ML20106B024

From kanterella
Jump to navigation Jump to search
Rev 1 to Ja Fitzpatrick Nuclear Power Plant Colr
ML20106B024
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 08/26/1992
From:
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
Shared Package
ML20106B021 List:
References
NUDOCS 9209300241
Download: ML20106B024 (33)
v • d • e


Text

_

.~.

4 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT CONTROLLED CdPY

[3 CONTROLLED REVIEWED BY: Plant Operations Review Committee Meeting No. 9 2 - 0 8 6 Date 07/22/92 m

0IO7'A APPPOVED BY:

v2

_(

. 3eC Date Reactor Analyst Supervisor

/4!TL APPROVED BY:

8 7

Date

/ Resident' Manager V

Page No.

1 2

3 4

5 6

7 8

Rev No.

I 1

1 1

1 1

1 1

Page No.

9 10 11 12 13 14 15 16 Rev. No.

I 1

1 1

1 1

1 1

Page No.

17 18 19 20 21 22 23 24 Rev. No.

I 1

1 1

1 1

1 1

Page No.

25 26 27 28 29 30 31 32 Rev. No.

I 1

1 1

1 1

1 1

Page No.

33 Rev. No.

1 Page 1 of 33 Rev. No.1 9209300241 920923 PDR ADOCK 05000333 P

PDR 7

,~

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT

. m -.

1.0 PURPOSE This report provides the cycle-specific operating limits for Cycle 11 of the James A. FitzPatrick Nuclear Power Plant. The following limits are addressed:

Operating Limit Minimum Critical Power Ratio (MCPR)

Flow Dependent MCPR Limits Maximum Averag: Planar Linear Heat Genention Rate (MAPLHGR)

Linear Heat Generation Rate (LHGR)

Flow-Biased Average Power Range Monitor (APRM) and Rod Block Monitor (RBM) Settings 2.0 APPLICABILITY The plant must be operated within the limits specified in this report. If any of t' ese limits are violated, the cornetive actions specified in the Technical Specifications must be taken.

3.0 REFERENCES

3.1 JAFNPP Administrative Procedure 7.2, Control of Core Operating Limits Report.

3.2 JAFNPP License Appendix A, Operating Technical Specifications.

3.3 FitzPatrick Cycle 11 Reload Safety Evaluation. JAF-SE-92-125 l

l 3.4 Gell Lead Test Assembly Report.

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

i 3.6 Supplemental Reload Licensing Submittal for JAFNPP Reload 10 Cple 11, GE Report 23A7114 June 1992. Includes a Supplement I containing MAPLHGR DATA.

3.7 Cycle 11 Reload Core. F1-91-252.

l Rev. No.1 Page 2 of 33 l

l l

NEW YORK POWER AU THORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT 4.0 DEFINITIONS Minimum cntical power ratio (MCPR) Minimum value of the ratio of that power in a 4.1 fuel 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 the GEXL correlation (Reference NEDE-10958).

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

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

Rated Recirculadon Flow - that drive flow which produces a core flow of 77.0 x 106 4.4 lb/hr.

5.0 PESPONSID1LEDES 5.1 See AP-7.2 (Reference 3.1).

It is the responsibility of the Shift Supervisor to assure that the reactor is operated 5.2 within the limits described herein.

6.0 SPECIAL INSTRUCTIONS /REOUIREhiENTS Not applicable.

1 Page 3 of 33 Rev. No.1

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT 7.0 PROCEDURE 7.1 Operating Limit MCPR During power operation, The Operating Limit MCPR shall be equal to or greater than the limits given below.

7.1.1 Technical Specification

Reference:

3.1.B 7.1.2 The Operating Limit MCPR shall be de... mined based on the following requirement:

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

f ve $ r.

