ML093490375

Supplemental Information Supporting the Request for a License Amendment to Modify Operating License in Support of the Use of Lsotope Test Assemblies

ML093490375
Person / Time
Site:	Clinton
Issue date:	12/14/2009
From:	Hansen J L Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RS-09-171
Download: ML093490375 (51)

Text

Exelon Generation www.exeloncorp.com 4300 Winfield Road Warrenville, IL 60555 Nuclear 10 CFR 50.90 December 14,2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461

Subject:

Supplemental Information Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies

References:

1. Letter from Mr. Jeffrey L. Hansen (Exelon Generation Company, LLC) to U. S. NRC, "License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies," dated June 26, 2009 2. Letter from U. S. NRC to Mr. Charles G. Pardee (Exelon Generation Company, LLC), "Clinton Power Station, Unit No. 1 - Request for Additional lnformation Related to License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies (TAC No. ME1 643)," dated October 16,2009 (ADAMS Accession No. ML092800426)

3. Letter from Mr. Jeffrey L. Hansen (Exelon Generation Company, LLC) to U. S. NRC, "Additional lnformation Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies," dated November 4,2009 4. Letter from Mr. Jeffrey L. Hansen (Exelon Generation Company, LLC) to U. S. NRC, "Additional lnformation Supporting the Request for a License Amendment to Modify Clinton Power Station Facility Operating License in Support of the Use of lsotope Test Assemblies," dated November 17, 2009 In Reference 1, Exelon Generation Company, LLC (EGC) requested an amendment to the facility operating license for Clinton Power Station (CPS), Unit 1. Specifically, the proposed change would modify CPS License Condition 2.B.(6) and create new License Conditions 1 .J and 2.8.(7) as part of a pilot program to irradiate Cobalt (Co)-59 targets to December 14,2009 U. S. Nuclear Regulatory Commission Page 2 produce Co-60.

In addition to the proposed license condition changes, EGC also requests an amendment to Appendix A, Technical Specifications (TS), of the CPS Facility Operating License. This proposed change would modify TS 4.2.1, "Fuel Assemblies," to describe the Isotope Test Assemblies (ITAs) being used. In Reference 2, the NRC requested that EGC provide additional information in support of their review of Reference

1. The NRC request for additional information and the specific EGC responses were provided in References 3 and 4. In response to RAls 4 and 6, EGC agreed to provide the CPS Cycle 13 Supplemental Reload Licensing Report to the NRC. The attachment to this letter contains the final version of this report. EGC has reviewed the information supporting a finding of no significant hazards consideration that was previously provided to the NRC in Reference

4. The additional information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration.

No new regulatory commitments are established by this submittal.

If you have any questions concerning this letter, please contact Mr. Timothy A. Byam at (630) 657-2804. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1 4'h day of December 2009.

~anager - Licensing Exelon Generation Company, LLC

Attachment:

Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 12 Cycle 13 ATTACHMENT Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 12 Cycle 13 Global Nuclear Fuel A Jolnt Venture of GE, Toshtba, & H~tach~ 0000-0099-4244-SRLR Revision 0 Class I December 2009 Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload 12 Cycle 13 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Important Notice Regarding Contents of This Report Please Read Carefully This report was prepared by Global Nuclear Fuel - Americas, LLC (GNF-A) solely for use by Exelon ("Recipient")

in support of the operating license for Clinton (the "Nuclear Plant"). The information contained in this report (the "Information")

is believed by GNF-A to be an accurate and true representation of the facts known by, obtained by or provided to GNF-A at the time this report was prepared. The only undertakings of GNF-A respecting the Information are contained in the contract between Recipient and GNF-A for nuclear fuel and related services for the Nuclear Plant (the "Fuel Contract") and nothing contained in this document shall be construed as amending or modifying the Fuel Contract.

The use of the Information for any purpose other than that for which it was intended under the Fuel Contract, is not authorized by GNF-A. In the event of any such unauthorized use, GNF-A neither (a) makes any representation or warranty (either expressed or implied) as to the completeness, accuracy or usefulness of the Information or that such unauthorized use may not infringe privately owned rights, nor (b) assumes any responsibility for liability or damage of any kind which may result from such use of such information.

