ML093100123

Attachment 23, Browns Ferry Unit 1 - Technical Specification Change 467, 51-9121246-000, Revision 0, MCPR Safety Limit Analysis

ML093100123
Person / Time
Site:	Browns Ferry
Issue date:	09/03/2009
From:	Tylinski S AREVA NP
To:	Office of Nuclear Reactor Regulation
References
20004-016, L32 090906 800, TS 467 51-9121246-000, Rev 000
Download: ML093100123 (16)

Text

ATTACHMENT 23 Browns Ferry Nuclear Plant (BFN)

Unit 1 Technical Specifications (TS) Change 467 Revision of Technical Specifications to allow utilization of AREVA NP fuel and associated analysis methodologies Safety Limit Minimum Critical Power Ratio Attached is the non-proprietary version of safety limit MCPR analyses results supporting 120% OLTP operation.

A L32 090906 800 20004-016 (07/23/2009)

AREVA AREVA NP Inc.,

an AREVA and Siemens company Engineering Information Record Document No: 51 - 9121246 - 000 Browns Ferry Unit I Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

Page 1 of 15

20004-016 (0712312009)

ARE VA 51-9121246-000 AREVA NP Inc.,

an AREVA and Siemens company Browns Ferry Unit I Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

Safety related? EYEs FEIINO Does this document contain assumptions requiring verification? D YES ZNO Does this document contain Customer Required Format? -I YES ~NO Signature Block PILP, RILR, PageslSections Name and A/A-CRF, Prepared/Revlewedl Title/Discipline Signature AIA-CRI Date Approved or Comments S.A. Tylinski, Engineer S. P Thermal-Hydraulics Richland S/r V "i/'/cs DOD. Crockett, Engineer Thermal-Hydraulics Richland c R /0) 9 D.W. Pruitt, Manager ,_ > A/A-CRI Thermal-Hydraulics Richland - -

A.B. Meginnis, Manager A Product Licensing ___-31_ ///2/ '

II/

Note: P/LP designates Preparer (P), Lead Preparer (LP)

R/LR designates Reviewer (R), Lead Reviewer (LR)

A/A-CRF designates Approver (A), Approver of Customer Requested Format (A-CRF)

NA-CRI designates Approver (A), Approver - Confirming Reviewer Independence (A-CRI)

Record of Revision Revision PageslSectionsl Brief Description I No. Date Paragraphs Changed Change Authorization 000 Initial issue.

This Is the nonproprietary version of 51-9119738-000.

Page 2

A 20004-016 (07/23/2009)

AR EVA 51-9121246-000 AREVA NP Inc.,

an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

Table of Contents 1.0 S um m ary a nd Results ................................................................................................................... 4 Tables 1 Fuel- and Plant-Related Uncertainties MCPR Safety Limit Analyses ....................................... 6 2 Results Summary for MCPR Safety Limit Analysis .................................................................. 7 3 Co re Lo a d ing ................................................................................................................................. 7 Figures 1 Radial Power Distribution for TLO Limiting Exposure of [ ]...................... 8 2 Radial Power Distribution for SLO Limiting Exposure of [ ..................... 9 3 Reference Core Loading Pattern ................................................................... ........ 10 4 Lower Right Quarter Core Layout by Fuel Type .................................................................... 12 5

]............................................................. . . 13 6

............................................................ . . 14 7

]............................................................. . . 15 Page 3

AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP) 1.0 Summary and Results This report presents the Browns Ferry Unit 1 Cycle 9 (BFE1-9) MCPR safety limit analysis results for 120% original licensed thermal power (OLTP) conditions. The MCPR safety limit analysis results presented are applicable in all the equipment out-of-service scenarios and extended operating domains identified in Reference 1.

The MCPR safety limit results presented support 1.07 for two-loop operation (TLO) and 1.10 for single-loop operation (SLO). Therefore, updates to the Browns Ferry Unit 1 Technical Specifications would be required for the BFE1-9 120% OLTP MCPR safety limit.

Reactor system measurement uncertainties are statistically convolved with MCPR calculational uncertainties to determine a MCPR safety limit that ensures that at least 99.9% of the fuel rods in the reactor core would not be expected to experience boiling transition during normal operation or an anticipated operational occurrence. [

] The MCPR safety limit is used in conjunction with transient analysis results to establish the MCPR operating limit.

The MCPR safety limit methodology is described in Reference 2.

The final 120% OLTP core design and step-through, developed by AREVA NP* to meet the operating requirements specified by TVA, was used in the BFE1-9 120% OLTP MCPR safety limit analysis. The BFE1 -9 120% OLTP design supports licensed rated power of 3,952 MWt and operation to licensing end of cycle (EOC) cycle exposure of approximately 19,635 MWd/MTU. The design includes extensions for final feedwater temperature reduction (FFTR) and coastdown.