4 7.1.2.2 The average scram time to notch position 38 is determined as follows:

n E N r.

i t i=1 A VE n

E N.I i=1 where:

n=

number of surveillance tests performed to date in the

cycle, i

N, =

number of active rods measured in the,th surveillance, and 7, =

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

i i

Rev. No.1 Page 4 of 33 l

.~-.

i I

I NEW YORK POWER AUTilORITY J AMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING L.MITS REPORT 7.1.2.3 The adjusted analysis mean scram time is calculated as follows:

N '

i/2 r, (sec) =

+ 1.65 o n

E N, 1-n where:

mean of the distribution for the average scram insertion

=

, 38 = 0.706 sec.

time to the pickup of notch positio.

standard deviation of the distribution for average scram a=

insertion time to the pickup of notch position 38 = 0.016 m.

N=

the total number of active rods measured in Technical Specification 4.3.C.I.

n The number of rods to be scram tested and the test intenals are given in Technical Speci6 cation 4.3.C.

7.1.3 When requiren'ent of 7.1.2 is met, the Operating Limit MCPR shall not be less than that speci6cd in Tables 8.1.a through d.

72.4 When the requirement 7.1.2 is not met (i.e. r, < r in) then the Operating Limit MCPR values (as a function of r) are given in Figures 8.1.a through d, where r = (ran-r.)/(r,-r.)

and the average scram time to notch position 38 as defined in 7.1.2.2.

7n=

4 the adjusted analysis mean scram time as defined in 7.1.2.3

=

r, the scram time to noten position 38 as defined in Technical

=

rx Specification 3.3.C.I.

Page 5 of 33 n

Rev. No.1 i

_6

__________.-_________m..

NEW YORK POWER AUTHORITY J AMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT 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 Li. nit MCPR shall be increased by 0.01, 7.1.6 During reactor power operation with core flow less than 100 percerat of rated, the Operating Limit MCPR shall be multiplied by the appropnate K, specified in Figure 8.2.

7.2 Maximum Averap Planar Linear Heat Generation Rate (MAPLHGR) 7.2.1 Technical Specification

Reference:

3.5.H 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 applicable APLHGR limit values which have been approved for the respective fuel and lattice types.

7.2.3 When aand 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 l

through h.

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

7.3 Linear Heat Generation Rat-fDIGR) 7.3.1 Technical Specification

Reference:

3.5.1.

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

Rev. No.1 Page 6 of 33

e 4

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT 7.4 APRM Trip Settings 7.4.1 APRM Flow Referenced Flux Scram Trip Setting (Run Mode) 7.4.1.1 Technical Specification

References:

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

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

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

7.4.1.3 In the event of operation with a maximum fraction of limiting powe-density (MFLPD) greater than the fraction of rated power (FRP), the setting shall be modified as follows:

S1(0.66W + 54%)(FRP/MFLPD) for two loop operation; S1(0.66W + 54% - 0.66 AW)(FRP/MFLPD) for single-loop operation; where:

fraction of rated thermal power (2436 Mwt);

FRP

=

MFLPD = Maximum fraction oflimiting power density, where the limiting pcwer density is as specified in Table 8.2.

'Ihe ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less th*.n the design value of 1.0, in which case the actual operating value will be used.

Rev. No.1 Page 7 of 33

- _.. ~ _ -

NEW YORK POWER AUTHORITY JASES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT I

7.4.2 APRhi Flow Biased Rod Block Setting 7.4.2.1 Technical Specification

References:

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

7.4.2.2 The APRM rod block trip setting shall be:

S10.66W + 42% for two loop operation; S50.66W + 42% - 0.66 AW for single loop operation; where:

S = rod block setting in percent of rated thermal power (2436 i

Mwt);

W= recirculation ficw 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 (FRP), the setting shall be modified as follows:

SA(0.66W + 42%)(FRP/MFLPD) for two loop operation; S1(0.66W + 42% 0.66AW)(FRP/MFLPD) for single loop operation; where:

FRP = fraction of rated thermal po.ver (2436 Mwt);

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

Page 8 of 33 Rev. No.1

4 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT 7.5 RBM Flow Biased Rod Block Setting 7.5.s Technical Specificatior.

Reference:

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

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

S = md block setting in percent of initial; W = loop flow in percent of rated K = intercept values of 39 %, 40%, 41 %, 42 %, 43 %, and 44% can be used with the appropriate MCPR Operating Limit from Table 8.1.a thmugh d; AW = difference between two loop and single loop effective drive flow.