Page 2 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by GNF-AIGEH Nuclear Analysis personnel. The Supplemental Reload Licensing Report was prepared by G. M. Baka. This document has been verified by J. Su. Page 3 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Table of Contents I. Plant Unique Items

2. Reload Fuel Bundles 3. Reference Core Loading Pattern

4. Core Reactivity and Control System Worth - No Voids, 20°C

5. Standby Liquid Control System Shutdown Capability

6. Reload Unique GETAB A00 Analysis - Initial Condition Parameters

7. Selected Margin Improvement Options

8. Operating Flexibility Options

9. Core-wide A00 Analysis Results

10. Rod Withdrawal Error A00 Summary 1 1. Cycle SLMCPR and OLMCPR Summary

12. Overpressurization Analysis Summary

13. Fuel Loading Error Results

14. Control Rod Drop Analysis Results 15. Stability Analysis Results

16. Loss-of-Coolant Accident Results Appendix A Analysis Conditions Appendix B Thermal-Mechanical Compliance Appendix C Decrease in Core Coolant Temperature Event Appendix D Off-Rated Limits

Appendix E Option B Scram Speeds Appendix F Final Feedwater Temperature Reduction (FFWTR)

Appendix G GE 141 Fuel Introduction Appendix H Calculated BSP Region End Points Appendix I List of Acronyms Page 4 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 The basis for this report is General Electric Stundurd Application for Reactor Fuel, NEDE-240 1 1 -P-A- 16, October 2007, the U.S. Supplement, NEDE-24011-P-A-16-US, October 2007, and FLN-2007-036, Proposed GESTAR II Amendment 31, Stability Analysis and SRLR Template Update, December 7, 2007. 1. Plant Unique Items Appendix A: Analysis Conditions Appendix B: Thermal-Mechanical Compliance Appendix C: Decrease in Core Coolant Temperature Event Appendix D: Off-Rated Limits Appendix E: Option B Scram Speeds Appendix F: Final Feedwater Temperature Reduction (FFWTR) Appendix G:

GE14I Fuel Introduction Appendix H: Calculated BSP Region End Points Appendix 1: List of Acronyms

2. Reload Fuel Bundles Page 5 Fuel Type Irradiated:

GE14-P1OSNAB420-15GZ-120T-l50-T6-2870 (GE14C) GE 14-P 10SNAB419-14GZ- 120T- 150-T6-287 1 (GE 14C)

GE 14-P 1 OSNAl34 17- 15GZ- 120T- 150-T6-3028 (GE14C) GE14-P1OSNAB418-14GZ-120T-150-T6-3027 (GE14C) GE 14-P 10SNAB4 18 l20T-150-T6-3029 (GE 14C) GE 14-P 1 OSNAB422-13GZ- 120T- 150-T6-303 1 (GE14C) GE 14-P1 OSNAB422-15GZ- 120T- 150-T6-3025 (GE14C) GE 14-P 1 OSNAB4 19- 14GZ- 120T- 150-T6-3030 (GE 14C)

GE 14-P 1 OSNAB4 13- 16GZ- 120T- 150-T6-3026 (GE14C) New: GE 14-P 10SNAB418-15GZ- 120T- 150-T6-324 1 (GE 14C) GE14-P1OSNAB422-13GZ-120T-150-T6-3239 (GE14C) GE14-PlOSNAB418-15GZ-120T-l50-T6-3242 (GE14C) GE14I-PlOSCOB405-13GZ-120T-150-T6-3243 (GE141) GE14-PlOSNAB418-15GZ-120T-150-T6-3240 (GE14C) Total: Loaded 11 11 12 12 12 12 12 12 12 13 13 13 13 13 Number 20 16 40 80 16 52 40 40 24 72 5 6 64 8 96 624 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 3. Reference Core Loading Pattern

4. Core Reactivity and Control System Worth - No Voids, 20°C Nominal previous end-of-cycle exposure:

Minimum previous end-of-cycle exposure (for cold shutdown considerations):

Assumed reload beginning-of-cycle exposure: Assumed reload end-of-cycle exposure (rated conditions):

