ML20212G716
| ML20212G716 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/13/1997 |
| From: | Gosbee G, Gurley J, Redden D COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20212G715 | List: |
| References | |
| NDIT-970160, NDIT-970160-R01, NDIT-970160-R1, NUDOCS 9711070064 | |
| Download: ML20212G716 (9) | |
Text
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NUCLIAR RTL SERVICES DEPARTMENT NUCLEAR DESIGN INFORMATION TRANSMITTAL S SAMTTY RELATED Onginnung Orgunnuon NDIT No 00160 0 NON-SAFETY RI2.ATED E NuclearIbelSerwes Rev. No. 1 O REGULATORYRELATED D Other (specify) Page I of 9 Stauon Braidwmd Una 2 Cyde 7 Genene To: James R. Meister. Braidwood Site Engineenng Manager Subject Braidw<wv! Unit 2 cvde 7 Operaunt Linuts Reruvt L auriev A de / /O[f 7f 9 L Preparer 7t: parer's Signat5re Date aa+e Reviewer a wSac-kevieweeWSignature tol,2 I9 7 Date D. Redden zu 2 i rl , /Off'] l' hT5 Supervimr
'N#iu@'s Sigidre [4),, 'Date Status ofInformation: VeriSed Unveri6ed Engineering Judgement Method and Schedule of Verification for Unverified NDITs:
Descripuan of inter-auon: Anached is the Braidwood Unit 2, Cycle 7 Operaung Limits Report (OLR).
Purpose of taformauk: Tids Retts6en supercedes Rev, O. Revtsson 0 had an inccrrect rnost negauve MTC linut. Braidwood Stauon is requemed to perfartn an On-Site Review (OSR) of tius document. Upon cornpletion of the OSR, Braidwood Station is to transnut the OLR portion to the Nuclear Regulatcry Commission pursuant to Technical Specificauon 6.9.1.9, Please provide STS (Jeff Gurley) with a copy of Braidwood Station's completed OSR and OLR mibnunal to the NRC.
Source of latsmauan: : I ) PND Calculation Number PC-01 " Operaung Lamiu Repat . Exy Linut," Project BR207, dated September i E.1997.
- 2) PND Calculadon Number SP-29,"Unfavaabte Exposure Time," Project BR207, dated July 15,1991
- 3) NDir ?7155,"Braidwood Unit 2 Cyde 7 Reload Safety Evaluation," dated September 26,1997.
- 4) PND Calculation Number SP.20," Moderator Tenperature Coefficient /Moderatar Density Coefficient," Project BR207 dated lune 26.1997.
Supplemental Distnbuuan: M. Lesniak 1. u,v 11Sen/D. Lawson + P. Boyle E. Young /M. Em H. S. Lnv1. Idrila'p ~
- Braidwuod Central File DG-CF 9711070064 971031 PDR P ADOCK 05000457 pg i
I
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NDIT 970lw Rev.1 P.ip 1 of 9 OPERATINO LIMITS REPORT (OLR) for BRAIDWOOD UNIT 2 CYCLE 7 1.0 OPER ATING LIMITS REPORT This Operating Limits Report (OLR) for Braldwood Station Unit 2 Cycle 7 has been prepared in accordance with the requirements (A Technical Specification 6.9.1.9.
The Technical Speelfications affected by this report are listed below; 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 Difference 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 tho specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies speelflod in Technical Specification 6.9.1.9.
2.1 Moderator Temnerature Coeffielent (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 104AWW'F.
- b. The EOUARO/RTP MTC shall be less negative than-4.1 x 10" AUW'F. l
~ "
2.1.2 The EOUARO/RTP MTG Surveillance limit is:
The 300 ppm /ARO/RTP MTC should be less negative than or equal to 3.2 x 10" hWW*F.
where: BOL stands for Beginnm i Cycle Life ARO standsIor All Rods out HZP stands for Hot Zero Thermal Power EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 3
=
i NDIT 970160 Rev.1 Pap 3 of 9 OPERATINO LlhtlTS RSPORT (OLR) hr BRAIDWOOD UNIT 2 CYCLE 7 2.2 Shutdown Rod Insertion Limh (Specification 3/4.1.3.5) 2.2.1 All shutdown banks shall be withdrawn to at least 228 steps.
2.3 Control Rod Innertion Limbs (Specification 3/4.1.3.6) 2.3.1 The control banks shall be kmited in physical insertion as rihown in Figure 1.
2.4 blat Flux Difference (Specification 3/4.2.1) 2.4.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +3.12% of the target flux dttierence.
2.4.2 The AFD Acceptable Operation Lirnits are provided in Figure 2.
2.5 Heat Flur Hot Channel Factor (Specification 3/4.2.2) 2.5.1 FeI Z) s (FS'"/P)[K(Z)) for P > 0.5 Fo(Z) s [FS"/0.5][K(2)) for P s 0.5 where: P = the ratio of THERMAL POWER to RATED THERMAL POWER FS'" = 2.60 K(Z) is provided in Figure 3.
_ 2.5.2 F4 = fy'[1 + n P(1. P))
F"y' limits within specified core planes shall be:
- a. For the lower core region f rom greater than or equal to 0% to less than or equal to 50%:
- 1) F"y" s 3.119 f or all core planes containing bank 'D' controi rods
- 2) F"y" s 1.776 for all unrodded core planes
- b. For the upper core region f rom greater than 50% to less than or equal to 100%:
- 1) F"y" s 2.251 for all core planes containing bank 'D' control rods
- 2) F"y" s 1.954 for all unrodded core planes 2.5.3 A plot of [Fo(z)
- Pa.) vs Axial Core Height is provided in Figure 4 and Table 1 contains the data plotted in Figure 4.
NDIT 970!f>0 Rev.1 Pa p 4 of 9 OPERATING LIMITS REPORT (OLR) fct BRAIDWOOD UhTT 2 CYCLE 7 2.6 Nuclear Enthstov Rise Hot Channel Factor (Specification 3/4.2.3)
FL s F'8[1.0 + PFe(1.0 P))
where: P = the ratio of THERMAL POWER to RATED THERMAL POWER F77 = 1.70 PFw = 0.3
. NDIT 970160 Rev.1
- Page 5 of 9 OPERATING LIMITS REPORT (0LR) for BRAIDWOOD UhTT 2 CYCLE 7 Figum 1:
Control Bank Insertion Limits Versus Percent Rated Thermal Power (29 %.228) (79 %, 228) 228 220 --
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NDIT 9701(4 Rev.1 Page 6 of 9 OPERATING LIMITS REPORT (OLR) for BRAIDWOOD UNIT 2 CYCLE 1 FIGURE 2: Axial Flux Difference Limits As A Function of Rated Thermal Power r
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o NDIT 970160 Rev.1 Page 9 of 9 OPERATINO LIMITS REPORT (OLR) for BRAIDWOOD UNIT 2 CYCLE 7 TaNe 1:(Fdr)
- PmA vs. Atlai Core lleight Fq SPIL Core Height (feet) Max Fa x P UMit
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Shaded area (top and bottom 15%) is ignored.
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