ML20043H105

Reload 9/Cycle 10 Core Operating Limits Rept.

ML20043H105
Person / Time
Site:	FitzPatrick
Issue date:	06/06/1990
From:	Burch D POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
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ML20043H086	List: ML20043H085 ML20043H105
References
NUDOCS 9006220014
Download: ML20043H105 (26)

Text

,

t 2 NEWYORK POWER AUTHORITY

. JAMES A. FITZPATRICK NUCLEAR POWER PLANT

. CORE OPERATING UMITS REPORT l

PORC MEETING NO. 90-57 Date 6/6/90 Orig. signed by APPROVED BY:- D. Durch Date Reactor Analyst Supervisor l Orig. signed by APPROVED BY: w. Fernandez Date Resident Manager  ;

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-9006220014 90061'1 POR ADOCK 05000333 p PNV g Rev. No. O Page 1 - of 26

1 NEW YORK POWER AUTHORITY - l JAMES A. FITZPATRICK NUCLEAR POWER PLANT

'. CORE OPERATING UMITS REPORT 1.0 PURPOSE' This report provides the cycle specific operating limits for Cycle 10 of the James A. RtzPatrick Nuclear Power Plant. The following limits are addressed:

Operating Umit Minimum Critical Power Ratio (MCPR)

Flow Dependent MCPR Umits Maximum Average Planar Unear Hoat Generation Rate (MAPLHGR)

Unear Heat Generation Rate (LHGR)

Flow Blased Average Power Range Monitor (APRM) and Rod Block Monitor (RBM)

Settings .

2.0 APPUCABluTY The plant must be operated within the limits specified in this report. If any of these limits

. are vio!sted, the corrective actions specified in the Technical Specifications must be taken.

3.0 REFERENCES

3.1 JAFNPP Administrative Procedure 7.2, Control of Core Operating Umits Report. -}

3.2 JAFNPP Ucense Appendix A, Operating Technical Specifications.

3.3 RtzPatrick Cycle 10 Reload Safety Evaluation.

3.4 GE11 Lead Test Assembly Report.

3.5 JAFNPP SAFER /GESTR LOCA Loss of Coolant Analysis,NEDC-31317P, including Errata and Addenda Sheets 1,2 and 3.

3.6 Supplemental Reload Ucensing Submittal for JAFNPP Reload 9 Cycle 10, GE Report 23A6482 February,1990.

3.7 JAFNPP LOCA Analysis, NEDO-21662 2 Amended July,1984.

Rev. No. O Page 2 of 26

NEW YORK POWER AUTHORITY li '

JAMES A. FITZPATRICK NUCLEAR POWER PLANT. 4 j' 4 CORE OPERATING UMITS REPORT- l l

l l

L - 4.0 DEFINITIONS l l

l~ 4.1 Minimum critical power ratio (MCPR) Minimum value of the ratio of that power in a fuel I assembly which is calculated to cause some point in that fuel assembly to experience boiling transition to the actual assembly operating power as calculated by application of I

the GEXL correlation (Reference NEDE 10958).

l 4.2 - Fraction of Umiting Power Density The ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHGR. The design LHGR is given in Table 8.2.

l l 4.3 Maximum Fraction of Umiting Power Density The Maximum Fraction of Umiting Power Density (MFLPD) is the highest value existing in the core of the Fraction of Umiting Power Density (FLPD).

4.4 8 Rated Recirculation Flow - that drive flow which produces a core flow of 77.0 x 10 lb/hr.

l 5.0 RESPONSIBlUTIES l 5.1 See AP 7.2 (Reference 3.1). I 5.2 It is the responsibility of the Shift Supervisor to assure that the reactor is operated within -l the limits described herein.

6.0 SPECI AL INSTRUCTION S/ REQUIREMENTS ,

i. Not applicable, i

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l 1

h 1

l l

Rev. No. O Page - 3 of 26 l

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..- i NEWYORK POWER AUTHORlW

' JAMES A. FITZPATRICK NUCLEAR POWER PLANT

'. CORE OPERATING UMITS REPORT I

i

! 7.0 PROCEDURE l

7.1 -. Operating Umit MCPR .j During power operation, the Operating Umit MCPR shall be equal to or greater than the j limits given below.'

