ML20108D867
| ML20108D867 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 03/11/1996 |
| From: | Redden D, Stevens T, Thomasen J COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20108D859 | List: |
| References | |
| NUDOCS 9605090088 | |
| Download: ML20108D867 (4) | |
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NUCLEAR RJEL SERVICES DEPARTMENT NUCLEAR DESIGN INFORMATION TRANSMf!TAL j
S SAFETY RELATED Originating Orgamzation NDIT No.
960028 O NON-SAFETY RELATED E Nuc!carFuelServices Rev. No.
O O REGULATORY RELATED O Other(specify)
PageIof5 Station Braidwood Unit 2 Cycle 6 Generic To: L K Kepley l
t Subject Braidwood Unit 2 Cycle 6 Operating Limits Report l
Tvrone L Stevens A4.YNL 3 [o 9h Preparer Prefp t's signature Date John P. Romasen h
Reviewer Sewer's Signature Date 5 n %
R. Redden NFS Supervisor NFS Su Signature Date l
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Status ofInformation:
E Verified O Unvenfied O Engineering Judgment Method and Schedule of Venfication for Unverified NDITs:
l Desenption ofInformation: Attached is the Braidwood Unit 2, Cycle 6 Operating Limits Report (OLR).
Purpose ofInformation: Braidwood station is requested to perform an On-Site Review (OSR.) of this document. Upon completion of the OSR, Braidwood Station is to notify llany Pontious (DO x7205) of the Nuclear Licensing Department. Nuclear Licensing will then transmit the OLR to the Nuclear Regulatory Commission pursuant to Technical Specification 6.9.1.9. Please provide NFS with a copy of Braidwood Station's completed OSR for incorporation into the BR2C6 reload licensing file.
Source ofInformation: PWR Nuclear Design Supplemental Distnbution:
H. D. Pontious Braidwood Central File L S. Dworakowski J. M. Constantino A. J. Patterson NDIT File S. M. Hurst CHRON No: ggggqq l
9605090088 960430 PDR ADOCK 05000457 P
NUCLEAR FUEL SERVICES DEPARTMENT NDIT No.
96c078 NUCLEAR DESIGN INFORMATION TRANSMTITAL Rev. No.
o Page 2 of 5 l
l Braidwood Unit 2 Cycle 6 Operatine Limit Resort - Fxv Portion l
This Radial Peaking Factor Limit Report is provided in accordance with Paragraph 6.9.1.9 of the Braidrood Unit 2 Nuclear Plant Technical Specifications.
The Fxy limits for RATED THERMAL POWER within specified core planes for Cycle 6 shall be:
a: For the lower core region from greater than or equal to 0% to less than or equal to 50%:
- 1. For all core planes containing bank "D" control rods:
F "" s 2.803 y
- 2. For all unrodded core planes:
Fy""s 1.729 b: For the upper core region from greater than 50% to less than or equal to 100%:
- 1. For all core planes containing bank "D" control rods:
Fy"" s 2.103
- 2. For all unrodded core planes:
F ""s 1.810 y
These Fxy(z) limits were used to confirm that the heat flux hot channel factor FQ(z) will be limited to the Technical Specification values of:
Fo(z) s [110] [K(z)]
for P > 0.5 and, P
Fo(z) s [5.00] [K(z)]
for P s 0.5 assuming the most limiting axial power distributions expected to result from the insertion and removal of Control Banks C and D dunng operation, including the accompanying variations in the axial xenon and power distnbutions as described in the ' Power Distribution Control and Load Following Procedures,"
WCAP-8403, September 1974. Therefore, these Fxy limits provide assurance that the initial conditions assumed in the LOCA analysis and the ECCS acceptance criteria of 10 CFR 50.46 are met.
See the attached table and figure for [ Fo(z) x P,,i] vs. Axial Core Height information.
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e NUCLEAR FUEL SERVICES DEPARTMENT NDIT NA 960078 NUCLEAR DESIGN INFORMATION TRANSMTITAL Rev. No.
o Page 3 of 5 Braidwood Unit 2 Cycle 6 Operatine Limit Report - MTC Portion l
a:
The Moderator Temperature Coefficient (MTC) limits are:
i f
- 1. The BOL/ARO/HZP-MTC shall be less positive than +4.0 x 10 Ak/k/ F.
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- 2. The EOUARO/RTP-MTC shall be less negative than -4.1 x 10 " Ak/k/*F.
l b:
The MTC surveillance limit is:
l 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 l
HZP stands for Hot Zero Thermal Power i
EOL stands for End of Cycle Life RTP stands for Rated Thermal Power i
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NUCLEAR FUEL SERVICES DEPARTMENT NDIT No.
960028 NUCLEAR DESIGN INFORMATION TRANSMrITAL Rev. No.
O Page 4 of 5 BRAIDWOOD UNIT 2 CYCLE 6 Fxy LIMIT EVALUATION Summary of Fq vs. Core Height Fq SPIL Core Height (feet)
Maximum Fq x P LIMIT BRMBBBB 1.8778 2.4999 2.5000 2.1282 2.2956 2.5000 2.3786 2.3666 2.5000 2.6289 2.3276 2.5000 2.8793 2.3561 2.5000 3.1297 2.3792 2.5000 3.3801 2.3948 2.5000 3.6305 2.4087 2.5000 3.8808 2.2272 2.5000 4.1312 2.4099 2.5000 4.3816 2.4126 2.5000 4.6320 2.4044 2.5000 4.8823 2.3915 2.5000 5.1327 2.3743 2.5000 5.3831 2.3905 2.5000 5.6335 2.2404 2.5000 5.8838 2.4268 2.5000 6.1342 2.4648 2.4957 6.3846 2.4878 2.4878 6.6350 2.4582 2.4799 6.8853 2.4457 2.4720 7.1357 2.4196 2.4640 7.3861 2.3648 2.4561 7.6365 2.4273 2.4482 7.8868 2.4195 2.4402 8.1372 2.4039 2.4323 8.3876 2.3792 2.4244 8.6380 2.3479 2.4165 8.8883 2.3011 2.4085 9.1387 2.2127 2.4006 9.3891 2.3076 2.3927 9.6395 2.3110 2.3847 9.8899 2.3407 2.3768 10.140 2.3681 2.3689 IWf63915'T ?"IE158ti: y ( 7:QDM077 90
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Unshaded area shows survei!!ance region.
Shaded area (top and bottom 15%) is ignored for this surveillance.
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3 NUCLEAR FUELSERVICES DEPARDENT NDIT No.
96o028 o
NUCIE.AR DES 10N INFORMATION TRANSMITTAL Rev. Na o
Page 5 of 5 Braidwood Unit 2 Cycle a FQ(Z) x P versus Core Height (60.150) 2.6000 2
(110.2-it) a
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2.2000 a
2.0000 l
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1.8000 a
1.6000 m Fxy Umit Analysis Points 1.4000 LOCA umiting Enve6 ope
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- Bottem Survemence uma 1.2000
- * * - Top Survenance umit g1.oooo 0.8000 a
0.6000 0.4000 t
l 0.2000 o.0000
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1 2
3 4
5 6
7 3
g 10 11 12 l
CORE HEIGHT (FT)
TOP BOTTOM i
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