N N. N s ,

q1x /x ,N / xy- x ~x w rwc<.a N s f

Scoop Tibe Satpule e C.shbnsWon Ponamed so That i / / \g ~x N s. 's N f-tow IAanknum/= iO2.5% ['/ /,/ x 'N s,' N.,.

/

/*

N 'sN

' N.

s N

s N

th Asamknan = 107.0% f ~

1- e w ua.um.n =itz a f

/

~

, rw ua am,o - ii7 a  ;

I 4 mm

, am i

, sa n ,

1 OO  !

0.9 - i i  ; i i i i ,, A  !

HO i 20 30 40 50 60 70 80 90 100 g l ws i Core Flow % of Rated oe

< es  !

.wg ,

FIGURE 17 "

t 7

k

i

• l PECO Fuel Management Section PECO-COLR-L2 R1 L2R1 Core Operating Limits Report Page 22, Rev. 1 TABLE 1 SINGLE LOOP REDUCTION FACTOR 0,88 l THIS FIGURE IS REFERRED TO BY l ,

I I

! TECHNICAL SPECIFICATION 3.2.1 i - i

1 l l i

\

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l t

e e

PECO Fuel Management Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Page 23, Rev. 1 p

i i

I i

i i

1 I

9 TABLE 2 i

l i

ROD BLOCK MONITOR SETPOINT t N=107 i

?

l i

f

(

I l

t THIS TABLE IS PSFERRED TO BY l 1 TECHNICAL SPECIFICATION 3.3.6 ,-

t

[

l I

( t

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

e e

. i PECO Fuel Management Section PECO-COLR-L2R1 L2R1 Coro Operating Limits Report Page 24, Rev. 1 l

I TABLE 3 L

-l t

)

LINEAR HEAT GENERATION RATE LIMIT ,

MAXIMUM VAL!JE Fuel TvDe Limit ( KW/ PT)_

i BP8X8R 13.4 ,

i.

GEBX8NB 14.4 [

Gell QFB 14.4 ANF QFB 14.4 ABB QFB 14.4 [

i

'r L

i THIS TABLE IS REFERRED TO BY l

! TECHNICAL SPECIFICATION 3.2.4 , I

I. t PECO Fuel Management Section PECO-COLR-L2R1 L2R1 Core Operating Limits Report Pago 25, Rov. 1 TABLE._i TURDINE DYPASS VALVE PARAMETERS TURBINEJYPASS SYSTEM . RESPONSE TIME Maximum delay time before 0.1 sec start of bypass valve opening following generation of the turbine bypass valve flow signal Maximum time after generation 0.3 see of a turbine bypass valve flow signal for bypass valve position to reach 80% of ft.11 stroke (includes the above delay time)

HI1U14UM REOUIRED BYPASS VALVES TO MAINTAIN SYSTEM OPERABILITX Number of valves = 7 THIS TABLE IS REFERRED TO BY l TECHNICAL SPECIFICATIONS 3.7.8 & 4.7.8.C i l

1 I

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