7.1.1 Technical Specification

Reference:

3.1.8  ;

i 7.1.2 The Operating Umit MCPR shall be determined based on the following requirement:

l l 7.1.2.1 The average scram time to notch position 38 shall be:  ;

=l l RAVE.1TB }

t 7.1.2.2 The average scram time to notch position 38 is determined as ,

l follows:  !

FI EN iri i=1 rse= ,,

ENi  ;

e i-1 i  ;

where:

n= number of surveillance tests performed to date in the cycle, N=i number of active rods measured in the th -

_ surveillance, and ,

ri

= average scram time to notch position 38 of all rods measured in the th I surveillance test.

7.1.2.3 The adjusted analysis mean scram time is calculated as follows:

,1/2 Ni ,

rn (sec)= + 1.65o ,,

ENi

'i=1 '

Rev. No. O Page - 4 of 26

l NEWYORK POWER AUTHORITY ]

- JAMES A.- FITZPATRICK NUCLEAR POWER PLANT J A '

CORE OPERATING UMITS REPORT '

7 where:

.- p= mean of the distribution for the average scram insertion time to the pickup of notch position

, 38 = 0.706 sec.~

a= standard deviation of the distribution for average scram insertion time to the pickup of notch position t 38 = 0.016 sec.

Nr -- the total number of active rods measured in e Technical Specification 4.3.C.1.

p.

The number of rods to be scram tested and the test intervals are given in Technical Specification 4.3.C.

7.1.3 When requirement of 7.1.2 is met, the Operating Umit MCPR shall not be less than that specified in Tables 8.1.a through d.

7.1.4 - When the requirement 7.1.2 is not met (i.e. rg < RAVE ) then the Operating Umit MCPR values (as~ a fraction of r) are given in Figures 8.1.a through d, where r = (RAVE rg)/(rg rg)

L and I the average scram time to notch position 38 as defined in RAVE = l 7.1.2.2 1 i

rg = the adjusted analysis mean scram time as defined in 7.1.2.3 _,

L the scram time to notch position 38 as defined in Technical rA =

Specification 3.3.C.1.

L Note: Should the operating limit MCPR obtained from these figures be less than the operating limit MCPR found in 7.1.3 for the -)

applicable RBM trip level setting then 7.1.3 shall apply,

, '7.1.5 During single-loop operation, the Operating Umit MCPR shall be increased by -

0.01.

7.1.6 During reactor power operation with core flow less than 100 percent of m;ed, the Operating Umit MCPR shall be multiplied by the appropriate K, specified in Figuro 8.2.

[' Rev. No. O Page S - of 26

a U NEW YORK POWER AUTHORITY-JAMES A. FITZPATRICK NUCLEAR POWER PLANT ,

CORE OPERATING UMITS REPORT 7.1.7 MCPR for the Quad + fuel need not be monitored. Core position of Quad +

fuel assures that MCPR is not a concern, and that power limitations are  ;

observed.  !

7.2 Maximum Average Planar Unear Heat Generation Rate (MAPLHGR) 7.2.1 Technical Specification

Reference:

3.5.H j 7.2.2 During power operation, the APLHGR for each fuel type as a function of axial location and average planar exposure shall be within limits based on t applicable APLHGR limit values which have been approved for the respective fuel and lattice types. ,

7.2.3 When hand calculations are required, the APLHGR for each type of fuel as a function of average planar exposure shall not exceed the limiting value for the most limiting lattice (excluding natural uranium) shown in Figures 8.3.a

[ through g.

1 7.2.4 During single loop operation, the APLHGR for each fuel type shall not exceed the values given in 7.2.2 or 7.2.3 above multiplied by 0.84.

7.3 Unear Heat Generation Rate (LHGR) 7.3.1 Technical Specification

Reference:

3.5.1 l

7.3.2 The LHGR of any rod in any fuel assembly at any axial location shall not exceed the maximum allowable LHGR specified in Table 8.2.

