RS-18-134, Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits
| ML18339A009 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 12/05/2018 |
| From: | Simpson P Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18339A008 | List: |
| References | |
| RS-18-134 | |
| Download: ML18339A009 (68) | |
Text
4300 Winfield Road Exelon Generation Warrenville . IL 60555 630 65 7 2000 Office Proprietary Information -Withhold from Public Disclosure Under 10 CFR 2.390 RS-18-134 10 CFR 50.90 December 5, 2018 U.S. Nuclear Regulatory Commission Attn : Document Control Desk Washington , DC 20555-0001 Dresden Nuclear Power Station , Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249 Quad Cities Nuclear Power Station , Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254 and 50-265
Subject:
Request to Revise Technical Specifications 2.1.1 for Minimum Critical Power Ratio Safety Limits - Dresden Nuclear Power Station , Units 2 and 3, and Quad Cities Nuclear Power Station , Units 1 and 2 In accordance with 10 CFR 50 .90 , "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC, (EGC) requests proposed changes to modify Technical Specifications (TS) 2.1.1, "Reactor Core Sls [Safety Limits]," for Dresden Nuclear Power Station (DNPS) , Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS) , Units 1 and 2. Specifically, these changes incorporate revised DNPS , Units 2 and 3, and QCNPS , Units 1 and 2, Minimum Critical Power Ratio Safety Limits (SLMCPRs) in accordance with analyses performed by Framatome for DNPS and QCNPS Cycles 26 and 25, respectively.
There are 12 attachments to this letter. Attachment 1 provides an evaluation of the proposed changes. Attachments 2 and 3 provide the current TS pages for DNPS and QCNPS ,
respectively , with the proposed changes indicated. Attachments 4 through 7 provide non-proprietary details regarding the analyses performed in support of the requested changes to the SLMCPRs. Attachment 9 through 12 provide the proprietary versions of Attachments 4 through 7. Attachment 8 is an affidavit from Framatome, Inc., as the owner of the proprietary information, attesting to the proprietary nature of the information contained in Attachments 9 through 12. The proprietary information has been reproduced in Attachments 9 through 12 such that the affidavit remains applicable . Accordingly, it is requested that the enclosed proprietary information be withheld from public disclosure in accordance with 10 CFR 2.390.
Attachments 9, 10, 11, and 12 contain Proprietary Information.
Withhold from Public Disclosure Under 10 CFR 2.390.
When separated from Attachments 9, 10, 11 and 12, this document is decontrolled.
December 5, 2018 U.S. Nuclear Regulatory Commission Page 2 The purpose of proposed changes is to provide for improved operational flexibility through the recapture of margins that are available as a result of the transition to Framatome's NRC approved SLMCPR calculation methodology. Additionally, the proposed changes are not required for any of the current operating cycles, and the current and anticipated future core designs that utilize ATRIUM 10XM fuel for DNPS and QCNPS allow for these changes.
The proposed amendments have been approved by the DNPS and QCNPS Plant Operations Review Committees in accordance with the EGC Quality Assurance Program.
EGC requests approval of the proposed amendments by December 5, 2019. Once approved, the amendments shall be implemented within 60 days.
In accordance with 10 CFR 50.91 , "Notice for public comment; State consultation," paragraph (b),
EGC is notifying the State of Illinois of this application for a change to the TS by transmitting a copy of this letter and its attachments to the designated State Official.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Mitchel A. Mathews at (630) 657-2819.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 5th day of December 2018.
Patrick R. Simpson Manager - Licensing Exelon Generation Company , LLC
December 5, 2018 U.S. Nuclear Regulatory Commission Page 3 Attachments:
- 1) Evaluation of Proposed Changes
- 2) Dresden Proposed Technical Specifications Changes - Marked-Up TS Page
- 3) Quad Cities Proposed Technical Specifications Changes - Marked-Up TS Page
- 4) FS1-0039283, "Dresden Unit 2 Cycle 26 SLMCPR Analysis," (Non-Proprietary Version)
- 5) FS1-0037607, "Dresden Unit 3 Cycle 26 SLMCPR Analysis," (Non-Proprietary Version)
- 6) FS1-0039279, "Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis," (Non-Proprietary Version)
- 7) FS1-0039286, "Quad Cities Unit 2 Cycle 25 SLMCPR Analysis," (Non-Proprietary Version)
- 8) Affidavit from Framatome, Inc. Attesting to the Proprietary Nature of Information in Attachments 9, 10, 11, and 12
- 9) FS1-0031933, "Dresden Unit 2 Cycle 26 SLMCPR Analysis," (Proprietary Version)
- 10) FS1-0037152, "Dresden Unit 3 Cycle 26 SLMCPR Analysis," (Proprietary Version)
- 11) FS1-0029827, "Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis," (Proprietary Version)
- 12) FS1-0034209, "Quad Cities Unit 2 Cycle 25 SLMCPR Analysis," (Proprietary Version) cc: NRC Regional Administrator, Region Ill NRC Senior Resident Inspector, Dresden Nuclear Power Station NRC Senior Resident Inspector, Quad Cities Nuclear Power Station Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT 1 Evaluation of Proposed Changes
Subject:
Request to Revise Technical Specification 2.1 .1 for Minimum Critical Power Ratio Safety Limits - Dresden Nuclear Power Station, Units 2 and 3, and Quad Cities Nuclear Power Station, Units 1 and 2 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria 4.2 Precedents 4.3 No Significant Hazards Consideration 4.4 Conclusions 5.0 ENVIRONMENTAL CONSIDERATON Page 1of7
ATTACHMENT 1 Evaluation of Proposed Changes 1.0
SUMMARY
DESCRIPTION Exelon Generation Company, LLC (EGC) is requesting NRC approval of proposed changes that would revise Technical Specification (TS) 2.1 .1, "Reactor Core Sls [Safety Limits]," for Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Quad Cities Nuclear Power Station (QCNPS), Units 1 and 2. Specifically, the proposed changes incorporate revised Safety Limit Minimum Critical Power Ratios (SLMCPRs) due to the cycle specific analyses performed by Framatome, Inc. for DNPS, Units 2 and 3, Cycle 26, and QCNPS, Units 1 and 2, Cycle 25.
Analyses performed in support of the proposed changes utilized cycle-specific input to establish the appropriate SLMCPRs. The purpose of proposed changes is to provide for improved operational flexibility through the recapture of margins that are available as a result of the transition to Framatome's NRC approved SLMCPR calculation methodology. Additionally, the proposed changes are not required for any of the current operating cycles, and the current and anticipated future core designs that utilize ATRIUM 10XM fuel for DNPS and QCNPS allow for these changes.
The proposed changes are described in detail in Section 2.0 below.
2.0 DETAILED DESCRIPTION For DNPS. Units 2 and 3:
The proposed amendment reflects a decrease of the two recirculation loop SLMCPR limit from greater than or equal to (2!:) 1.12 to 2!: 1.08 and a decrease in the single recirculation loop SLMCPR from 2!: 1.14 to 2!: 1.10.
For QCNPS, Unit 1:
The proposed amendment reflects a decrease of the two recirculation loop SLMCPR limit from 2!: 1.11 to 2!: 1.08 and a decrease in the single recirculation loop SLMCPR from 2!: 1.14 to 2!: 1.10.
For QCNPS, Unit 2:
The proposed amendment reflects a decrease of the two recirculation loop SLMCPR limit from 2!: 1.12 to 2!: 1.08 and a decrease in the single recirculation loop SLMCPR from 2!: 1.14 to 2!: 1.10.
The proposed changes have been evaluated in accordance with 10 CFR 50.91(a)(1) using the criteria in 10 CFR 50.92(c), and it has been determined that the changes do not involve a significant hazards consideration . The bases for these determinations are included in Section 4.0 of this Attachment. provides the current DNPS TS page with the proposed changes indicated for DNPS, Units 2 and 3. Attachment 3 provides the current QCNPS TS page with the proposed changes indicated for QCNPS, Units 1 and 2.
3.0 TECHNICAL EVALUATION
The proposed TS change will revise the SLMCPRs contained in TS 2.1.1 .2 for two recirculation loop operation and single recirculation loop operation to reflect the changes in the cycle specific Page 2 of 7
ATTACHMENT 1 Evaluation of Proposed Changes analysis performed by Framatome, Inc. for DNPS, Units 2 and 3, Cycle 26, and Quad Cities Nuclear Power Station, Units 1 and 2, Cycle 25.
The proposed TS SLMCPR values were selected based on the cycle-specific SLMCPRs calculated for DNPS, Units 2 and 3, Cycle 26, and QCNPS Units 1 and 2, Cycle 25, and will be confirmed in the future on a cycle-specific basis. Bounding values relative to those reflected in Attachments 4 through 7 and 9 through 12 were selected to prevent the need for future changes to TS 2.1.1.2 on an emergent basis in the event that future cycle-specific calculations, including full core loads of ATRIUM 10XM fuel , would not be able to confirm that the lower values could be met. A single set of SLMCPR values for DNPS, Units 2 and 3, and QCNPS , Units 1 and 2, was selected to simplify implementation. The current cycle-specific SLMCPR values for DNPS, Units 2 and 3, and QCNPS , Units 1 and 2, as shown in Attachments 4 through 7 and 9 through 12, were developed with Framatome, Inc's NRG-approved SLMCPR methodology. These SLMCPRs were calculated using NRG-approved methodology described in ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors." By letter dated June 14, 2011, Topical Report ANP-10307P, Revision 0, was approved by the NRC (i.e., ADAMS Accession No. ML11140A125). The NRC letter approving Topical Report AN P-10307P states that the report is acceptable for referencing in licensing applications for boiling water reactors to the extent specified and under the limitations delineated in the topical report and in the final NRC safety evaluation . The final NRC safety evaluation concluded the topical report is acceptable for use for plant-specific licensing actions, without listing any limitations or conditions. A detailed discussion of the methodologies utilized for calculating the SLMCPRs for DNPS, Units 2 and 3, and QCNPS, Units 1 and 2 is provided in Section 3.0 of Attachments 4 through 7 and 9 through 12.