Rev. No.1 Page 9 of 33

- -w t

+-

~v,u.

m -

r,,

s_%,-+

r.-

i we

NEW YORK POWER AlifHORITY JAMES A. FITZPATRICK NUCi. EAR POWER PLANT CORE OPERATING LIMITO REPORT S.0 FIGURES AND TABLES Table 8.1.a MCPR Operating Limit for incremental Cycle Core Average Exposure:

GE8x8EB Table 8.1.b MCPR Operating Limit for incremental Cycle Core Average Exposure:

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

GEllLTA Table 8.1.d MCPR Operating Limit for Incremental Cycle Core Average Exposure:

Gell Table. 8.2 Maximum LHGR i

Fig.are 8.1.a MCPR Operating Limit Versus 7: GE8;8EB Figure 8.1.b MCPR Operating Limit Versus r: GE8x8NB-3

$igure 8.1.c MCPR Operating Limit Versus r: GElILTA Figure 8.1.d MCPR Operating Limit Versus r: gel 1 Figure 8.2 K, Factor i

Figure 8.3.a MAPLHGR Versus Planar Average Exposuic: BD319A Figure 8.3.b MAPLHGR Versus Planar Average Exposure: BD336A Figure 8.3.c MAPLHGR Versus Planar Average Exposure: BD339A i

'?igure 8.3.d MAPLHGR Versus Planar Average Exposure:GE10-P8HXB327-1IGZ-70M-150-T Fip.ure 8.3.e MAPLHGR Versus Planar Average Exposure:GE10-P8HXB324-12GZ -

70M-15(TT i

Page 10 of 33 Rev. No.1

NEW YORK POWER AUTHORITY JAhtES A. FITZPATRICK NUCLEAR POWER PLANT s

CORE OPERATING LIh11TS REPORT Figure 8.3.f hiAPLHGR Versus Planar Average Exposure: 89LTA Figure 8.3.g hiAPLHGR Versus Planar Average Exposure: gel 1-P9 HUB 356-55GZ-o 100hi-146T Figure 8.3.h hfAPLHGR Versus Planar Average Exposure: Gell-P9 HUB 359-16GZl-100ht-146-T Figure 8.4.a CYCLE 11 LOADING PATTERN, UPPER IIFT QUADRANT, BUNDLE DESIGN Figure 8.4.b CYCLE 11 LOADING PATTERN, UPPER RIGHT QUADRANT, BUNDLE DESIGN Figure 8.4.c ( '(' '.E 11 LOADING PATTERN, LOWER RIGHT QUADRANT, Bui4DLE DESIGN Figure 8,4.d CYCLE 11 LOADING PATTERN, LOWER LEFT QUADRANT, BUNDLE DESIGN 9.0 EXHIBITS Not Applicable.

Rev. No.1 Page 11 of 33 l

i NEW YORK POWER AUTHORITY J

JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT TABLE 8.1.a MCPR Operating Limit for incremental Cycle Core Average Exposure for GE8x8EB At RBM Hi-Trip BOC to 9000 GWD/t to 10250 GWD/t Level Setting 9000 GWD/t 10250 GWD/t to EOC S = 0.66W + 39%

1.26 1.26 1.27 S = 0.66W + 40%

1.26 1.26 1.27 S = 0.66W + 41 %

1.27 1.27 1.27 S = 0.66W + 42 %

1.27 1.29 1.29 S = 0.66W + 43%

1.31 1.31 1.31 S = 0.66W + 44 %

l.31 1.31 1.31 l

Technical Specification

Reference:

3.1. 8 For single loop operation, these limits shall be increased by 0.01.

Rev. No.1 Page 12 of 33 i

I-

l NEW YO.'V POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING 1.lMITS REPORT TABLE 8.1.b MCPR Operating Limit for Incremental Cycle Core Average Exposure: GE8x8NB-3 At RBM Hi-Trip l BOC to 9000 GWD/t to 10250 GWD ~t Level Setting 9000 GWD/t 10250 GWD/t to EOC S = 0.66W + 39%

!.31 1.31 1.31 S = 0.66W + 40%

1.31 1.31 1.31 S = 0.66W + 41 %

1.31 1.31 1.31 S = 0.66W + 42 %

1.31 1.31 1.31 F = 0.66W + 43 %

1.31 1.31 1.31

, S = 0.66W + 44 %

1.32 1.32 1.32 Technical Specification

Reference:

3.1.B Fcr single loop operation, these limits shall be inctrased by 0.01.