7.4 APRM Trip Settings 7.4.1 APRM Flow Referenced Flux Scram Trip Setting (Run Mode) l i 7.4.1.1 Technical Specification

References:

2.1.A.1.c, Table 3.1 1, 3.1.A 7.4.1.2 When the Mode Switch is in the RUN position, the APRM flow referenced flux scram trip setting shall be S10.66W + 54% for two loop operation; S50.66W + 54% -0.66 AW for single loop operation; where:

Rev. No. 0 Page - 6 of 26

NEW YORK POWER AUTHORITY '

' JAMES A. FITZPATRICK NUCLEAR POWER PLANT '

l- - CORE OPERATING LIMITS REPORT S= setting in percent of rated thermal power (2436 L MWt); )

1 W= recirculation flow in percent of rated; AW = - difference between two loop and single loop _ l effective drive flow at the same core flow.1 h

7.4.1.3 in the event of operation with a maximum fraction of limiting i power density (MFLPD) greater than the fraction of rated power -

(FRP), the setting shall be modified as follows: ,

1 S 5 (0.66W + 54%)(FRP/MFLPD) for two loop operation; )

'1 S 5 (0.66W + 54% 0.66 AW)(FRP/MFLPD) for single loop j l

operation; q l l where: l 1

FRP = fraction of rated thermal power (2436 MWt);

l' MFLPD = maximum fraction of limiting power density, where i

the limiting power density is as specified in Table I

! 8.2.

i i The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than the I design value of 1.0, In which case the actual operating value will be used.

7.4.2 APRM Flow Blased Rod Block Setting l

l' 7.4.2.1 Technical Specification

References:

2.1.A.1.d, Table 3.2-3,3.2.C.1 l

~

7.4.2.2 The APRM rod block trip setting shall be:

i S 50.66W + 42% for two loop operation; S 50.66W + 42% - 0.66 AW for single loop operation; where:

S= rod block setting in percent of rated thermal power (2436 MWt);

Rev. No. O Page 7 - of 26

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c. I J NEW, YORK POWER AUTHORITY ~

JAMES A. FITZPATRICK NUCLEAR POWER PLANT ,

p .' - CORE OPERATING UMITS REPORT W = recirculation flow in percent of rated; ,

AW = difference between two loop and single loop effective drive flow at the same core flow.

7.4.2.3 in the event of operation with a maximum fraction of limiting . '

power density (MFLPD) greater than the fraction of rated power

l. (FRP), the setting shall be modified as follows:

SS (0.66W + 42%) (FRP/MFLPD) for two loop operation; I S5 (0.66W + 42% 0.66 AW) (FRP/MFLPD) for single loop ,

operation; "

where:

FRP = fraction of rated thermal power (2436 MWt);

MFLPD = maximum fraction of limiting power density as specified in Table 8.2.

l l' 7.5 RBM Flow Blased Rod Block Setting 7.5.1 Technical Specification

Reference:

3.2.C.1 7.5.2 The RBM flow biased rod block trip setting shall be:

S50.66W + K for two loop operation; S10.66W + K - 0.66 AW for single loop operation; where:

l

' i' S = rod block setting in percent of initial; W = loop flow in percent of rated K = Intercept values of 39%,40%,41%,42%,43%,and44% can be used with l the appropriate MCPR Operating Umit from Table 8.1.a through d; AW = difference between two loop and single loop effective drive flow.

Rev. No. O Page 8 of 26

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l J NEW YORK POWER AUTHORITY l JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING UMITS REPORT l a 8.0 FIGURES AND TABLES Table 8.1.a MCPR Operating Umit for incremental Cycle Core Average Exposure: BP8x8R 3

Table 8.1.b MCPR Operating Umit for incremental Cycle Core Average j Exposure: GE8x8EB ,

Table 8.1.c MCPR Operating Umit for incremental Cycle Core Average Exposure: GE8x8NB 3

. Table 8.1.d MCPR Operating Umit for incremental Cycle Core Average Exposure: GE11LTA  !

Table 8.2 Maximum LHGR Figure 8.1.a MCPR Operating Umit Versus r: BP8x8R Figure 8.1.b MCPR Operating Umit Versus r: GE8x8EB l Figure 8.1.c MCPR Operating Umit Versus r: GE8x8NB-3 Figure 8.1.d MCPR Operating Umit Versus r: GE11LTA Figure 8.2 K, Factor Figure 8.3.a MAPLHGR Versus Planar Average Exposure:  !

BP8DRB299, OUAD+

Figure 8.3.b MAPLHGR Versus Planar Average Exposure: BD319A L Figure 8.3.c MAPLHGR Versus Planar Average Exposure:

BD336A e Figure 8.3.d MAPLHGR Versus Planar Average Exposure: ,

BD339A .

