ML20140H145

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Rev 1 to Ndit 97044, Braidwood Unit 1 Cycle 7 Operating Limits Rept
ML20140H145
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 04/22/1997
From: Gurley J, Moravak P, Redden D
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20140H139 List:
References
NDIT-97044, NDIT-97044-R01, NDIT-97044-R1, NUDOCS 9705120350
Download: ML20140H145 (9)
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h NUC11AR FUEL SERVICES DEPARTMEPfr NUCLEAR DESIGN INFORMATION 'IRANSMrrTAL j

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@ SAFETY RELATED Originating Organization NDfTNo.

97044 i

O NON-SAFETY RELATED

@ NuclearFuelServices Rev. No.

t O REGULATORY RELATED D Other(specify)

Page 1 of 11 1

Station Braidwood Unit 1 Cycle 7 Ocneric To: James R. Meister, Braidwood Site Engineenng Manager P

Subject Braidwood Unit I Cycle 7 Operating Umits doort h

'2 f2 2

J. Ourley MA

/

Preparer gparer's Signature "

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ll P Moravek Reviewer R

Sign Date D. Redden O

NFS Srspervisor ifrSfupervisor's Signature' Date Status ofInformation:

@ Venried Q Unvenfied LJ EngineenngJudgement Method and Schedule of Venfication for Unverified NDirs-Desenpuon of Informauon: Attached is the Braidwood Umt 1. Cycle 7 Operaung Unuts Repon (OLR).

Purpose of Information:'I1nis Revhlon sunercedes Reviden 0. Revision 0 contained an error in the BOUARO/HZP-MTC value. Braadwood Station is requested to perform an On-Site Review (OSR) of this document. Upon completion of the OSR Braidwood Station is to transmit the OLR portion to the Nuclear Regulatory Commission pursuant to Technical Specification 6.9.1.9. Please provide NFS Deff Ourley) with a copy of Braidwood Station's completed OSR and OLR submittal to the NRC.

Source of Informanon: 1) PND Calculanon Number NR42. "Fxy unuts Genersoon for OLR." Project BRIC7. dated Rbruary 26.1997,

2) PND Calculation Number SP-57. "UET Analysis for BRIC7." Project BRIC7. File NDN 10.6. dated February 17,1997
3) Lener from M. Imsniak to U. S. Nuclear Regulatory Comminion. " Application for Amendment to Facility Opernung Ucenses-Reactivity Convol Systems: Byron Stanon Units 1 and 2. NPF-37/66: Docket Nos. 50 454/455: Braidwood Units I and 2 NPF 72/77 Docket Nos. 50456/457." dated December 21.1995.

Supplemental Distnbuuon: M. Lesniak L Kepley / B. Bergmann/D. lawson P. Boyle E. Young /R. Lee H. S. Kim/J. Dunlap Braidwood Central File 9705120350 970501 6

PDR ADOCK 0500 P

NDIT 97044 Rev.1 i

Page 2 of 11 OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 1 CYCLE 7 1.0 OPERATING LIMITS REPORT This Operating Limits Report (OLR) for Braidwood Station Unit 1 Cycle 7 has been prepared in accordance with the requirements of Technical Specification 6.9.1.9.

1 The Technical Specifications affected by this report are listed below:

i 3/4.1.1.3 Moderator Temperature Coefficient 3/4.1.3.5 Shutdown Rod insertion Limit 3/4.1.3.6 Control Rod Insertion Limits 3/4.2.1 Axial Flux Ditference 3/4.2.2 Heat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 6.9.1.9.

2.1 Moderator Temoerature Coefficient (Specification 3/4.1.1.3) 2.1.1 The Moderator Temperature Coefficient (MTC) limits are:

a. The BOUARO/HZP-MTC shall be less positive than +3.5 x 10 s Ak/k/*F.
b. The EOUARO/RTP-MTC shall be less negative than 4.1 x 10" ak/k/ F.