Reference core loading pattern: Cycle exposure at which R occurs 5. Standby Liquid Control System Shutdown Capability Core Average Exposure 3441 6 MWdMT (3 1222 MWdST) 33733 MWdfMT (30603 MWdST) 13298 MWd/MT (12064 MWdST) 3 1985 MWd/MT (29016 MWdST) Cycle Exposure 207 17 MWdMT (1 8794 MWdST) 20034 MWcUMT (18175 MWdST) 0 MWdMT (0 MWcUST) 18686 MWdMT (16952 MWdST) Page 6 Figure 1 Boron (ppm) (at 20°C) 850 Shutdown Margin (Ak) (at 160°C, Xenon Free) Analytical Requirement LO.O1O Achieved 0.026 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 6. Reload Unique GETAB A00 Analysis - Initial Condition Parameters

' Operating domain: ICF (HBB) Exposure range

BOC to EOC ( Application Condition:

1,2,3,4 ) Fuel Design GE14C Operating domain: ICF & FWTR with PROOS (HBB) Exposure range

BOC to EOC ( Application Condition:

2 ) ' Exposure range designation is defined in Table 7-1. Application condition number is defined in Section

11. Fuel Design GE 14C Operating domain: ICF & FWTR with TBVOOS (HBB) Exposure range

BOC to EOC ( Application Condition:

4 ) Page 7 Fuel Design GE 14C Peaking Factors R-Factor 1.040 Local 1.45 Peaking Factors R-Factor 1.040 Local 1.45 Peaking Factors Bundle Power (MWt) 7.640 Radial 1.41 R-Factor 1.040 Local 1.45 Axial 1.32 Bundle Power (MWt) 8.022 Radial 1.48 Bundle Flow (1000 lblhr) 116.6 Axial 1.32 Bundle Power (MWt) 7.704 Radial 1.42 Initial MCPR 1.22 Bundle Flow (1000 lblhr) 114.6 Axial 1.32 Initial MCPR 1.2 1 Bundle Flow (1000 Iblhr) 116.6 Initial MCPR 1.27 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Selected Margin Improvement Options Recirculation pump trip: Rod withdrawal limiter:

Thermal power monitor: Improved scram time: Measured scram time: Exposure dependent limits: Exposure points analyzed:

Yes Yes Yes Yes (ODYN Option B) Table 7-1 Cycle Exposure Range Designation Refer to the GESTAR basis document identified at the beginning of this report for the margin improvement options currently supported therein.

End of Rated (EOR) is defined as the cycle exposure corresponding to all rods out, 100%

power/100%

flow, and normal feedwater temperature. For plants without mid-cycle OLMCPR points, EOR is not applicable.

Name BOC to EOC Page 8 Exposure Range BOC13 to EOC13 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 8. Operating Flexibility Options ' The following information presents the operational domains and flexibility options which are supported by the reload licensing analysis. Inclusion of these results in this report is not meant to imply that these domains and options have been fully licensed and approved for operation. Extended Operating Domain (EOD):

Yes EOD type: Maximum Extended Operating Domain (MEOD) Minimum core flow at rated power: 99.0 % increased Core Flow:

Flow point analyzed throughout cycle: Feedwater Temperature Reduction:

Feedwater temperature reduction during cycle: Final feedwater temperature reduction: ARTS Program: Single Loop Operation: Equipment Out of Service:

Safetylrelief valves Out of Service: (credit taken for 14 valves) ADS Out of Service: PROOS: 1 TCVOOS: 1 TSVOOS: 1 MSIVOOS: 1 TBVOOS: Turbine Bypass System 00s: Yes 107.0 % Yes 120.0°F 120.0°F No Yes Yes Yes Yes Yes Yes Yes Yes Yes Refer to the GESTAR basis document identified at the beginning of this report for the operating flexibility options currently supported therein. FWHOOS is synonymous with "Feedwater temperature reduction during cycle". MSIVOOS applicable up to 75% rated power.