By letter dated October 20, 2016, Topical Report ANP-10307PA, Revision 0, was approved by the NRC as an analytical method used to determine the SLMCPR for DNPS, Units 2 and 3 and QCNPS , Units 1 and 2 (i.e., ADAMS Accession No. ML16218A485). Subsequent to that approval , ANP-10307PA has been used for determining core operating limits for DNPS, Unit 2 Cycle 26, DNPS, Unit 3, Cycles 25 and 26, QCNPC, Unit 1, Cycle 25, and QCNPS , Unit 2, Cycle 25.
The SLMCPR analysis establishes SLMCPR values which will ensure that at least 99.9% of the fuel rods in the core avoid boiling transition (BT) during normal operation or an anticipated operational occurrence (AOO) . The SLMCPR is determined using a statistical analysis employing a Monte Carlo process that perturbs the input parameters used in the calculation of minimum critical power ratio (MCPR). The set of uncertainties used in the statistical analysis includes both fuel-related and plant-related uncertainties. Details regarding the cycle-specific SLMCPR analyses are included in Attachments 4 through 7 (i.e., non-proprietary versions of the analyses), and 9 through 12 (i.e., proprietary versions of the analyses) . Those attachments summarize the methodology, inputs, and results for the proposed changes in the SLMCPRs.
No plant hardware or operational changes are required with these proposed changes.
Page 3 of 7
ATTACHMENT 1 Evaluation of Proposed Changes
4.0 REGULATORY EVALUATION
4.1 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met.
10 CFR 50.36, "Technical specifications," paragraph (c)(1), requires that power reactor facility TS include safety limits for process variables that protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. The SLMCPR analysis establishes SLMCPR values that will ensure that during normal operation and during abnormal operational transients, at least 99.9% of all fuel rods in the core do not experience transition boiling if the limit is not violated . Thus, the SLMCPR is required to be contained in TS.
10 CFR 50.36(c)(5) states that the TS will include administrative controls that address the provisions relating to organization and management, procedures, record keeping, review and audit, and reporting necessary to assure operation of the facility in a safe manner. The Core Operating Limits Report (COLR) is required as a part of the reporting requirements specified in the DNPS and QCNPS TS Administrative Controls section. The TS require the core operating limits to be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and to be documented in the COLR. In addition, it requires the analytical methods used to determine the core operating limits to be those that have been previously reviewed and approved by the NRC, and specifically to be those described in Technical Specification 5.6.5.b.
The proposed amendments ensure that these requirements are met.
General Design Criterion (GDC) 10, "Reactor design," of Appendix A to 10 CFR Part 50 states, "The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences."
4.2 Precedents
- 1. Letter from F. E. Saba (NRC) to J. W. Shea (TVA) , "Browns Ferry Nuclear Plant, Unit 1 -
Issuance of Amendment to Revise Technical Specifications Related to Cycle 12 Safety Limit Minimum Critical Power Ratio (CAC No. MF6760)," dated April 26, 2016 (ADAMS Accession No. ML16028A414)
- 2. Letter from A. Hon (NRC) to W . R. Gideon (Duke Energy), "Brunswick Steam Electric Plant, Units 1 and 2 - Issuance of Amendments to Revise Technical Specification Section 2.1.1.2, Safety Limit Minimum Critical Power Ratio (CAC Nos. MF8470 and MF8471)," dated March 10, 2017 (ADAMS Accession No. ML17059D146)
Page 4 of 7
ATTACHMENT 1 Evaluation of Proposed Changes 4.3 No Significant Hazards Consideration In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC, (EGC) is requesting a change to the Technical Specifications (TSs) of Renewed Facility Operating License (FOL) Nos. DPR-19 and DPR-25 for Dresden Nuclear Power Station (DNPS), Units 2 and 3, and Renewed FOL Nos. DPR-29 and DPR-30 for Quad Cities Nuclear Power Station (QCNPS) , Units 1 and 2.
Specifically, the proposed license amendments involve revising the Safety Limit Minimum Critical Power Ratio (SLMCPR) values contained in TS 2.1.1.2 for both two recirculation loop and single recirculation loop operation, for DNPS , Units 2 and 3, and QCNPS , Units 1 and 2.
According to 10 CFR 50 .92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
In support of this determination , an evaluation of each of the three criteria set forth in 10 CFR 50 .92 is provided below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed SLMCPR values have been determined using NRG-approved methods discussed in AREVA Topical Report ANP-10307PA, Revision 0, "AREVA MCPR Safety Limit Methodology for Boiling Water Reactors," dated June 2011. The proposed SLMCPRs for two recirculation loop and single recirculation loop operation ensure that the acceptance criterion continues to be met (i.e., at least 99.9 percent of all fuel rods in the core do not experience boiling transition).
The probability of an evaluated accident is derived from the probabilities of the individual precursors to that accident. The proposed license amendments do not involve any plant modifications or operational changes that could affect system reliability or performance, or that could affect the probability of operator error. As such, the proposed changes do not affect any postulated accident precursors. Since no individual precursors of an accident are affected , the proposed license amendments do not involve a significant increase in the probability of a previously analyzed event.
The consequences of an evaluated accident are determined by the operability of plant systems designed to mitigate those consequences. The basis for the SLMCPR calculations Page 5 of 7
ATTACHMENT 1 Evaluation of Proposed Changes is to ensure that during normal operation and during anticipated operational occurrences, at least 99.9 percent of all fuel rods in the core do not experience boiling transition if the safety limit is not exceeded .
Based on these considerations, the proposed changes do not involve a significant increase in the consequences of a previously analyzed accident.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
Creation of the possibility of a new or different kind of accident requires creating one or more new accident precursors. New accident precursors may be created by modifications of plant configuration, including changes in allowable modes of operation. The SLMCPR is a TS numerical value calculated for two recirculation loop operation and single recirculation loop operation to ensure at least 99.9 percent of all fuel rods in the core do not experience boiling transition if the safety limit is not exceeded . SLMCPR values are calculated using NRC-approved methodology identified in the TSs. The proposed SLMCPR values do not involve any new modes of plant operation or any plant modifications and do not directly or indirectly affect the failure modes of any plant systems or components. Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated .
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No.
The SLMCPR provides a margin of safety by ensuring that at least 99.9 percent of the fuel rods do not experience boiling transition during normal operation and anticipated operational occurrences if the MCPR Safety Limit is not exceeded. Revision of the SLMCPR values in TS 2.1.1 .2, using an NRC-approved methodology, will ensure that the current level of fuel protection is maintained by continuing to ensure that the fuel design safety criterion is met (i.e., that no more than 0.1 percent of the rods are expected to be in boiling transition if the MCPR Safety Limit is not exceeded). The SLMCPRs are verified to be bounding by cycle-specific analyses prior to power operations for each operating cycle. Therefore, the proposed amendments do not result in a significant reduction in the margin of safety.
Based on the above, EGC concludes that the proposed amendments do not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of no significant hazards consideration is justified .
4.4 Conclusions In conclusion , based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Page 6 of 7
ATTACHMENT 1 Evaluation of Proposed Changes
5.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendments would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendments do not involve (i) a significant hazards consideration, (ii) a significant change in the types or a significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendments meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b) , no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
Page 7 of 7
ATTACHMENT 2 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 Docket Nos. 50-237 and 50-249 Renewed Facility Operating License Nos. DPR-19 and DPR-25 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits Dresden Proposed Technical Specifications Changes MARKED-UP TS PAGE 2.0-1
SLs 2.0 2.0 SAFETY LIMITS (SLs)
flow< 10% rated core flow:
THERMAL POWER shall bes 25% RTP.
2.1.1.2 With the reactor steam dome pressure 2 685 psig and core ~
flow 2 10% rated core flow:
~, For two recirculation loop operation, MCPR shall be 2
~. or for sing}e~culation loop operation, MCPR shall be 2 -3:-:-+/--4.~
- 2. 1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall bes 1345 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.l Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
Dresden 2 and 3 2.0-1 Amendment No. 250/243
ATTACHMENT 3 QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 Docket Nos. 50-254 and 50-265 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits Quad Cities Proposed Technical Specifications Changes MARKED-UP TS PAGE
SLs 2.0 2.0 SAFETY LIMITS (SLs)
- 2. 1 SLs 2.1.l Reactor Core SLs 2.1.1.l With the reactor steam dome pressure< 685 psig or core flow< 10% rated core flow:
THERMAL POWER shall be~ 25% RTP.
2.1.1.2 With the reactor steam dome pressure~ 685 psig and core~
flow~ 10% rated core flow:
~1 be~
. two recirculation loop operation, MCPR shall
. , or for single recirculation loop operation, MCPR shall be~ +-:-+/--4~
-Fe-f---tJnit 2, t',.'O recirculation loop operation, MCPR shall be> 1.12, or for single recirculation loop operation, MCPR shall be:?: 1.14.