Rev. No.1 Page 13 of 33

.~.

NEW YOAK POWER iM1110RITY U MES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT TABl.E 8.1.c MCPR Operating Limit for incremental Cycle Core Average Exposure: GEllLTA At RBM Hi-Trip BOC to 9000 GWD/t 10250 GWV/t level Setting 9000 GWD/t 10250 GWD/t to EOC S = 0.66W + 39%

1.30 1.30 1.34 S = 0.66W + 40%

1.30 1.30 1.34 S = 0.66W + 41 %

1.30 1.30 1.34 S = 0.66W + 42%

1.30 1.30 1.34 S = 0.66W + 43 %

1.30 1 30 1.34 S = 0.66W + 44 %

1.30 1.30 1.34 Technical Specification

Reference:

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

I i

Page 14 of 33 Rev. No.1

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT TABLE 8.1.d MCPR Operating Limit for Incremental Cycle Core Average Exposure: Gell At RBM Hi Trip BOC to 9000 GWD/t 10250 GWD/t l

level Setting 9000 GWD/t 10250 GWD/t to EOC S = 0.66W + 39%

1.33 1.35 1.38 S = 0.66W + 40%

1.33 1.35 1.38 S = }.66W + 41 %

1.33 1.35 1.38 S = c. MW + 42 %

1.33 1.35 1.38 S = 0.66W + 43 %

1.33 1.35 1.38 S = 0.66W + 44 %

1.33 1.35 1.38 Technical Specification Refuence: 3.1.B For single loop operation, these limits shall be increased by 0.01.

L

\\

s Rev. No.1 Page 15 of 33

_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ _Y-___- _

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT j

TABLE 8.2 Maximum LHGR Fuel Type Fuel Bundle Design Maximum LHGR (kw/ft)

BD319A GE8x8EB 14.4 BD336A GE8x8EB 14.4 BD339A GE8x8EB 14.4 GE10-P8HXB322 GE8x8NB-3 14.4 1 IGZ-70M-150-T GE10-P8HXB324 GE8x8NB-3 14.4 12GZ-70M-150-T 4

89LTA GElILTA 14.4 4

gel 1-PSXUB356 gel 1 14.4 15GZ-100M-146-T gel 1-P9 HUB 359 gel 1 14.4 16GZ1-100M 146-T Technical Specification

Reference:

3.5.1 i

l L

l Rev. No. -l Page 16 of 33

,,..,.,,__.,__.,._.__a,_,_,__.__,,

NEW Y'JRK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.1.a MCPR Operating Limit Versus r (TAU): GE8x8EB l

l 1,36 1.J6 j

1.35 1.35 1 34

1. e4 l
  • 33 1 33 1.32

's.12 1 31 1 31 3.2 1.3

{

{

i.23

,.a.

1.2e e

g 1.2e 3

1.27 1.27 4...

r g

s 4.as 4.rs

}

}

3.2.

,.e4 i.23

, 23 s.22 1.r2 1.21 1.21 s.e 3.2 1

0 TAU C

BJC-9000

+ 9000 10230 o 10250-50C Technical Specification Reference 3.1.B For single loop operation, these limits shall be increased by 0.01.

l i

1 i

Rev. No.1 Page 17 of 33

4 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPE. TING LIMITS REPORT i

FIGURE 8.1.b MCPR Operating Limit Versus r (TAU): GE8x8NB 3 l

1 37 1.37 1 36 4

1.36 1.35 1.35

1. y 1 }1 1 33 1 33 i

1.32 1,32 1.?1 1,31 1.3 g

1 S

1.29 1,29 2

1.28 A -

1,29 1.21 1.21

-E 1.26 1.26

{'