Page 9 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 9. Core-wide A00 Analysis Results ' Methods used: GEMINI, GEXL-PLUS Operating domain: ICF (HBB) Exposure range

BOC to EOC ( Application Condition:

1,2,3,4 ) Operating domain: ICF & FWTR with PROOS (HBB) Exposure range

BOC to EOC ( Application Condition:

2 ) 10. Rod Withdrawal Error A00 Summary Event FW Controller Failure Turbine Trip wlo Bypass Load Rejection wlo Bypass Operating domain: ICF & FWTR with TBVOOS (HBB) Exposure range

BOC to EOC ( Application Condition:

4 ) A cycle specific Rod Withdrawal Error (RWE) analysis was performed to confm that the results are bounded by the generic BWRl6 RWE analysis described in NEDE-24011-P-A-US. The results for the RWL RWE event are shown in Section 1 1 below. Uncorrected ACPR CE14C 0.09 0.13 0.11 Event Pressure Regulator Failure

' Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 1 1. Page 10 Fig. 2 3 4 Flux (% rated) 125 156 143 Uncorrected ACPR GE14C 0.12 Event FW Controller Failure Q/A (% rated) 104 100 100 Fig. 5 Flux (% rated) 141 Uncorrected ACPR GE14C 0.18 Q/ A (% rated) 106 Fig. 6 Flux (% rated) 171 Q/A (% rated) 107 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 11. Cycle SLMCPR and OLMCPR Summary 8 9 10 Two Loop Operation (TLO) safety limit: 1.09 Single Loop Operation (SLO) safety limit:

1.12 Stability MCPR Design Basis: See Section 15 ECCS MCPR Design Basis:

See Section 16 (Initial MCPR) Non-~ressurization Events:

• An adder of 0.07 should be applied to the GE14C OLMCPRs for the GE14I bundle. Exposure range designation is defined in Table 7-1. lo For SLO, the MCPR operating limit is 0.03 greater than the two loop value.

I' The cycle-independent OLMCPR for the recirculation pump seizure event while in SLO for GE14C is 1.43. When adjusted for the off-rated powerlflow conditions of SLO this limit corresponds to a rated OLMCPR of 1.24. Exposure range:

BOC to EOC Page 11 Rod Withdrawal Error Loss of Feedwater Heating Fuel Loading Error (Mislocated) Fuel Loading Error (Misoriented) Rated Equivalent SLO Pump Seizure " All Fuel Types 1.20 1.22 1.17 1.26 1.24 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 limit in^

Pressurization Events OLMCPR Summary Table: Pressurization Events: l3 l2 Each application condition (Appl.

Cond.) covers the entire range of licensed flow and feedwater temperature unless specified otherwise. The OLMCPR values presented apply to rated power operation based on the two loop operation safety limit MCPR. l3 Application condition numbers shown for each of the following pressurization events represent the application conditions for which this event contributed in the determination of the limiting OLMCPR value.

APP~. Cond. Page 12 Option A GE14C Exposure Range Option B GE14C 1 2 3 4 Base (Includes TCV and/or TSV Stuck Closed)

BOC to EOC 1.35 1.25 PROOS (Includes TCV and/or TSV Stuck Closed)

BOC to EOC 1.35 1.25 I I lTBVOOS BOC to EOC 1.35 1.25 Turbine Bypass System OOS 1.30 BOC to EOC 1.40 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 12. Overpressurization Analysis Summary

13. Fuel Loading Error Results Variable water gap misoriented bundle analysis:

Yes l4 Event MSIV Closure (Flux Scram) - ICF (HBB) l4 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

PSI (~sig) 1294 Misoriented Fuel Bundle GEI4-P1OSNAB417-15GZ-120T-150-T6-3028 (GE14C) GE14-PlOSNAB418-14GZ- 120T-150-T6-3027 (GE14C) GE14-P I OSNAB418-15GZ- 120T- 150-T6-3029 (GE 14C) GE14-PI 0SNAB422-13GZ- 120T- 150-T6-303 1 (GE 14C) GE14-PlOSNAB422-15GZ-120T-150-T6-3025 (GE14C) GE 14-P 10SNAB419-14GZ- 120T- 150-T6-3030 (GE 14C) GE14-PlOSNAB413-16GZ-12OT-150-T6-3026 (GE14C) GE 14-P 1 OSNAB4 18- 15GZ- 120T-150-T6-3240 (GE14C) GE 14-P lOSNAB418-15GZ- 120T- 150-T6-3242 (GE 14C) GE14-P1OSNAB422-13GZ-120T-150-T6-3239 (GE14C) GE14-P10SNAB418-15GZ-120T-150-T6-3241 (GE14C) GE 141-P 1 OSCOB405-13GZ- 120T- 150-T6-3243 (GE141) Page 13 ACPR 0.13 0.16 0.12 0.16 0.17 0.16 0.16 0.16 0.13 0.12 0.12 0.14 Pdome (psi& 1298 Pv (psi@ 1322 Plant Response Figure 7 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 14. Control Rod Drop Analysis Results Clinton Power Station is a banked position withdrawal sequence plant; therefore, the control rod drop accident analysis is not required.