2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.
2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be~ 1345 psig.
2.2 SL Violations With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:
2.2.l Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.
Quad Cities 1 and 2 2.0-1 Amendment No. 262/257
ATTACHMENT 4 DRESDEN NUCLEAR POWER STATION ,
UNITS 2 AND 3 Docket Nos. 50-237 and 50-249 Renewed Facility Operating License Nos. DPR-19 and DPR-25 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits FS1-0039283, "Dresden Unit 2 Cycle 26 SLMCPR Analysis,"
(Non-Proprietary Version)
IDENTIFICATION REVISION framat me FS1-0039283 2.0 Framatome I 11 I Fuel TOTAL NUMBER OF PAGES: 11 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version)
ADDITIONAL INFORMATION:
This is the Non-Proprietary Version of FS 1-0031933 Rev 2.0.
PROJECT Dresden Unit 2 Cycle 26 DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING None EIR - Engineering CATEGORY Information Report STATUS This document 1s electronically approved. Records regarding the signatures are stored 111 the Fuel BU Document Database. Any attempt to modify this file may subject employees to civil and criminal penalties. EDM Object Id: 090 1216780c 1e164 - Release date (YYYY/MMIDD). 2018i08i3 1 19:11:56 [Western European Time ]
Role Name Date iYYYY 1MM!DD) Organization
\l\lri ter STOUT Ryan 201il/08i31 01:06:34 Fra.matome lnc.
Reviewer CARR Darrell 20 18/03i31 02:08:08 Framalome lnc.
Approver BYRAM Morris 2018/08/31 02:46:38 Framalome !nc.
Approver SCHNEPP Robert 2018/08/31 19:08:40 Framatome Inc .
Classification Export AL: OE001 ECCN: OE001 RELEASE DAT A: Les marchandises portant la designation "AL inegal N" sont soumises a la rBglementation europeenne ou allemande en matiere de contr6te des exportations au sein ou hors de l'UE. Les marchandises portant la designation "ECCN inegal N" sont soumises a la reglementation americaine. Les marchandises portant les designations AL:N" ou "ECCN:N" peuvent, salon la destination ou !'utilisation finales du produit, egalement etre sou mises a autorisation.
Exoort classification AL : OE001 ECCN: OE001 Goods labeled with ~AL not equal to N" are subject to European or German export authorization when being exported within or out of the EU. Goods labeled with ~ E C CN not equal to N" are subject to US reexport au thorization. Even without a label, or with label ~AL: N" or "ECCN: N", authorization may be required due to the SAFETY RELATED DOCUMENT: y final whereabouts and purpose for which the goods are to be used.
Exportkennzeichnung AL: OE001 ECCN: OE001 CHANGE CONTROL RECORDS : France: N Die mil "AL ungleich N" gekennzeichneten GUter unlerliegen bei der Au sfuhr aus der EU bzw.
This document, when revised, must be USA: Y innergemeinschaftlichen Verbringung der europaischen bzw. deul schen Ausfuhrgenehmigungspflicht. Die mil "ECCN ungleich N" gekennzeichneten GUier unterliegen der US-Reexportgenehmigungspflicht. Auch ohne reviewed or approved by following regions: Germany: N Kennzeichen , bzw. bei Kennzeichen "AL: N" oder "ECCN: N", kann sich eine Genehmigungspflicht, unter anderem durch den Endverbleib und Verwendunaszweck der Goter, eraeben.
CW0 1L Rev. 5.1 - 05/02/18
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 2/11 REVISIONS REVISION DATE EXPLANATORY NOTES 2.0 See 151 page This is the Non-Proprietary Version of FS 1-0031933 Rev 2.0.
release date 1.0 8/29/2018 New document.
This document was created to facilitate the release of Rev 2.0 in order to keep the revision number the same as this document's Proprietary counterpart, FS1-0031933.
Framatome - Fuel This document is sub*ect to th e restricti ons set forth on the fi rst or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 3/11 TABLE OF CONTENTS
- 1. PURPOSE .................................................................... ............ ................................. .. .................. ........ 4
- 2. METHODOLOGY .. ..... .. ................................................ ......................................................................... 4
- 3. ANALYSIS .... ..... ........ ... ................ ................. ... ...... .. .... ... .. ............................................. ................... ... . 5
- 4. DISCUSSION OF RESULTS ................................................................ ................................................. 6
- 5. REFERENCES .... ...... ...... .. .. ..... .. ... ............................................................... ................................. ........ 7 LIST OF TABLES Table 1 Fuel and Plant Related Uncertainties Used in SLMCPR Analysis .... ...... .... .... .. .......... .. ....... .. .... ..... 8 Table 2 Results Summary of SLMCPR Analysis ......................................................................................... 9 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type ................................................. 9 LIST OF FIGURES Figure 1 Dresden Unit 2 Cycle 26 Core Loading Map ... .. .......................................................................... 10 Figure 2 Radial Power Distribution for Dresden Unit 2 Cycle 26 SLMCPR [ ] ..... 11 Framatome - Fuel Th is document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 4/11
- 1. PURPOSE The purpose of this report is to provide safety limit minimum critical power ratio (SLM CPR) results for Dresden Unit 2 in support of Cycle 26.
- 2. METHODOLOGY The two-loop operation (TLO) and single-loop operation (SLO) SLMCPRs were determined using the methodology presented in Reference 1. The SLMCPR is defined as the minimum value of the critical power ratio which ensures at least 99.9% of the fuel rods in the core avoid boiling transition (BT} during normal operation or an anticipated operational occurrence (AOO). The SLMCPR is determined using a statistical analysis employing a Monte Carlo process that perturbs the input parameters used in the calculation of minimum critical power ratio (MCPR). The set of uncertainties used in the statistical analysis includes both fuel-related and plant-related uncertainties.
The SLMCPR analysis is performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the operating limit MCPR (OLMCPR) and produce a MCPR equal to the SLMCPR during an AOO. [
]
In the Framatome methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis. [
]
Framatome - Fuel Th is document is sub 'ect to the restrictions set forth on the fi rst or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 5/11
[
]
This adjustment is a plant specific extension of the Reference 1 approved methodology and is discussed in Reference 2 Section 5.
- 3. ANALYSIS The core loading and cycle depletion from the Dresden Unit 2 Cycle 26 fuel cycle design was used as the basis of the SLMCPR analysis. Figure 1 presents the core loading, including the nuclear fuel design type, the cycle the fuel was originally loaded , and the number of assemblies of each nuclear fuel type for the fuel cycle. The cycle is made up of OPTIMA2 and ATRIUM' 10XM* fuel. Analyses were performed [
] for the Dresden Unit 2 power/flow map. The SLO calculations used a [
] The radial power distribution [ ] is presented in Figure 2.
The ACE/ATRIUM 10XM critical power correlation (Reference 4) is used for the ATRIUM 10XM fuel while the SPCB critical power correlation (Reference 5) is used for the OPTIMA2 fuel. The application of the SPCB critical power correlation to OPTIMA2 fuel [
]
The uncertainties used in the SLMCPR analysis are presented in Table 1. The radial and nodal power uncertainties used in the analysis include the combined effects of up to 40% of the TIP channels out-of-service , up to 50% of the LPRMs out-of-service , and an LPRM calibration interval of 2500 effective full power hours (EFPH) . The radial and nodal power uncertainties also allow for startup without 100% of the TIP channels available. Note however, that only 40% of the TIP channels can be out of service at any given time, including startup, as described above.
The Dresden Unit 2 Cycle 26 SLMCPR analysis supports a TLO SLMCPR of 1.08 and an SLO SLMCPR of 1.09. Table 2 presents a summary of the analysis results including the SLMCPR and the percentage of rods expected to experience BT. The percentages of the total number of fuel rods predicted to experience
- ATRIUM is a trademark of Framatome Inc.
Framatome - Fuel Thi s document is sub*ect to the restrictions set forth on th e fi rst or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 6/11 BT in the overall Monte Carlo statistical evaluation for each nuclear fuel type are presented in Table 3.
The results are for the limiting exposures from the design step-through .
- 4. DISCUSSION OF RESULTS The results support lower TLO and SLO SLMCPRs than the values currently applied at Dresden . This is primarily due to the application of the Framatome SAFLIM3D methodology. It is expected that lower SLMCPRs will be supported as more ATRIUM 10XM fuel is loaded since the additive constant uncertainty of the ATRIUM 10XM fuel is much lower than the value used for the OPTIMA2 fuel.
Framatome - Fuel This document is sub*ect to the restrictions set forth on th e fi rst or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 7/11
- 5. REFERENCES
- 1. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011.
- 2. ANP-3338P Revision 1, Applicability of AREVA BWR Methods to the Dresden and Quad Cities Reactors Operating at Extended Power Uprate, AREVA, August 2015.
Failed or Bypassed Instrumentation and Extended Calibration ," HDC:96 :012, May 6, 1996 (38-9043714-000).
- 4. ANP-10298P-A Revision 1, ACE/ATRIUM 10XM Critical Power Correlation, AREVA, March 2014.
- 5. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
- 6. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation 's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
- 7. FS1-0015517 Revision 2.0, "Critical Power Correlation and Associated Additive Constants for OPTIMA2 Fuel at Quad Cities Units 1 & 2 and Dresden Units 2 & 3," AREVA, August 31 , 2014.