2.1.2 The EOUARO/RTP-MTC Surveillance limit is:

The 300 ppm /ARO/RTP-MTC should be less negative than or equal to -3.2 x 10" ak/k/ F.

where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER

i NDTr 97044 Rev.1 Page 3 of 11 OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 1 CYCLE 7 i

2.2 Shutdown Rod insertion Limit (Specification 3/4.1.3.5) 2.2.1 All shutdown banks shall be withdrawn to at least 228 steps.

2.3 Control Rod I isertion Umits (Specification 3/4.1.3.6) i 2.3.1 The control banks shall be limited in physical insertion as shown in Figure 1.

2.4 Axial Flux Difference (Specification 3/4.2.1) 1 2.4.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +3,-12% of the target flux difference.

i 2.4.2 The AFD Acceptable Operation Limits are provided in Figure 2.

2.5 Heat Flux Hot Channel Fector (Specification 3/4.2.2) 2.5.1 Fo(Z) s [F$"iP][K(Z)] for P > C.5 Fo(Z) s [F$"/0.5][K(Z)] for P s 0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FS" = 2.60 K(Z) is provided in Fjgure 3.

2.5.2 F[y = F7 [1 + 0.2(1 - P)]

F7 limits within specified core planes shall be:

1

a. For the lower core region from greater than or equal to 0% to less than or equal to 50%:
1) F7 s 3.119 for all core planes containing bank "D" control rods
2) F7 s 1.854 for all unrodded core planes
b. For the upper core region from greater than 50% to less than or equal to 100%:

1

1) F7 5 2.251 for all core planes containing bank "D' control rods
2) F7 51.923 for all unrodded core planes 2.5.3 A plot of [Fo(z)
  • Pu] vs Axial Core Height is provided in Figure 4 and Table 1 contains the data plotted in Figure 4.

NDIT 97044 Rev.I 2

Page 4 of 11 a

j OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 1 CYCLE 7 i

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2.6 Nuclear Enthalov Rise Hot Channel Factor (Specification 3/4.2.3)

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t F1 s F*a((1.0 + PFe(1.0 P)]

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. where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FLJ = 1.70 PFm = 0.3

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Page 5 of 11 OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 1 CYCLE 7 Figure 1:

Control Bank Insertion Limits Versus Percent Rated Thermal Power (29 %,228)

(79 %,228) j I

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10 20 30 40 50 60 70 80 90 100 Relative Power (Percent)

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Rev.1 Page 6 of 11 i

OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 1 CYCLE 7 i

FIGURE 2: Axial Flux Difference Limits As A Function of Rated Thermal Power l

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Page 9 of 11 3

i' OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 1 CYCLE 7 Table 1: {Fo(z)

  • Pu] vs. Axial Core Height i

Fq SPIL 4

l Core Height Max Fa x P UMIT J

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1.8778 2.

2.6000 J

4 2.1282 2.4052 2.6000 j

2.3786 2.527 2.6000 i

2.6290 2.5287 2.6000 i

2.8794 2.4992 2.6000 3.1297 2.4651 2.6000 j

3.3801 2.4304 2.6000 3.6305 2.4048 2.6000 j

3.8809 2.2001 2.6000 4.1313 2.3605 2.6000 l

4.3816 2.3481 2.6000 4.6320 2.3510 2.6000 l

4.8824 2.3068 2.6000 1

5.1328 2.2978 2.6000 j

5.3832 2.3422 2.6000 l

5.6335 2.1888 2.6000 5.8839 2.3651 2.6000 t

6.1343 2.4148 2.5956 1

6.3847 2.4638 2.5875 l

6.6351 2.5047 2.5794 l

6.8854 2.5703 2.5712 7.1358 2.5462 2.5631 7.3862 2.4753 2.5549 l

7.6366 2.5159 2.5468 i

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8.1373 2.5207 2.5305 i

8.3877 2.5128 2.5224 I

8.6381 2.5136 2.5143 8.8885 2.4730 2.5061 I

9.1388 2.3915 2.4980 i

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9.6396 2.4516 2.4817 l

9.8900 2.4593 2.4736 10.1400 2.

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1 Unshaded area shows swveillance region.

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Shaded area (top and bottom 15%) is ignored.

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