The BFE1-9 120% OLTP MCPR safety limit analysis used the SPCB critical power correlation additive constants and additive constant uncertainty reported in Reference 3t for ATRIUMTM-10* fuel. [

] The impacts of channel bow were explicitly accounted for in the analysis consistent with the process described in Reference 2. The local power peaking uncertainty is based upon the monitoring computer code as reported in Reference 4. The relationship between assembly flow rate and assembly power was determined for each fuel type using the methodology and assembly flow rate uncertainty reported in Reference 2.

• AREVA NP Inc. is an AREVA and Siemens company t AREVA has submitted an addendum to the NRC for Reference 3. It is Addendum 1 Revision 0 titled, SPCB Additive Constants forATRIUM-IO Fuel. It addresses Condition Report 2007-3653 regarding the CPR test loop power error. Analyses for BFE1-9 120% OLTP incorporate this addendum.

ATRIUM is a trademark of AREVA NP.

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AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

The analysis supports:

• Fuel- and plant-related uncertainties for BFE1-9 120% OLTP presented in Table 1.

• 50% of the LPRMs out of service (LPRM bypass model on or off).

• Up to 2 TIP machines out of service, or the equivalent number of TIP channels.

• 2500 EFPH LPRM calibration interval.

• No reused channels.

Table 2 presents a summary of the analysis results including the MCPR safety limit and the percentage of rods expected to experience boiling transition for both TLO and SLO. Analyses were performed using the power distributions from each exposure in the design step-through. The safety limit radial power histograms for the limiting TLO and SLO cycle exposures of [

], respectively (i.e., the exposures that results in the highest number of rods expected to experience boiling transition) are presented in Figures 1 and 2. The BFEI-9 120% OLTP core loading and fuel design are presented in Table 3 and Figures 3 through 7.

References

1. 51-9107387-000, "Browns Ferry Unit 1 Cycle 9 Calculation Plan," AREVA NP, May 2009.

2. ANF-524(P)(A) Revision 2 and Supplements 1 and 2, ANF CriticalPower Methodology for Boiling Water Reactors, Advanced Nuclear Fuels Corporation, November 1990.

3. EMF-2209(P)(A) Revision 2, SPCB CriticalPower Correlation,Framatome ANP, September 2003.

4. EMF-2158(P)(A) Revision 0, Siemens Power CorporationMethodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/MICROBURN-B2, Siemens Power Corporation, October 1999.

5. Letter, H. Donald Curet (AREVA) to H.J. Richings (USNRC), "POWERPLEX Core Monitoring:

Failed or Bypassed Instrumentation and Extended Calibration," HDC:96:012, May 6, 1996.

(38-9043714-000).

6. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation'sCriticalPower Correlationsto Co-Resident Fuel, Siemens Power Corporation, August 2000.

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AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

Table 1 Fuel- and Plant-Related Uncertainties MCPR Safety Limit Analyses Standard Parameter Deviation Fuel-Related Uncertainties

[

Plant-Related Uncertainties Feedwater flow rate 1.8%

Feedwater temperature 0.8%

Core pressure 0.7%

Total core flow rate TLO 2.5%

SLO 6.0%

• [

I Page 6

AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

Table 2 Results Summary for MCPR Safety Limit Analysis Percentage of Rods in Boiling SLMCPR Transition TLO - 1.07 0.0687 SLO- 1.10 0.0731 Table 3 Core Loading Nuclear Total Serial Fuel Cycle Fuel Number of Number Description Loaded Type Assemblies Prefix GE14 7 4 24 JLX GE14 7 5 12 JLX GE14 7 6 17 JLX GE14 7 9 32 JLX GE14 7 10 12 JLX GE14 7 11 8 JLX GE14 8 14 48 JYE GE14 8 15 96 JYE GE14 8 16 64 JYE GE14 8 17 48 JYE GE14 8 18 71 JYE ATRIUM-10 9 19 192 FAA ATRIUM-10 9 20 40 FAA ATRIUM-10 9 21 100 FAA Page 7

AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP) 200 175 150 C:

125 100 I I I I I I I 0

E 75 z

50 25 0 . . . . . . . . . . i i

.0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Radial Power Peaking Figure 1 Radial Power Distribution for TLO Limiting Exposure of [ I Page 8

AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP) 200 175 150

_0 125 4--

100 0

E 75 z

50 25 0

.0 .1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 Radial Power Peaking Figure 2 Radial Power Distribution for SLO Limiting Exposure of [ I Page 9

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0 I-Figure 3 Reference Loading Pattern