- 8. EMF-2493(P) Revision 0, MICROBURN-B2 Based Impact of Failed/Bypassed LPRMs and TIPs, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Radial Bundle Power Uncertainty, Siemens Power Corporation, December 2000.
- 9. EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASM0-4/MICROBURN-B2, Siemens Power Corporation ,
October 1999.
- 10. Exelon TODI ES1700005 Revision 1, "Dresden Unit 2 Cycle 26 Plant Parameters Document,
March 17, 2017 (38-220184 7-002).
Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling : None Page 8/11 Table 1 Fuel and Plant Related Uncertainties Used in SLMCPR Analysis Parameter Uncertainty Reference Fuel-Related Uncertainties
[
]
Plant-Related Uncertainties Feedwater flow rate 0.271 Mlbm/hrt 10 Feedwater temperature 8.5°Ft 10 Core pressure 11 psigt 10 Total core flow TLO 2.50% 10 SLO 6.0% 10 Ranges of applicability for the ACE/ATRIUM 10XM correlation are presented in Reference 4. Ranges of applicability for the application of the SPCB correlation to OPTIMA2 fuel are presented in Reference 7.
t
[ 1 i
Uncertainty based on the application of the Reference 6 co-resident fuel methodology.
§ These uncertainties were determined using the methodology discussed in References 3 and 8.
[ 1 Framatome - Fuel This document is sub*ect to th e restriction s set forth on the first or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling : None Page 9/11 Table 2 Results Summary of SLMCPR Analysis SLMCPR Percentage of Rods in Boiling Transition TL0-1 .08 0.0922 SL0-1 .09 0.0307 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Nuclear Contribution of Total Rods Fuel Burn up Fuel Predicted To Be Design Status Type in BT(%)
TLO SLO 12 OPTIMA2 Twice burned [
13 OPTIMA2 Twice burned 14 OPTIMA2 Twice burned 15 OPTIMA2 Once burned 16 OPTIMA2 Once burned 17 OPTIMA2 Once burned 1 ATRIUM 10XM Fresh 2 ATRIUM 10XM Fresh 3 ATRIUM 10XM Fresh ]
Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 10/11 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 12 OPTIMA2 24 [
13 OPTIMA2 24 14 OPTIMA2 24 15 OPTIMA2 25 16 OPTIMA2 25 17 OPTIMA2 25 1 ATRIUM 10XM 26 2 ATRIUM 10XM 26 3 ATRIUM 10XM 26 1
Figure 1 Dresden Unit 2 Cycle 26 Core Loading Map Framatome - Fuel This docume nt is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039283 Rev. 2.0 Dresden Unit 2 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling : None Page 11/11 Figure 2 Radial Power Distribution for Dresden Unit 2 Cycle 26 SLMCPR [ 1 Framatome - Fuel This document is sub*ect to the restrict1ons set forth on the first or title a e
ATTACHMENT 5 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 Docket Nos. 50-237 and 50-249 Renewed Facility Operating License Nos. DPR-19 and DPR-25 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits FS1-0037607, "Dresden Unit 3 Cycle 26 SLMCPR Analysis,"
(Non-Proprietary Version)
IDENTIFICATION REVISION framat me FS1-0037607 2.0 I
Framatome 11 I Fuel TOTAL NUMBER OF PAGES: 11 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version)
ADDITIONAL INFORMATION:
This is the Non-Proprietary version of FS1-0037152 Rev 2.0.
PROJECT Dresden Unit 3 Cycle 26 DISTRIBUTION TO PURPOSE OF DISTRIBUTION MieAzuma HANDLING None Adrian Constantinescu EIR - Engineering Mark Lanza CATEGORY Information Report Earl Riley Paul Smith STATUS Ryan Stout Th is documen t is electronically approved. Records regardmg the signatures are stored in the Fuel BU Document Database. P..ny attem pt to modify this file may su r;ject employees to civil and crimi nal pena lties . EDl\:1 Object Id: 09012 16780c1e156 - Release date (YYYY!MMIDD ) : 20 18i08i31 22:24:26 PNestern Euro pea n T ime j Role Name Date rYYYY/MM'DDl Organiza1ion Writer STOUT Ryan 201fli08i31 21 :15:'.JO Framatome Inc.
Reviewer CARR Darrell 2018/08i3 I 22 :09:28 Framalome Inc .
.i\pprover BYRAM Morris 20 18/08i31 22 :21:12 Framalome Inc.
Approver SCHN EPP Robert 2018/08/31 22: 11 :06 Framatome Inc.
Classification Export AL: OE001 ECCN: OE001 RELEASE DATA: Les marchandises portant ta designation "AL inegal N" sont soumises a la regtementation europ9enne ou allemande en matiere de contr61e des exportations au sein ou hors de l'UE. Les marchandises portant ta designation "ECCN inegal N" sent soumises a ta r8glementation americaine. Les marchandises portant les designations "Al:N" ou "ECCN :N" peuvent, selon la destination ou !'utilisation finales du produit, 9galement etre soumises a autorisation.
Export classification AL: OE001 ECCN: OE001 Goods labeled with MAL not equal to W are subject to European or German export authorization when being exported within or out of the EU. Goods labeled with -EcCN not equal to N" are subject to US reexport au thorization. Even without a label. or with label ~Al: N" or MECCN: N", au thorization may be required due to the SAFETY RELATED DOCUMENT: y final whereabouts and purpose for which the goods are to be used.
Exportkennzeichnung AL: OE001 ECCN: OE001 CHANGE CONTROL RECORDS: France: N Die mit "AL ungleich N" gekennzeichneten Gi..iter unterliegen bei der Ausfuhr aus der EU bzw.
This document, when revised, must be USA: Y innergemeinschaftlichen Verbringung der europaischen bzw. deutschen Ausfuhrgenehmigungspf1icht. Die mit "ECCN ungleich N" gekennzeichneten GOter unterliegen der US-Reexportgenehmigungspflicht. Auch ohne reviewed or approved by following regions : Germany: N Kennzeichen, bzw. bei Kennzeichen "AL: N" oder "ECCN: N", kann sich eine Genehmigungspflicht, unter anderem durch den Endverbleib und Verwendunaszweck der Guter, eraeben.
CW01L Rev . 5.1 - 05/02118
No FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 2/11 REVISIONS REVISION DATE EXPLANATORY NOTES 2.0 See 151 page Added Proprietary brackets to Figures 1 and 2.
release date This is the Non-Proprietary version of FS1-0037152 Rev 2.0.
1.0 5/24/2018 New document.
This is the Non-Proprietary version of FS 1-0037152.
Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling : None Page 3/11 TABLE OF CONTENTS
- 1. PURPOSE ................................. .... .. ........ .... ....... .. ........ .... ...... ... ..... .. .... ..... ........... ... ............. .. .............. .4
- 2. METHODOLOGY .... .. .. .......... .. .... ....... ..... .. .. .... ..... .................................... .. ... ... .. ......... .. .. ... ..... .... ..... ..... 4
- 3. ANALYSIS .......................... .... ...... .. ... ... .. .... ....... .. ..... .... ..... .. ...... ... .. ... ....... ...... ...... .... .... ... ......... ........ .... . 5
- 4. DISCUSSION OF RES UL TS ..... ........ ....... ..... ....... .................. ................... .... ........ .. .. .. ..... ........... ...... .... 6
- 5. REFERENCES ...... .. .. .. ...... .......... ..... .. .... ... ..... .. ... ........ .. ........ ... ... ... .. ... ..... .... ... ..... .. .. ....... ...... ... ........ ... .. 7 LIST OF TABLES Table 1 Fuel and Plant Related Uncertainties Used in SLMCPR Analysis .. .... .. ............... ...... ... ... ...... .... ... .. 8 Table 2 Results Summary of SLMCPR Analysis ..... ... .................. ... ... ...... ..... ... .. ..... ...... ...... ... .. .. .......... .... ... 9 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type ..... ........ ..... .... ...... ...... ........... .. .. 9 LIST OF FIGURES Figure 1 Dresden Unit 3 Cycle 26 Core Loading Map ... .. .......... .. .... .... .... .... ................... ... .... .. ..... ...... ..... .. 10 Figure 2 Radial Power Distribution for Dresden Unit 3 Cycle 26 SLMCPR [ ] .... . 11 Framatome - Fuel Th is docume nt is sub*ect to the restrict ions set forth on the first or title a e
No FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 4/11
- 1. PURPOSE The purpose of this report is to provide safety limit minimum critical power ratio (SLMCPR) results for Dresden Unit 3 in support of Cycle 26.
- 2. METHODOLOGY The two-loop operation (TLO) and single-loop operation (SLO) SLMCPRs were determined using the methodology presented in Reference 1. The SLMCPR is defined as the minimum value of the critical power ratio which ensures at least 99.9% of the fuel rods in the core are expected to avoid boiling transition (BT) during normal operation or an anticipated operational occurrence (AOO). The SLMCPR is determined using a statistical analysis employing a Monte Carlo process that perturbs the input parameters used in the calculation of minimum critical power ratio (MCPR). The set of uncertainties used in the statistical analysis includes both fuel-related and plant-related uncertainties.