$ 25 1 25 1.24 1.24 1.23 1.23 1.22 1.22 1.21 1.21 1.2 1.2 TAU O

EOC-9000

+

9000-102S0 o 102 W ECC Technical Specification

Reference:

3.1.B

(

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

Rev. No.1 Page 18 of13 I -

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.1.c MCPR Operating Limit Versus r (TAU): GEllLTA 1 43 1 43 i,42 1.42 1.41 1.41 1.4 1.4 1 !9 1 39 1.38

1. 38 1.37 1.37 1.36
1. 36 1 35 1.35
1. 34 y

y 1.34

}

{

1.33 1.33 5.n

,.32 g

g g

4.34 2.31 3

1.3 1,3 1.as

- 1. a 1.29 1.29 1.27 1.27 1.26 1.26 1.25 i,25 0

1 TAU 0 00C-9000

+ 9004 10210 o iO2 W EOC Tecitnical Speci6 cation

Reference:

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

Rev. No.- 1 Page 19 of 33 w

g

.r

- -,n.

-.,.-,n,n,

~,

n w

n

I NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.1.d MCPR Operating Limit Versus r (TAU): Gell 1 47 i 47 4 46 -

1.46 4 4s -

4.s g

1 44 i 44 -

1 4) 1 43 1 42 i e2 1.41 1.41 V

,.4 V

,.4 j

j 1.2e

, w

3. 2a i 2e g

g 3.2)

- 3.22

- 3.26 1 36 1.25 - /

- 3.2s

- 1. 34 1.24

- 1.33 1.33

1. 32 1.32 TAU O

DOC-WGCR)

+

90CD-10250 0

40250- EUC Technical Specification

Reference:

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

Page 20 of 33 Rev. No. I

4 -

A.

9 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.2 K, Factor 9.4 o

- \\.

u t

u

- w cor=x ch"O m e w w n ma an ior n 101 0%

na n io 111.0 %

gg i*t 1

1-I i

w

<o ao so in eo so

,oe ce=, c..,

-1 Technical Specification

Reference:

3.1.B Rev. No.1 Page 21 cf 33

3 NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.3.a MAPLHGR Versus Planar Average Exposure: BD319A 14 00 13 00 12.00 11.00 10.00 9.00 B.00 f

7.00 E 00 g

3.00 4.00 3,00 2.00 1 00 0

10 2G 40 50 60 Platur Average EnroeweCGrQ/t)

This curve represents the limiting exposure dependent M/.PLHGR values.

i Technical Specification

Reference:

3.5.H

Reference:

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

Rev. No.1 Page 22 of 33 1

{--

~

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.3.b MAPLHGR Versus Planar Average Exposure: BD336A 14 00 ----

13 00 -

12.00 -

11 00 10,00 -

9.00 0 00

(

7.00 E 00 g

5.00 4 00 3.00 2.00 1 00 0

10 20 40 50 60 planer Averson Enoueu e<GMVt)

This curve represents the limiting exposure dependent MAPLHGR values.

Technical SpeciFcation Refer-nce: 3.5.H Rcference: NEDC-31317P For single loop operating these MAPLHGR values shall be multiplied by 0.84.

Page 23 of 33 Rev. No.1

O 1

~

NEW YORK POWER AUTHORrrY JAMES A. FITZ!'ATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.3.c MAPLHGR Versus Planar Average Exposure: BD339A i

14 00 13.00 -

12 00 -

ii 00 10.00 -

9.00 9.00 h

7.00 b

s ao i

g 5.00 3

4.00 3.00 2.00 1 00 0

TO 20 40 50 60

- - o This curve represents the limiting exposure

~

dependent MAPLHGR values.

Technical Specification

Reference:

3.5.H Refuence: NEDC-31317P For stagle loop operating these MAPLHGR values shall be multiplied by 0.84 Rev. No.1 Page 24 of 33

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMTTS REPORT FIGURE 8.3.d MAPLHGR Versus Planar Average Exposure:

GE10-P8HXB322-1IGZ-70M-150-T i4. OL 13.00 42.00 11 00 10.00 9.00 0.00 7.00 i

s.00 g

S.00 4.00 3.00 2.00 1 00 0

10 20 30 40 50 60 0,_.~.---

This curve represents the limiting exposure dependent MAPLHGR values.