31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 60 JLX729 JLX691 JYE382 JLX688 JLX558 JLX633 JLX635 CD 58 JYE310 JYE334 JYE318 JYE326 JYE246 JYE366 JYE170 JLX631 E0 56 JYE274 FAA315 FAA182 FAA323 FAA25O FAA238 FAA214 JYE202 JLX482 JLX629 54 FAA258 JYE134 FAA286 JYE270 FAA166 JYE422 FAA294 JYE342 JYE146 JLX491 cn 52 JYE286 F'AA218 JYE294 FAA190 FAA194 FAA306 JYE374 FAA270 FAA282 JYE182 JYE370O 50 FAA230 JYE414 FAA206 JYE118 FAA174 JYE410 FAA246 JYE390 FAA066 JYE110 JYE194 JLX547 JLX640 48 JYE102 F'AA146 JYE126 FAA114 JYE282 FAA138 JYE350 FAA094 FAA330 FAA002 FAA274 JYE142 JLX481 46JE6 FA9 AA5 Y25 A12 JYE302 FAA122 JYE226 FAA110 JYE394 FAA266 JYE346 JYE150 JLX639 44 JYE158 FAA050 JYE230 FAA026 JYE198 FAA134 JYE402 FAA126 JYE354 FAA242 JYE378 FAA278 FAA210 JYE178 JLX637-42 FAA018 JLX355 FAA058 JYE214 FAA054 JYE398 FAA150 JYE306 FAA130 JYE406 FAA312 JYE426 FAA234 JYE358 JLX638 40 JLX286 FAA010 JYE242 FAA074 JYE362 FAA086 JYE238 FAA014 JYE278 FAA170 FAA198 FAA118 FAA254 JYE250 JLX553 38 FAA038 JYE222 FAA102 JYE114 FAA078 JYE218 FAA030 JYE258 FAA046 JYE122 FAA186 JYE262 FAA324 JYE330 JLX545 36 JYE210 FAA302 JLX330 FAA106 JYE154 FAA022 JYE234 FAA158 JYE130 FAA202 JYE298 FAA290 FAA178 JYE322 JYE386 CD 34 FAA034 JLX229 FAA298 JYE186 FAA006 JLX412 FAA042 JYE174 FAA142 JYE418 FAA222 JYE138 FAA316 JYE338 JLX692 .

32 JYE190 FAA062 JYE206 FAA082 JLX403 FAA070 JYE162 FAA098 JYE1O6 FAA226 JYE290 FAA262 JYE266 JYE314 JLX739 K 30 JYE195 FAA035 JYE207 FAA039 JLX290 FAA019 JYE163 FAA091 JYE107 FAA231 JYE291 FAA259 JYE263 JYE315 JLX740 -

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24 FAA083 JYE183 F'AA107 JYE111 FAA075 JYE219 FAA027 JYE259 FAA115 JYE123 FAA191 JYE271 FAA325 JYE331 JLX701 22 JLX354 FAA007 JYE151 FAA079 JYE359 FAA055 JYE203 FAA163 JYE283 FAA175 FAA195 FAA167 FAA251 JYE251 JLX548 20 FAA071 JLX351 FAA023 JYE215 FAA087 JYE403 FAA135 JYE307 FAA139 JYE407 FAA311 JYE427 FAA239 JYE363 JLX492r 18 JYE155 FAA043 JYE231 FAA031 JYE243 FAA151 JYE399 FAA123 JYE355 FAA247 JYE379 FAA295 FAA215 JYE179 JLX644 3 16 FAA099 JYE159 FAA159 JYE255 FAA015 JYE303 FAA127 JYE223 FAA095 JYE395 FAA271 JYE347 JYE199 JLX642 -

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Figure 3 Reference Loading Pattern (Continued)

AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

No. Per I

Fuel Type Description Cycle Loaded Quarter core 4 GE14-PlODNAB157-NOG 7 6 5 GE14-PlODNAB377-16GZ 7 3 6 GE14-PlODNAB402-16GZ 7 5 9 GE14-PlODNAB419-16GZ 7 7 10 GE14-PlODNAB368-15GZ 7 3 11 GE14-PlODNAB402-19GZ 7 2 14 GE14-PlODNAB406-16GZ 8 12 15 GE14-PlODNAB400-17GZ 8 24 16 GE14-PlODNAB406-15GZ 8 16 17 GE14-PlODNAB417-16GZ 8 12 18 GE14-PlODNAB418-16GZ 8 18 19 A10-3761B-14GV80-FAA 9 48 20 Al0-3831B-12GV80-FAA 9 10 21 Al0-4171B-14GV80-FAA 9 25 Figure 4 Lower Right Quarter Core Layout By Fuel Type Page 12

AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

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AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

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AREVA NP Inc., 51-9121246-000 an AREVA and Siemens company Browns Ferry Unit 1 Cycle 9 MCPR Safety Limit Analysis (120% OLTP)

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