The SLMCPR analysis is performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the operating limit MCPR (OLMCPR) and produce a MCPR equal to the SLMCPR during an AOO. [
1 In the Framatome methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis. [
1 Framatome - Fuel This document is sub*ect to the restrictions set forth on the fi rst or title a e
No FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 5/11
[ ]
This adjustment is a plant specific extension of the Reference 1 approved methodology and is discussed in Reference 2 Section 5.
- 3. ANALYSIS The core loading and cycle depletion from the Dresden Unit 3 Cycle 26 fuel cycle design was used as the basis of the SLMCPR analysis . Figure 1 presents the core loading, including the fuel design type, the cycle the fuel was originally loaded, and the number of assemblies of each fuel type for the fuel cycle. The cycle is made up of OPTIMA2 and ATRIUM' 10XM* fuel. Analyses were performed [
] for the Dresden Unit 3 power/flow map.
The SLO calculations used a [ ] The radial power distribution [ ] is presented in Figure 2.
The ACE/ATRIUM 10XM critical power correlation (Reference 4) is used for the ATRIUM 10XM fuel while the SPCB critical power correlation (Reference 5) is used for the OPTIMA2 fuel. The application of the SPCB critical power correlation to OPTIMA2 fuel [
]
The uncertainties used in the SLMCPR analysis are presented in Table 1. The radial and nodal power uncertainties used in the analysis include the combined effects of up to 40% of the TIP channels out-of-service, up to 50% of the LPRMs out-of-service, and an LPRM calibration interval of 2500 effective full power hours (EFPH). The radial and nodal power uncertainties also allow for startup without 100% of the TIP channels available. Note however, that only 40% of the TIP channels can be out of service at any given time, including startup , as described above.
The Dresden Unit 3 Cycle 26 SLMCPR analysis supports a TLO SLMCPR of 1.06 and an SLO SLMCPR of 1.08. Table 2 presents a summary of the analysis results including the SLMCPR and the percentage of rods expected to experience BT. The percentages of the total number of fuel rods predicted to experience BT in the overall Monte Carlo statistical evaluation for each nuclear fuel type are presented in Table 3.
The results are for the limiting exposure from the design step-through.
- ATRIUM is a trademark of Framatome Inc.
Framatome - Fuel This document is sub*ect to th e restrictions set forth on the first or title a e
No FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 6/11
- 4. DISCUSSION OF RESULTS The results support lower TLO and SLO SLMCPRs than the values currently applied at Dresden. This is consistent with the application of the Framatome SAFLIM3D methodology. In addition , the increased number of ATRIUM 10XM assemblies also leads to a lower SLMCPR since the additive constant uncertainty for the ATRIUM 1OXM fuel is much lower than the value used for the OPTIMA2 fuel.
Framatome - Fuel This document is sub*ect to the restrictions set forth on th e first or title a e
No FS1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 7/11
- 5. REFERENCES
- 1. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011 .
- 2. ANP-3338P Revision 1, Applicability of AREVA BWR Methods to the Dresden and Quad Cities Reactors Operating at Extended Power Uprate, AREVA, August 2015.
Failed or Bypassed Instrumentation and Extended Calibration," HDC:96:012, May 6, 1996.
(38-9043714-000) .
- 4. ANP-10298P-A Revision 1, ACE/ATRIUM 10XM Critical Power Correlation, AREVA, March 2014.
- 5. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
- 6. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation, August 2000.
- 7. FS1-0015517 Revision 2.0, "Critical Power Correlation and Associated Additive Constants for OPTIMA2 Fuel at Quad Cities Units 1 & 2 and Dresden Units 2 & 3," AREVA, August 31 , 2014.
- 8. EMF-2493(P), Revision 0, MICROBURN-B2 Based Impact of Failed/Bypassed LPRMs and TIPs, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Radial Bundle Power Uncertainty, Siemens Power Corporation, December 2000.
- 9. EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASM0-4/MICROBURN-B2, Siemens Power Corporation ,
October 1999.
- 10. Exelon TOOi ES1800002 Revision 0, "Dresden Unit 3 Cycle 26 Plant Parameters Document (PPD) ," February 2018 (FS 1-0036095 Rev. 1.0).
Framatome - Fuel This document is sub*ect to th e restricti ons set forth on the first or title a e
No FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 8/11 Table 1 Fuel and Plant Related Uncertainties Used in SLMCPR Analysis Parameter Uncertainty Reference Fuel-Related Uncertainties Plant-Related Uncertainties Feedwater flow rate 0.271 Mlbm/hrt 10 Feedwater temperature 8.5°Ft 10 Core pressure 11 psigt 10 Total core flow TLO 2.50% 10 SLO 6.0% 10 Ranges of applicability for the ACE/ATRIUM 1OXM correlation are presented in Reference 4. Ranges of applicability for the application of the SPCB correlation to OPTIMA2 fuel are presented in Reference 7.
[
+ Uncertainty based on the application of the Reference 6 co-resident fuel methodology.
§ These uncertainties were determined using the methodology discussed in References 3 and 8.
[
Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 9/11 Table 2 Results Summary of SLMCPR Analysis SLMCPR Percentage of Rods in Boiling Transition TL0-1 .06 0.0403 SL0-1.08 0.0373 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Nuclear Contribution of Total Rods Fuel Burn up Fuel Predicted To Be Design Status Type in BT(%)
TLO SLO 4 OPTIMA2 Twice burned [
5 OPTIMA2 Twice burned 6 OPTIMA2 Twice burned 7 ATRIUM 10XM Once burned 8 ATRIUM 10XM Once burned 9 ATRIUM 10XM Once burned 10 ATRIUM 10XM Fresh 11 ATRIUM 10XM Fresh 12 ATRIUM 10XM Fresh 1 Framatome - Fuel This document is sub*ect to the restrictions set forth on the fi rst or ti tle a e
No FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Analysis (Non-Proprietary Version) framatome Handling : None Page 10/11 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 4 OPTIMA2 24 [
5 OPTIMA2 24 6 OPTIMA2 24 7 ATRIUM 10XM 25 8 ATRIUM 10XM 25 9 ATRIUM 10XM 25 10 ATRIUM 10XM 26 11 ATRIUM 10XM 26 12 ATRIUM 10XM 26 ]
Figure 1 Dresden Unit 3 Cycle 26 Core Loading Map Framatome - Fuel This document is sub*ect to the restrictions set forth on the fi rst or title a e
N° FS 1-0037607 Rev. 2.0 Dresden Unit 3 Cycle 26 SLMCPR Handling : None Page 11/11 Analysis (Non-Proprietary version) framatome Figure 2 Radial Power Distribution tor Dresden Unit 3 Cycle 26 SLMCPR [ ]
Framatome - Fuel This document is sub*ect to the restrictions set forth on the fi rst or title a e
ATTACHMENT 6 QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 Docket Nos. 50-254 and 50-265 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits FS1-0039279, "Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis,"
(Non-Proprietary Version)
IDENTIFICATION REVISION
'--~-F_s_1_-0_03_9_2_19~~~1 j~~-2._o~~ Framatome Fuel framat e TOTAL NUMBER OF PAGES: 10 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version)
ADDITIONAL INFORMATION:
This is the Non-Proprietary Version of FS1-0029827 Rev 2.0.
Quad Cities Unit 1 PROJECT Cycle 25 DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING None EIR - Engineering CATEGORY Information Report STATUS This document 1s electronically approved . Records regarding the signatures are stored in ihe Fuel BU Document Database . Any attempt to modify this file may subject em ployees to civil and criminal penalties . EDM Object Id: 0901216780cle149 - Release date (YYYY1MM!DD). 2018i08i31 19:13:39 piVestern European Time]
Role Name Date (YYYYIMM/DDl Orqan ization Wri ter STOUT Ryan 201iJi08/31 \l1:00:'.J7 Framatome Inc.
Reviewer CARR Darrell 2018/08/3 *1 02:11 :23 Framalome Inc.
Approver SCHNEPP Robert 2018/08/3*1 19:09:14 Framalome Inc.
Approver BYR/\M Morris 2018/08i31 02:51:47 Framatome Inc.
Classification Export AL: OE001 ECCN: OE001 RELEASE DAT A: Les marchandises portant la designation "AL inegal N" sent soumises a la r9glementation europeenne ou allemande en matiere de contr61e des exportations au sein ou hors de l'UE. Les marchandises portant la designation "ECCN inegal W sont soumises a ta r9glemen tation americaine. Les marchandises portant les designations "Al:N" ou "ECCN:N" peuvent , selon la destination ou !'u tilisation finales du produit. 9galement etre soumises a autorisation.
Export classification AL: OE001 ECCN: OE001 Goods labeled with ~ AL not equal to Ny are subject to European or German export authorization when being exported within or out of the EU. Good s labeled with ~ ECCN not equal to N" are subject to US reexport au thorization. Even withou t a label, or with label ~A l: N" or ~ ECCN : N". au thorization may be required due to the SAFETY RELATED DOCUMENT: y final whereabou ts and purpose for which the good s are to be used.
Exportkennzeichnung AL : OE001 ECCN: OE001 CHANGE CONTROL RECORDS: France: N Die mit "AL ungleich N" gekennzeichneten GOter unterliegen bei der Au sfuhr aus der EU bzw.