Figure 8.3.e MAPLHGR Versus Planar Average Exposure:

GE10 P8HXB32211GZ-70M 150 T Figure 8.3.f MAPLHGR Versus Planar Average Exposure:

GE10-P8HXB324-12GZ-70M 150T l Figure 8.3.g MAPLHGR Versus Planar Average Exposure:

89LTA l 9.0 EXHIBITS 1

i Not applicable.

i Rev.No.0 Page 9 - of 26

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NEW YORK POWER AUTHORITY ,

JAMES A. FITZPATRICK NUCLEAR POWER PLANT  !

CORE OPERATING UMITS REPORT ,

i TABLE 8.1.a A

~

MCPR Operating Umit for incremental Cycle 3 Core Average Exposure for BP8X8R 4 AT RBM Hi Trip BOC to EOC 2GWD/t to EOC 1GWD/t Level Setting EOC-2GWD/t EOC 1GWD/t to EOC_

S = 0.66W + 39% 1.26 1.29 1.32 '

S = 0.66W + 40% 1.26 1.29- 1.32 S = 0.66W + 41% 1.28 1.29 1.32 S = 0.66W + 42% 1.30 1.30 1.32 i S = 0. 66W + 43% 1.33 1.33 1.33 i S = 0.66W + 44% 1.35 1.35 1.35 Technical Specification

Reference:

3.1.B i For single loop operation, these limits shall be increased by 0.01.

1 Rev. No. O Page 10 of 26

1. NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING UMITS REPORT TABLE 8.1.b L

MCPR Operating Umit for incremental Cycle Core Average Exposure for GE8X8EB At RBM Hi Trip BOC to EOC-2GWD/t to EOC 1GWD/t Level Setting EOC 2GWD/t EOC 1GWD/t to EOC S = 0.66W + 39% 1.27. 1.30 1.32 S = 0.66W + 40% 1.27 1.30 1.32 i S = 0.66W + 41% 1.28 1.30 1.32 S = 0.66W + 42% 1.30 1.30 1.32 S = 0.66W + 43% 1.33 1.33 1.33 S = 0.66W + 44% 1.35 1.35 1.35 Technical Specification

Reference:

3.1.B For single loop operation, these limits shall be increaseo by 0.01.

1 I

Rev. No. 0 Page 11 of 26 ew,

3 NEWYORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING UMITS REPORT TABLE 8.1.c MCPR Operating Umit for incremental Cycle Core Average Exposure: GE8X8NB 3 At RBM Hi Trip BOC to EOC-2GWD/t to EOC 1GWD/t Level Setting EOC-2GWD/t EOC-1GWD/t to EOC S = 0.66W + 39% 1.31 1.31 1.33 S = 0.66W + 40% 1.31 1.31 1.33 S = 0.66W + 41% - 1.31 1.31 1.33 S = 0.66W + 42% 1.31 1.31 1.33 S = 0.66W + 43% 1.32 1.33 1.33 1

S = 0.66W + 44% 1.33 1.33 1.33 Technical Specification

Reference:

3.1.B For single loop operation, these limits shall be increased by 0.01, i.

l- Rev. No. 0 Page 12 - of 26 L

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4:;

NEWYORK POWER AUTHORlW l

JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING UMITS REPORT TABLE 8.1.d I. MCPR Operating Umit for incrernental Cycle h Core Average Exposure: GE11LTA At RBM Hi Trip BOC to EOC-2GWD/t to EOC 1GWD/t Level Setting EOC-2GWD/t EOC 1GWD/t to EOC i S = 0.66W + 39% 1.34 1.37 1.42 S = 0.66W + 40% 1.34 1.37 1.42 S = 0.66W + 41% 1.34 1.37 1.42 1

, S = 0.66W + 42% 1.34 1.37 1.42 S = 0.66W + 43% 1.34 1.37 1.42 l S = 0.66W + 44% 1.35 1.37 1.42 Technical Specification

Reference:

3.1.B For single loop operation, these limits shall be increased by 0.01.