Technical Specification

Reference:

3.5.H

Reference:

NEDC-31317P For single loop operating these MPLHGR values shall be multiplied by 0.84 Rev. No.1 Page 25 of 33

{

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.3.e MAPLHGlt Versus Planar Average Egosure:

GElf P8HXB32412GZ-70M-15GT c

14 (

13 00 12.00 11 00 10.00 9.00 9 00

{

7,00 6 oc 5.00 4.00 3.00 3.00 1 00 i ~

0.00 O

10 20 30 40 50 60 Planer Averson EmpoeiroCoeWt) his 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.

Page 26 of 33 Rev. No.1

~

NEW YORK POWER AUTHORITY JAMES A. FITZPA1 RICK NUCLEAR POWER PLANT CORE OPER/

NG LIMITS REPORT

+

c.

FIGURE 8.3.f

?jk 4 e 1, ~ -

Me.PLHGR Vereus Planar Average Exposure: 89LTA

.y 8t -'

13 00 12.00 11 00 'p G

10.00 -

. no -

t uo

\\

g f

8,00 X

5.00 I

4.00 3.00 2.00 1.u0

' O 10 20 40 50 CO

..... u-n o This curve represents the limiting exposure dependent MAPLHGR values.

Technical Specification

Reference:

3.5.H Referenx: NEDC-31317P For single loop operating these MAPLHGR values shall be multiplied by 0.84.

Page 27 of 33 Rev. No.

_. e mods

NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.3.g MAPLHGR Versus P'anar Average Exposure: Gell-P9 HUB 356-15GZ-100M-146-T a

12 00 l

11 00 -

N

/

10 00 -

9.00 -

e.00 7 00 6<00 5.00 4.00 3.00 3 00 1.00 0

10 20 30 50 60 P f arter Averags Est33casse(Ov0/n This curve represents the limiting exposure 7

dependst MAPLHGR values.

Technical Specification i.eference: 3.5.H

Reference:

A23A71?4 Rev 1 For single loop operating these MAPLHGR values shall be multiplied by 0.84.

Page 28 of 33 Rev. No.1 i

.. ~

NEW YORK POWER AUTHORITY JAMES A FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT FIGURE 8.3.h MAPLHGR Versus Planar Average Exposurr Gell-P9 HUB 35916GZl-100M-146-T 12.00 11.00 t'. 00 y' 4

9.00 8.00 7 00 t) 6.00 5

s.00 g

(

4.00 2

3.00 3 CD 1.00 0

10 20 40 50 60 p i. n.e * -.o. a oo. <. cc e st3 l

l l

l l

This curve represents the limiting exposure l

dependent MAPLHGR values.

l I

Technical Specification

Reference:

3.5.H

Reference:

23A7114 Rev 1 For single loop operating these MAPLMGR values shall be multiplied by 0.84.

l l

Page 29 of 33 Rev. No.1

4

' I NEW YORK POWER ALT 1HORrfY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT-l A

A A

A

.A 52 A

A B

B.

B B

50 A

A A

A B

D B

D B

48

)

A A-B B

B D.

B D

A D

.46

-D A

44 B

A A

A A

B D

A A

A B

A A

D

'B A

A D

B A

42 l

i A

B B

D A

D-B D

A.

D A

40 A

A B-D B-D B

D A

D B-D 38 A

A B

D A

A B

D A

A A

D A

36 A

C D

B' A

A D

A A.

A D

B A-34

-A B

B-D B

D A

D A

D A

D A

32 A

B D

A~

D.

B D.