This document, when revised, must be USA: Y innergemeinschaftlichen Verbringung der europaischen bzw. deutschen Ausfuhrgenehmigungspflicht. Die mit "ECCN ungleich N" gekennzeichneten GUter unterliegen der US-Reexportgenehmigungspflicht. Auch ohne reviewed or approved by following regions: Germany: N Kennzeichen . bzw. bei Kennzeichen "AL : N" oder "ECCN: N", kann sich eine Genehmigungspflicht, unter anderem durch den Endverbleib und Verwendunaszweck der GUter, emeben.
CW01L Rev. 5.1 - 05/02/18
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 2/10 REVISIONS REVISION DATE EXPLANATORY NOTES 2.0 See 151 page This is the Non-Proprietary Version of FS1-0029827 Rev 2.0.
release date 1.0 8/29/2018 New document.
This document was created to facilitate the release of Rev 2.0 in order to keep the revision number the same as this document's Proprietary counterpart, FS 1-0029827.
Framatome - Fuel This document is sub*ect to the re strictions set forth on the fi rst or title a e
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 3/10 TABLE OF CONTENTS
- 1. PURPOSE .............................................................................................................................................4
- 2. METHODOLOGY .......................................... ........ ... ..... ... .... .. ... .... .. .......................... ... ......................... 4
- 3. ANALYSIS ..................... .... ... .. .................... .................. ... ...... ... ...... ................ ... .... .. ... .. ..... ........ .. .... .... .. 5
- 4. DISCUSSION OF RES ULTS ................................................................................................................. 6
- 5. REFERENCES ......................................................................................................................................6 LIST OF TABLES Table 1 Fuel and Plant Related Uncertainties Used in SLMCPR Analysis .................................................. 7 Table 2 Results Summary of SLMCPR Analysis ........ .. ...... ...... ...... ... .. .. ........ ...... ................................... ..... 8 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type .......... ....... .. ..... ........... .............. 8 LIST OF FIGURES Figure 1 Quad Cities Unit 1 Cycle 25 24 Month Design Core Loading Map .. ...... ....... .... ..... ........ .. .. ............ 9 Figure 2 Radial Power Distribution for Quad Cities Unit 1 Cycle 25 24 Month Design SLMCPR [ ] ...... .. .. ......... ................ .................... ......... ....... ............ ... 10 Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 4/10
- 1. PURPOSE The purpose of this report is to provide safety limit minimum critical power ratio (SLMCPR) results for the Quad Cities Unit 1 Cycle 25 24 month cycle design.
- 2. METHODOLOGY The two-loop operation (TLO) and single-loop operation (SLO) SLMCPRs were determined using the methodology presented in Reference 1. The SLM CPR is defined as the minimum value of the critical power ratio which ensures at least 99.9% of the fuel rods in the core avoid boiling transition (BT) during normal operation or an anticipated operational occurrence (AOO). The SLMCPR is determined using a statistical analysis employing a Monte Carlo process that perturbs the input parameters used in the calculation of minimum critical power ratio (MCPR). The set of uncertainties used in the statistical analysis includes both fuel-related and plant-related uncertainties.
The SLMCPR analysis is performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the operating limit MCPR (OLMCPR) and produce a MCPR equal to the SLMCPR during an AOO . [
]
In the Framatome methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis. [
]
Framatome - Fuel This document is sub*ect to the restrictions set forth on the fi rst or title a e
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1Cycle25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 5/10
[
] This adjustment is a plant specific extension of the Reference 1 approved methodology and is discussed in Reference 2 Section 5.
- 3. ANALYSIS The core loading and cycle depletion from the Quad Cities Unit 1 Cycle 25 24 month fuel cycle design was used as the basis of the SLMCPR analysis. Figure 1 presents the core loading, including the nuclear fuel type, the cycle the fuel was originally loaded, and the number of assemblies of each nuclear fuel type for the fuel cycle. The cycle is made up of OPTIMA2 and ATRIUM TM 1OXM* fuel. Analyses were performed [ ] for the Quad Cities Unit 1 power/flow map. The SLO calculations used a [
] The radial power distribution [
] is presented in Figure 2.
The ACE/ATRIUM 10XM critical power correlation (Reference 4) is used for the ATRIUM 10XM fuel while the SPCB critical power correlation (Reference 5) is used for the OPTIMA2 fuel. The application of the SPCB critical power correlation to OPTIMA2 fuel [
1 The uncertainties used in the SLMCPR analysis are presented in Table 1. The radial and nodal power uncertainties used in the analysis include the combined effects of up to 40% of the TIP channels out-of-service, up to 50% of the LPRMs out-of-service, and an LPRM calibration interval of 2500 effective full power hours (EFPH). The radial and nodal power uncertainties also allow for startup without 100% of the TIP channels available. Note however, only 40% of the TIP channels can be out of service at any given time , including startup, as described above.
The Quad Cities Unit 1 Cycle 25 24 month cycle SLMCPR analysis supports a TLO SLMCPR of 1.06 and an SLO SLMCPR of 1.08. Table 2 presents a summary of the analysis results including the SLMCPR and
- ATRIUM is a trademark of Framatome Inc.
Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 6/10 the percentage of rods expected to experience BT. The percentages of the total number of fuel rods predicted to experience BT in the overall Monte Carlo statistical evaluation for each nuclear fuel type are presented in Table 3. The results are for the limiting exposures from the design step-through.
- 4. DISCUSSION OF RESULTS The results support lower TLO and SLO SLMCPRs than the values currently applied at Quad Cities. This is primarily due to the application of the Framatome SAFLIM3D methodology.
- 5. REFERENCES
- 1. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011 .
- 2. ANP-3338P Revision 1, Applicability of AREVA BWR Methods to the Dresden and Quad Cities Reactors Operating at Extended Power Uprate, AREVA, August 2015.
Failed or Bypassed Instrumentation and Extended Calibration ," HDC :96:012 , May 6, 1996 (38-9043714-000).
- 4. ANP-10298P-A Revision 1, ACE/ATRIUM 10XM Critical Power Correlation, AREVA, March 2014.
- 5. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation, AREVA NP, September 2009.
- 6. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation 's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation , August 2000.
- 7. FS1-0015517 Revision 2.0, "Critical Power Correlation and Associated Additive Constants for OPTIMA2 Fuel at Quad Cities Units 1 & 2 and Dresden Units 2 & 3," AREVA, August 31 , 2014.
- 8. EMF-2493(P) Revision 0, MICROBURN-B2 Based Impact of Failed/Bypassed LPRMs and T/Ps, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Bundle Radial Power Uncertainty, Siemens Power Corporation, December 2000.
- 9. EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASM0-4/MICROBURN-B2, Siemens Power Corporation, October 1999.
October 25, 2016, (38-2201707-001 ).
Framatome - Fuel This document is sub*ect to th e restrictions set forth on the fi rst or title a e
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 7110 Table 1 Fuel and Plant Related Uncertainties Used in SLMCPR Analysis Parameter Uncertainty Reference Fuel-Related Uncertainties
[
1 Plant-Related Uncertainties Feedwater flow rate 0.229 Mlbm/hrt 10 Feedwater temperature 10 Core pressure 22.56 psigt 10 Total core flow TLO 2.50% 10 SLO 6.0% 10 Ranges of applicability for the ACE/ATRIUM 10XM correlation are presented in Reference 4. Ranges of applicability for the application of the SPCB correlation to OPTIMA2 fuel are presented in Reference 7.
t
[ 1
+ Uncertainty based on the application of the Reference 6 co-resident fuel methodology.
§ These uncertainties were determined using the methodology discussed in References 3 and 8.
[ 1 Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 8/10 Table 2 Results Summary of SLMCPR Analysis Percentage of Rods in SLMCPR Boiling Transition TL0-1.06 0.0513 SL0-1.08 0.0513 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Nuclear Contribution of Total Rods Fuel Fuel Burnup Predicted To Be Type Design Status in BT(%)
TLO SLO 35 OPTIMA2 Twice burned [
36 OPTIMA2 Twice burned 37 OPTIMA2 Twice burned 38 OPTIMA2 Once burned 39 OPTIMA2 Once burned 40 OPTIMA2 Once burned ATRIUM 10XM Fresh 2 ATRIUM 10XM Fresh 3 ATRIUM 10XM Fresh 1
Framatome - Fuel This documen t is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 9/10 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 35 OPTIMA2 23 [
36 OPTIMA2 23 37 OPTIMA2 23 38 OPTIMA2 24 39 OPTIMA2 24 40 OPTIMA2 24 1 ATRIUM 10XM 25 2 ATRIUM 10XM 25 3 ATRIUM 10XM 25 ]
Figure 1 Quad Cities Unit 1 Cycle 25 24 Month Design Core Loading Map Framatome - Fuel This document is sub*ect to th e restricti ons set forth on the fi rst or title a e
No FS 1-0039279 Rev. 2.0 Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 10/10 Figure 2 Radial Power Distribution for Quad Cities Unit 1 Cycle 25 24 Month Design SLMCPR [ ]
Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
ATTACHMENT 7 QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 Docket Nos. 50-254 and 50-265 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits FS1-0039286, "Quad Cities Unit 2 Cycle 25 SLMCPR Analysis,"
(Non-Proprietary Version)
IDENTIFICATION REVISION framat me FS1-0039286 2.0 Framatome I 11 I Fuel TOTAL NUMBER OF PAGES: 10 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version)
ADDITIONAL INFORMATION:
This is the Non-Proprietary Version of FS1 -0034209 Rev 2.0.