! .I l

l l

Rev. No. 0 Page of 26 i

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT TABLE 8.2 Maximum LHGR Fuel Type Fuel Bundle Design Maximum LHGR (kw/ft) -

BP8DRB299 BP8x8R 13.4 OUAD+ QUAD + 13.4 BD319A GE8x8EB 14.4 BD336A GE8x8EB 14.4 BD339A GE8x8EB 14.4 GE10 P8HXB322 GE8x8NB 3 14.4 11GZ 70M 150-T

' GE10-P8HXB324 GE8x8NB-3 14.4 12GZ 70M 150 T 88LTA GE11LTA 14.4 Technical Specification

Reference:

3.5.1 l

Rev.No.0 Page 14 of 26

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i' -C .

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT

.. CORE OPERATING UMITS REPORT 4

FIGURE 8.1.a -

MCPR Ope.ating Umit Vorsus r: BP8X8R 1.4 1.38 -

N 3 1.36 -

M

-w U 1.34 - EOC 2.

b EOC-1 g 1.33 c

/y

'= / /

/

E O

g 1.3 -

EOC--y f 1.28 -

1.26 1.24 0 0.2 0.4 0.6 0.8 1 T

Technical Specification

Reference:

3.1.B For single loop operation, these limits shall be increased by 0.01.

- Rev. No. O Page 15 of 26

• NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT

_,, CORE OPERATING UMITS REPORT FIGURE 8.1.b MCPR Operating Umit Versus r: GE8X8E8 ^

1,4 '

1.38 -

1'36 ~

e t 1,34 . EOC

// '

?. / <

b 1.32 E C-1 e

~$

o 1 .3 EOC- /

Y' 1.28

/[

1.26- -

1 1.24 '

0 0.2 0.4 0.6 0.8 1 T

Technical Specification Reference 3.1.8

.For single loop operation, these limits shall be increased by 0.01.

Rev. No. O Page 16 of 26

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• NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT

.. CORE OPERATING LIMITS REPORT i

I FIGURE 8.1.c MCPR Operating Umit Versus r: GE8X8NB 3 1.4 1.38 -

1.36 - I g EOC b 1.34 ' --

i 3 EOC-

{

'E  !

O 1.32 -

w i EOC '

g, 13 '

/

o .{

,/ ,

1.28 -

1.26 - ,

i 1.24 -

I i

0 0.2 0.4 0.6 0.8 1 T .;

Technical Specification

Reference:

3.1.8 For single loop operation, these limits shall be increased by 0.01.

Rev. No. 0 Page 17 - of 26 1:

r; 5 e 1

[ '4 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT.

5 *.

CORE OPERATING UMITS REPORT

+

FIGURE 8.1.d l ', MCPR Operating Umit Versus r: GE11LTA I

.1.5 i

1,48

[ci! 1.46 -

I EOC i(a. (1A4 -

v 2

.* 1.42 E

d

.g 1.4 -

EOC-3o i

@ 1.38 EOC-2

-1.36 -

/

1.34 1.32 0 0.2 0.4 0.6 0.8 1 7

l Technical Specification

Reference:

3.1.8 For single loop operation, these limits shall be increased by 0.01.

l Rev. No. O Page 18 of 26

NEWYORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT

.. CORE OPERATING UMITS REPORT 1.4 i

r l

u 1.8 = -

i i

1J =

Aantaaste sulme commun, --

Kg e

i ., .  ;

teemuat Mlap p M 1WW 840lestanAA a 103.6%

10, 0%

1.0 = 113.0% E u , D.

09 i a n ,

a 30 a0 60 e4 70 00 88 100 CORE PLo,; ( g )

FIGURE 8.2 Kg Factor  :

Technical Specification

Reference:

3.1.8 Rev. No. 0 Page 19.of 26

i O NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING UMITS REPORT FIGURE 8.3.a MAPLHGR Versus Planar Average Exposure: BP8DRB299, QUAD +

'13 12.5 -

12 -

, 11.5 -

G v 11 -

E

] 10.5 2 10 -

9.5 -

s

\

8.5 '

O 10 20 30 40 50 Planar Average Exposure (GWd/ST)

This curve represents the limiting exposure-dependent MAPLHGR values.

Technical Specification

Reference:

3.5.H

Reference:

NEDO-21662 2 Amended December 1984, WCAP 11159 _

For single loop operation, these MAPLHGR values shall be multiplied by 0.84.