B D

B D

A D

30 A

B B

D A

'A A

D A

A A

D A

28 s

01 03 05 07 09 11 13 15 17 19 21 23 25

' ~

FIGURE 8.4.a i-CYCLE 11 LOADING PATTERN, UPPER LEFT QUADRANT, BUNDLE DESIGN A = GE8x8EB, Bundle Types BD319A, BD336A, BD339A B = GE8x8NB-3, Bundle Types P8HXB322, P8HXB324 C = GE11LTA, Bundle Type 89LTA D-= Gell, Bundle Type P9 HUB 356, P9 HUB 359 n

Rev. No.1 Page 30 of 33

n NEW YORK POWER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT h

52 A

A A

A A

3 l

50 B

B B

B A

A 48 B

D B

D B

A A

A A

46 D

A D

B D

B B

B A

A 44 A

D B

A A

D B

A A

A A

42 A

B D

A A

3 D

A A

B A

40 A

D A

D B

D A

D B

B A

38 D

b D

A D

B D

B D

B A

A 36,A D

A A

A D

B A

A D

B A

A 34 A

B D

A A

A D

A A

B D

C A

32 A

D A

D A

D A

D B

D B

B A

30 D

A D

B D

B D

B D

A D

B A

^

..d__ _A A

A D

B B

A d,[

A m

27 29 31 33 35 37 39 41 43 45 47 49 51 FIGURE 8.4.b CYCLE 11 i OADING PATTERN, UPPER RIGHT QUADRANT, BUNDLE DESIGN A = GE8x8EB, Bundle Types BD319A, BD336A, BD339A B = GE8x8NB-3, Bundle Tyys P8HXB322, P8HXB324 C = GEllLTA, Bun (le Type 89LTA D = gel 1, Bundle Type P HUB 356, P9 HUB 359 Page 31 of 33 Rev. No.1 i

,.m

.._m S

. NEW YORK POW ER AUTHORITY JAMES A. FITZPATRICK NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT 27 29 31 33 35 37 39 41 43 45 47 49 51 26 A

D A

A A

D A

A A

D B

A 24 D

A D

B D

B D

B D

A D

B A

22 A

D A

D A

D A

D B

D B

B A

20 A

B D

A A

A D

A A

B D

C A

18 A

D A

A A

D B

A A

D B

A A

16 D

B D

A D

B D

B D

B A

A 14 A

D A

D B

D A

D B

B A

12 A

B D

A A

B D

A A

B A

10 A

D B

A A

D B

A A

A A

08 D

A D

B D

B B

B A

A 06 B

D B

D B

A A

A A

. r_.

04 B

B B

B A

A M

A A

A A

A j

FIGURE 8.4.c CYCLE 11 LOADING PA'lTERN, LOWER RIGHT QUADRANT, BUNDLE DESIGN A = GE8x8EB, Bundle. Types BD319A, SD336A, BD339A B = GE3x8NB-3, Bundle Type, P8HXB322, P8HXB324 i

C = GE11LTA, Bundle Type 89LTA D = Gell, Bundle Type P9 HUB 356, P9 HUB 359 3

Page 32 of 33 Rev. No.1

l NEW YORK POWER AUTHORITY

) AMES A. FITZPATRICK NUCLEAR POWER itANT CORE OPERATING LIMITS REPORT 01 03 05 07 09 11 13 15 17 19 21 23 25 A

B B

D A

A A

D A

A A

D A

26 A

B D

A D

B D

B D

B D

A D

24 A

B B

D B

D A

D A

D A

D A

22 A

C D

B A

A D

A A

A D

B A

20 A

A B

D A

A B

D A

A A

D A

18 A

B D

B D

B D

A D

B D

16 j

I A

B B

D A

D B

D A

D A

14 A

B A

A D

B A

A D

B A

12 A

A A

A B

D A

A B

D A

10 A

A B

B B

D B

D A

D 08 A

A A

A B

D B

D B

06 A

A B

B B

B 04 A

A A

A A

02 FIGURE 8.4.d CYCLE 11 LOADING PATTERN, LOWER LEFT QUADRANT, BUNDLE DESIGN A = GE3x8EB, Bundle Types BD319A, BD336A, BD339A c

B = GEEx8NB-3, Bundle Types P8HXB322, P8HXB324 C = GEllLTA, Bundle Type 89LTA D = gel 1, Bundle Type P9 HUB 356, P9 HUB 359 Rev. No.1 Page 33 of 33

_

Retrieved from "https://kanterella.com/w/index.php?title=ML20106B024&oldid=4301918"