Quad Cities Unit 2 PROJECT Cycle 25 DISTRIBUTION TO PURPOSE OF DISTRIBUTION HANDLING None EIR - Engineering CATEGORY Information Report STATUS This document is electronically approved . Records regarding 1he signatures are stored in !he Fuel BU Document Database . Any attem pt to morJ1fy this file may <:ub1eci employees to civil and criminal penalties. EDM Object Id: 0901 21 6730c1e159 - Relea se date (YYYY!MM/DD )
- 2018i08i31 19:08:4 1 [Western European Tirne j Role Name 0 ,1te i YY YY/MM/DDl Organization Writer STOUT Ryan 2011.\/08/3 1 01 :06 :0() Framalome Inc.
Rov1owor CARR Darrell 2018/08/3*1 02:04 :32 Framalome Inc.
.4. pprO V(:.~r BYRAM Morns 2018/08/3*1 02: 42:28 Framalome Inc.
Approver SC HNEPP Robert 2013/08/31 *1 9: 07: 18 Framatome Inc.
Classification Export AL: OE001 ECCN: OE00 1 RELEASE DATA: Les marchandises portant la designation "AL inegal N" sont soumises a la r0g lementation eu ropeenne ou allemande en mati9re de contr61e des exportations au se in ou hors de l'UE. Les marchandises portant la designation "ECCN inegal N" sont soumises a la reglementation am9ricaine. Les marchandises porta nt les designations "AL:N" ou "ECC N:N" peuvent, seton la destination ou l'utilisation finales du produ it, 9galement etre soum ises a autorisation.
Export classifica tion AL: OE001 ECCN: OE001 Goods labeled with MAL not equal to W are subject to European or Gennan export au thorization when be ing exported within or out of the EU . Goods labeled with MECCN not equat to N" are subject to US reexport authorization. Even without a label, or with label MAL: N" or "ECCN: N", authorization may be required due to the SAFETY RELATED DOCUMENT: y final whereabouts and purpose for wh ich the goods are to be used.
Export kennzeichnung AL: OE001 ECCN: OE00 1 CHANGE CONTROL RECORDS: France: N Die mit "AL ungleich N" gekennzeichneten Gi.iter unterliegen bei der Ausfuhr aus der EU bzw.
This document, when revised , must be USA: Y innergemeinschaftlichen Verbringung der europa ischen bzw. deutschen Ausfu hrgenehmigungspflicht. Die mit "ECCN ungleich N" gekennzeichneten GOter untertiegen der US-Reexportgenehmigungspflicht. Auch ohne reviewed or approved by following regions : Germany: N Kennze ichen, bzw. bei Kennzeichen "AL: N" oder "ECCN: N", kann sich eine Genehmigungspflicht, unter anderem durch den Endverbleib und Verwendu naszweck der GOter, eraeben CW0 1l Rev . 5.1 - 05102/18
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 2/10 REVISIONS REVISION DATE EXPLANATORY NOTES 2.0 See 151 page This is the Non-Proprietary Version of FS1-0034209 Rev 2.0.
release date 1.0 8/29/2018 New document.
This document was created to facilitate the release of Rev 2.0 in order to keep the revision number the same as this document's Proprietary counterpart, FS 1-0034209.
Framatome - Fuel This documen t is sub*ect to the restrictions set forth on the fi rst or title a e
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 3/10 TABLE OF CONTENTS
- 1. PURPOSE .... ..... .... ..... .... ...... ..... ..... ........ .... ... .... ..... ... ... ..... ... ..... .. ..... ... ... ......... ..... .... .... .. .... .... .. ...... ..... ..4
- 2. METHODOLOGY .. .. .... ... .... ...... ... ... ....................... ...... ... ... ........ ... ... .... ...... .. ...... .... ..... ..... .... ............. .... .4
- 3. ANALYSIS .. ..... .... .. ...... ... ............ ... .. ... ....... ................... ;.......... .. .. .. .. .......... .. ..... .. .... .. .. .. .. .. ....... .. .. ..... .... . 5
- 4. DISCUSSION OF RESULTS .... ... ..... .... ......... ... .... ...... .. .... .. ...... ..... ... ...... ... ................ ...... .. ... ....... ........ .. 6
- 5. REFERENCES ... ... .. ........... ...... ... ... .. .. ...... ... ......... .... ... ..... .... .. ... ......... ... ... ..... ... ...... ... ............ .... .... ..... ... 6 LIST OF TABLES Table 1 Fuel and Plant Related Uncertainties Used in SLMCPR Analysis ... .. ........ .. ... .. ........ .. .. .. ... ..... ........ ?
Table 2 Results Summary of SLMCPR Analysis .. ..... .. .... .... ......... .. ..... ... .. .. .. .............. .. ........ ... ..... ........... .. .. 8 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type ......... .. ....... .. ....... ..... ... ............. .8 LIST OF FIGURES Figure 1 Quad Cities Unit 2 Cycle 25 Core Loading Map ...... .. .. .... .. ..... ...... ... .. ... .... ......... ... .... .. ... .... ..... ...... 9 Figure 2 Radial Power Distribution for Quad Cities Unit 2 Cycle 25 SLMCPR [
1.............................................................................................................................. 10 Framatome - Fuel This document is sub*ect to the restricti ons set forth on the fi rst or title a e
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 4/10
- 1. PURPOSE The purpose of this report is to provide safety limit minimum critical power ratio (SLMCPR) results for Quad Cities Unit 2 in support of Cycle 25.
- 2. METHODOLOGY The two-loop operation (TLO) and single-loop operation (SLO) SLMCPRs were determined using the methodology presented in Reference 1. The SLM CPR is defined as the minimum value of the critical power ratio which ensures at least 99.9% of the fuel rods in the core avoid boiling transition (BT) during normal operation or an anticipated operational occurrence (AOO). The SLMCPR is determined using a statistical analysis employing a Monte Carlo process that perturbs the input parameters used in the calculation of minimum critical power ratio (MCPR). The set of uncertainties used in the statistical analysis includes both fuel-related and plant-related uncertainties.
The SLMCPR analysis is performed with a power distribution that conservatively represents expected reactor operating states that could both exist at the operating limit MCPR (OLMCPR) and produce a MCPR equal to the SLMCPR during an AOO. [
]
In the Framatome methodology, the effects of channel bow on the critical power performance are accounted for in the SLMCPR analysis. [
]
Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 5/10
[
) This adjustment is a plant specific extension of the Reference 1 approved methodology and is discussed in Reference 2 Section 5.
- 3. ANALYSIS The core loading and cycle depletion from the Quad Cities Unit 2 Cycle 25 fuel cycle design was used as the basis of the SLMCPR analysis.
Figure 1 presents the core loading, including the fuel design type, the cycle the fuel was originally loaded, and the number of assemblies of each fuel type for the fuel cycle. The cycle is made up of OPTIMA2 and ATRIUMTM 10XM* fuel. Analyses were performed [
] for the Quad Cities Unit 2 power/flow map. The SLO calculations used a
[ ] The radial power distribution (
] is presented in Figure 2.
The ACE/ATRIUM 10XM critical power correlation (Reference 4) is used for the ATRIUM 10XM fuel while the SPCB critical power correlation (Reference 5) is used for the OPTIMA2 fuel. The application of the SPCB critical power correlation to OPTIMA2 fuel [
1 The uncertainties used in the SLMCPR analysis are presented in Table 1. The radial and nodal power uncertainties used in the analysis include the combined effects of up to 40% of the TIP channels out-of-service, up to 50% of the LPRMs out-of-service, and an LPRM calibration interval of 2500 effective full power hours (EFPH). The radial and nodal power uncertainties also allow for startup without 100% of the TIP channels available. Note however, that only 40% of the TIP channels can be out of service at any given time, including startup, as described above.
The Quad Cities Unit 2 Cycle 25 SLMCPR analysis supports a TLO SLMCPR of 1.06 and an SLO SLMCPR of 1.08. Table 2 presents a summary of the analysis results including the SLMCPR and the ATRIUM is a trademark of Framatome Inc.
Framatome - Fuel This document is sub*ect to the restri ctions set fort h on the fi rst or title a e
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling : None Page 6/10 percentage of rods expected to experience BT. The percentages of the total number of fuel rods predicted to experience BT in the overall Monte Carlo statistical evaluation for each nuclear fuel type are presented in Table 3. The results are for the limiting exposures from the design step-through .
- 4. DISCUSSION OF RESULTS The results support lower TLO and SLO SLMCPRs than the values currently applied at Quad Cities. This is primarily due to the application of the Framatome SAFLIM3D methodology. Lower SLMCPRs may be supported as more ATRIUM 1OXM fuel is loaded since the additive constant uncertainty of the ATRIUM 10XM fuel is much lower than the value used for the OPTIMA2 fuel.
- 5. REFERENCES
- 1. ANP-10307PA Revision 0, AREVA MCPR Safety Limit Methodology for Boiling Water Reactors, AREVA NP, June 2011 .
- 2. ANP-3338P Revision 1, Applicability of AREVA BWR Methods to the Dresden and Quad Cities Reactors Operating at Extended Power Uprate, AREVA, August 2015.
Failed or Bypassed Instrumentation and Extended Calibration ," HDC:96:012 , May 6, 1996 (38-9043 714-000).
- 4. ANP-10298P-A Revision 1, ACE/ATRIUM 10XM Critical Power Correlation , AREVA, March 2014.