Rev. No. 0 Page 20 of 26

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• NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLE.AR POWER PLANT

. CORE OPERATING LIMITS REPORT FIGURE 8.3.b MAPLHGR Versus Planar Average Exposure: BD319A 13 -

, . - ss

'N .

p N n

11 -

n g 10 -

E \

19- N 8 -

N 1

7 -

6 ,

i 0 10 20 30 l

.t0 50 Planar Average Exposure (GWd/ST)

This curve represents the limiting exposure dependent MAPLHGR values.

Technical Specification

Reference:

3.5 H

Reference:

NEDC 31317P For single loop operation, these MAPLHGR values shall be multiplied by 0.84.

Rev. No. O Page . 21 of 26

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.3.c MAPLHGR Versus Planar Average Exposure: BD336A 14 13 -

/

12 -

ll

• e

.5

- 10 -

M 2

39 -

Q 2 8 -

7-i 6-  !

5 0 10 20 30 40 50 Planar Average Exposure (GWd/ST)

{

I This curve represents the limiting exposure dependent MAPLHGR values.

Technical Specification

Reference:

3.5.H

Reference:

NEDC 31317P For single loop operating these MAPLHGR values shall be multiplied by 0.84.

i Rev. No O Page 22 of 26

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• NEWYORK POWER AUTHORITY JAtaES A. FITZPATRICK NUCLEAR POWER PLANT

. CORE OPERATING UMITS REPORT FIGURE 8.3.d MAPLHGR Versus Planar Average Exposure: BD339A -

14 13 -

/

12 -  !

g li b

~ 10 -

M 2

• ] 9 -

k 2 g _

7 -

i i

6 -

5 O 10 20 30 40 50 Planar Average Exposure (GWd/ST) 4 i

This curve represents the limiting exposure dependent MAPLHGR values.

Technical Specification

Reference:

3.5.H

Reference:

NEDC 31317P For single loop operating these MAPLHGR values shall be multiplied by 0.84.

Rev. No. O Page 23 of 26

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' NEW YORK POWER AUTHORITY JAMES A. FIT 2 PATRICK NUCLEAR POWER PLANT

. ORE OPERATING UMITS REPORT FIGURE 8.3.e MAPLHGR Versus Planar Average Exposure:

GE10 P8HXB32211GZ 70M 150-T 14 13 -

..N 12 -

,11 y' 6

.6

- 10 -

ed 9

3 9 -

k 2 8 - i 7 -

6-5 .

O 10 20 30 40 50 (4 Planar Average Exposure (GWd/ST) i i

This curve represents the limiting exposure  !

dependent MAPLHGR values.

Technical Specification

Reference:

3.5.H

Reference:

NEDC 31317P For single loop operating those MPLHGR values shall be muhlplied by 0.64.

- Rev. No. 0 Page 24 of 26 i

o a NEW YORK POWER AUTHORITY i JAMES A. FITZPATRICK NUCLEAR POWER PLANT  ;

CORE OPERATING UMITS REPORT '

FIGURE 8.3.f i

MAPLHGR Versus Planar Average Exposure:

GE10 P8HXB32412GZ 70M 150T 14 f 13 -

s 12 -

11 -

c:

1

- 10 -

ed 3

39 -

k 2 8 -

7-

\\

6--

k 5 ' '

O 10 20 30 40 50 60

• Planar Average Exposure (GWd/5T)

This curve represents the limiting exposure dependent MAPLHGR values.

Technical Specification

Reference:

3.5.H

Reference:

NEDC 31317P For single loop operating these MAPLHGR values shall be muhlplied by 0.84 Rev. No. O Page 25 of 26

i

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'c' NEW YORK POWER AUTHORITY JAMES A. FIT 2 PATRICK NUCLE.AR POWER PLANT -

=,

CORE OPERATING UMITS REPORT FIGURE 8.3.g MAPLHGR Versus Planar Average Exposure: 89LTA 13 12 -

11 2

10 -

M 9 ,

a m 9 -

2 8 - -

7-6 '

0 10 20 30 40 50 (4 Planar Average Exposure (GWd/ST) i l

1 i

This curve represents the limiting exposure L dependent MAPLHGR values.

l- Technical Specification

Reference:

3.5.H

Reference:

NEDC 31317P For single loop operating these MAPLHGR values shall be multiplied by 0.84.

l l

Rev No.O Page 26 of 26 i

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