- 5. EMF-2209(P)(A) Revision 3, SPCB Critical Power Correlation , AREVA NP, September 2009.
- 6. EMF-2245(P)(A) Revision 0, Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel, Siemens Power Corporation , August 2000.
- 7. FS1-0015517 Revision 2.0, "Critical Power Correlation and Associated Additive Constants for OPTIMA2 Fuel at Quad Cities Units 1 & 2 and Dresden Units 2 & 3," AREVA, August 31, 2014.
- 8. EMF-2493(P) Revision 0, MICROBURN-B2 Based Impact of Failed/Bypassed LPRMs and TIPs, Extended LPRM Calibration Interval, and Single Loop Operation on Measured Radial Bundle Power Uncertainty, Siemens Power Corporation, December 2000.
- 9. EMF-2158(P)(A) Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors:
Evaluation and Validation of CASM0-4/MICROBURN-B2, Siemens Power Corporation ,
October 1999.
- 10. Exelon TOOi ES1700011 Revision 4, "Quad Cities Unit 2 Cycle 25 Plant Parameters Document,"
November 7, 2017. (FS1-0032866 Revision 5.0)
Framatome - Fuel This document is sub'ect to the restrictions set forth on the fi rst or title a e
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 7110 Table 1 Fuel and Plant Related Uncertainties Used in SLMCPR Analysis Parameter Uncertainty Reference Fuel-Related Uncertainties
[
]
Plant-Related Uncertainties Feedwater flow rate 0.229 Mlbm/hrt 10 Feedwater temperature 10 Core pressure 22 .56 psigt 10 Total core flow TLO 2.50% 10 SLO 6.0% 10 Ranges of applicability for the ACE/ATRIUM 1OXM correlation are presented in Reference 4. Ranges of applicability for the application of the SPCB correlation to OPTIMA2 fuel are presented in Reference 7.
t
[ ]
+ Uncertainty based on the application of the Reference 6 co-resident fuel methodology.
§ These uncertainties were determined using the methodology discussed in References 3 and 8.
[ ]
Framatome - Fuel This document is sub'ect to the restrictions set forth on the fi rst or title a e
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling : None Page 8/10 Table 2 Results Summary of SLMCPR Analysis Percentage of Rods in SLMCPR Boiling Transition TL0-1.06 0.0483 SL0-1 .08 0.0586 Table 3 Contribution of Total Predicted Rods in BT by Nuclear Fuel Type Nuclear Contribution of Total Rods Fuel Fuel Burn up Predicted To Be Type Design Status in BT(%)
TLO SLO 23 OPTIMA2 Twice burned [
24 OPTIMA2 Twice burned 25 OPTIMA2 Twice burned 41 OPTIMA2 Once burned 42 OPTIMA2 Once burned 43 OPTIMA2 Once burned 1 ATRIUM 10XM Fresh 2 ATRIUM 10XM Fresh 3 ATRIUM 10XM Fresh ]
Framatome - Fuel This documen t is sub*ect to the restrictions set forth on the fi rst or title a e
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling : None Page 9/10 Nuclear Fuel Cycle Number of Fuel Type Description Loaded Assemblies 23 OPTIMA2 23 [
24 OPTIMA2 23 25 OPTIMA2 23 41 OPTIMA2 24 42 OPTIMA2 24 43 OPTIMA2 24 1 ATRIUM 10XM 25 2 ATRIUM 10XM 25 3 ATRIUM 10XM 25 ]
Figure 1 Quad Cities Unit 2 Cycle 25 Core Loading Map Framatome - Fuel This document is sub*ect to the restrictions set forth on the first or title a e
No FS 1-0039286 Rev. 2.0 Quad Cities Unit 2 Cycle 25 SLMCPR Analysis (Non-Proprietary Version) framatome Handling: None Page 10/10 Figure 2 Radial Power Distribution for Quad Cities Unit 2 Cycle 25 SLMCPR [ ]
Framatome - Fuel This document is sub-ect to the restrictions set forth on th e first or title a e
ATTACHMENT 8 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 Docket Nos. 50-237 and 50-249 Renewed Facility Operating License Nos. DPR-19 and DPR-25 QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 Docket Nos. 50-254 and 50-265 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits Affidavit from Framatome, Inc. Attesting to the Proprietary Nature of Information in Attachments 9, 10, 11, and 12
AFFIDAVIT STATE OF WASHINGTON SS.
COUNTY OF BENTON
- 1. My name is Alan B. Meginnis. I am Manager, Product Licensing, for Framatome Inc. and as such I am authorized to execute this Affidavit.
- 2. I am familiar with the criteria applied by Framatome to determine whether certain Framatome information is proprietary. I am familiar with the policies established by Framatome to ensure the proper application of these criteria.
- 3. I am familiar with the Framatome information contained in the enclosures FS1-0029827, Revision 2; entitled "Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis,"
FS1 -0034209, Revision 2; entitled "Quad Cities Unit 2 Cycle 25 SLMCPR Analysis,"
FS1- 0031933, Revision 2; entitled "Dresden Unit 2 Cycle 26 SLMCPR Analysis," and FS1-0037152, Revision 2; entitled "Dresden Unit 3 Cycle 26 SLMCPR Analysis," referred to herein as "Documents." Information contained in these Documents has been classified by Framatome as proprietary in accordance with the policies established by Framatome for the control and protection of proprietary and confidential information.
- 4. These Documents contain information of a proprietary and confidential nature and are of the type customarily held in confidence by Framatome and not made available to the public. Based on my experience, I am aware that other companies regard information of the kind contained in these Documents as proprietary and confidential.
- 5. These Documents have been made available to the U.S. Nuclear Regulatory Commission in confidence with the request that the information contained in these Documents
be withheld from public disclosure. The request for withholding of proprietary information is made in accordance with 10 CFR 2.390. The information for which withholding from disclosure is requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial or financial information."
- 6. The following criteria are customarily applied by Framatome to determine whether information should be classified as proprietary:
(a) The information reveals details of Framatome's research and development plans and programs or their results.
(b) Use of the information by a competitor would permit the competitor to significantly reduce its expenditures, in time or resources, to design, produce, or market a similar product or service.
(c) The information includes test data or analytical techniques concerning a process, methodology, or component, the application of which results in a competitive advantage for Framatome.
(d) The information reveals certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides a competitive advantage for Framatome in product optimization or marketability.
(e) The information is vital to a competitive advantage held by Framatome, would be helpful to competitors to Framatome, and would likely cause substantial harm to the competitive position of Framatome.
The information in these Documents is considered proprietary for the reasons set forth in paragraphs 6(c) and 6(d) above.
- 7. In accordance with Framatome's policies governing the protection and control of information, proprietary information contained in these Documents have been made available, on a limited basis, to others outside Framatome only as required and under suitable agreement providing for nondisclosure and limited use of the information.
- 8. Framatome policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
- 9. The foregoing statements are true and correct to the best of my knowledge, information, and belief.
SUBSCRIBED before me this day of Oc dobe-r I 2018.
~#'/~/~
Hailey M Siekawitch NOTARY PUBLIC, STATE OF WASHINGTON MY COMMISSION EXPIRES: 9/28/2020
Proprietary Information -Withhold from Public Disclosure Under 10 CFR 2.390 ATTACHMENT 9 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 Docket Nos. 50-237 and 50-249 Renewed Facility Operating License Nos. DPR-19 and DPR-25 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits FS1-0031933, "Dresden Unit 2 Cycle 26 SLMCPR Analysis,"
(Proprietary Version)
Attachments 9, 10, 11, and 12 contain Proprietary Information.
Withhold from Public Disclosure Under 10 CFR 2.390.
When separated from Attachments 9, 10, 11, and 12, this document is decontrolled.
Proprietary Information -Withhold from Public Disclosure Under 10 CFR 2.390 ATTACHMENT 10 DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 Docket Nos. 50-237 and 50-249 Renewed Facility Operating License Nos. DPR-19 and DPR-25 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits FS1-0037152, "Dresden Unit 3 Cycle 26 SLMCPR Analysis,"
(Proprietary Version)
Attachments 9, 10, 11, and 12 contain Proprietary Information.
Withhold from Public Disclosure Under 10 CFR 2.390.
When separated from Attachments 9, 10, 11, and 12, this document is decontrolled.
Proprietary Information -Withhold from Public Disclosure Under 10 CFR 2.390 ATTACHMENT 11 QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 Docket Nos. 50-254 and 50-265 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits FS1-0029827, "Quad Cities Unit 1 Cycle 25 24 Month SLMCPR Analysis,"
(Proprietary Version)
Attachments 9, 10, 11, and 12 contain Proprietary Information.
Withhold from Public Disclosure Under 10 CFR 2.390.
When separated from Attachments 9, 10, 11, and 12, this document is decontrolled.
Proprietary Information -Withhold from Public Disclosure Under 10 CFR 2.390 ATTACHMENT 12 QUAD CITIES NUCLEAR POWER STATION, UNITS 1AND2 Docket Nos. 50-254 and 50-265 Renewed Facility Operating License Nos. DPR-29 and DPR-30 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limits FS1-0034209, "Quad Cities Unit 2 Cycle 25 SLMCPR Analysis,"
(Proprietary Version)
Attachments 9, 10, 11, and 12 contain Proprietary Information.
Withhold from Public Disclosure Under 10 CFR 2.390.
When separated from Attachments 9, 10, 11, and 12, this document is decontrolled.