NRC approval is documented in NEDE-24011 -P-A-US.

15. Stability Analysis Results 15.1 Stability Option 111 Solution Clinton has implemented BWROG Long Term Stability Solution Option 111 using the Oscillation Power Range Monitor (OPRM) as described in Reference 1 in Section 15.4. The plant specific Hot Channel Oscillation Magnitude (HCOM) (Reference 2 in Section 15.4) and other cycle specific stability parameters are used in the Cycle 13 Option I11 stability evaluation. Backup Stability Protection (BSP) regions are used by the plant in the event that the Option I11 OPRM system is declared inoperable. The following Option 111 OPRM stability setpoint determination described in Section 15.2 and the implementation of the associated BSP Regions described in Section 15.3 provide the stability licensing bases for Clinton Cycle 13.

15.2 Detect and Suppress Evaluation A reload Option 111 evaluation has been performed in accordance with the licensing methodology described in Reference 3 in Section 15.4. The stability based OLMCPR is determined for two conditions as a function of OPRM amplitude setpoint. The two conditions evaluated are: (1) a postulated oscillation at 45% rated core flow quasi steady-state operation (SS), and (2) a postulated oscillation following a two recirculation pump trip (2PT) from the limiting rated power operation state point. The OPRM-setpoint-dependent OLMCPR(SS) and OLMCPR(2PT) values are calculated for Cycle 13 in accordance with the BWROG regional mode DIVOM guidelines described in Reference 4 in Section 15.4. The Cycle 13 Option I11 evaluation provides adequate protection against violation of the SLMCPR for the two postulated reactor instability events as long as the plant OLMCPR is equal to or greater than OLMCPR(SS) and OLMCPR(2PT) for the selected OPRM setpoint in Table 15-2. The relationship between the OPRM Successive Confirmation Count Setpoint and the OPRM Amplitude Setpoint is provided in Reference 3 in Section 15.4 and Table 15-1. For intermediate OPRM Amplitude Setpoints, the corresponding OPRM Successive Confirmation Count Setpoints have been obtained by using linear interpolation. The OPRM setpoints for TLO are conservative relative to SLO and are, therefore, bounding.

Page 14 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Table 15-1 Relationship between OPRM Successive Confirmation Count Setpoint and OPRM Amplitude Setpoint Page 15 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Table 15-2 OPRM Setpoint Versus OLMCPR 15.3 Backup Stability Protection OPRM Amplitude Setpoint 1.05 1.06 1.07 1.08 1.09 The BSP region boundaries were calculated for Clinton Cycle 13 for normal and reduced feedwater temperature operation. The endpoints of the regions are defined in Tables 15-3 and 15-4. The region boundaries, shown in Figures 8 and 9, are defined using the Modified Shape Function (MSF).

See Reference 5 in Section 15.4. Page 16 OLMCPR(SS) 1.222 1.251 1.281 1.3 12 1.346 I OLMCPR(2PT) 1.138 1.165 1.194 1.223 1.254 1.19 1.20 OLMCPR Acceptance Criteria 1.779 1.836 Off-rated OLMCPR (945% flow 1.658 1.71 1 Rated Power OLMCPR (see Section 11)

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Table 15-3 BSP Region Intercepts for Normal Feedwater Temperature Table 15-4 BSP Region Intercepts for Reduced Feedwater Temperature Note that the Normal Feedwater Temperature Intercepts are for a feedwater temperature of 380°F or higher and the Reduced Feedwater Temperature Intercepts are for a feedwater temperature of 3 10°F or higher. The Cycle 12 BSP regions, defined in Reference 6 in Section 15.4, are bounding for Cycle

13. Note also that the OPRM Trip-Enabled Regions are confirmed.

Page 17 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 15.4 References

1. B WR Owners' Group Long-term Stability Soltitions Licensing Methodology, NEDO-3 1960-A, November 1995 (including Supplement 1). 2. Reactor Long-Term Stability Solution Option Ill: Licensing Basis Hot Channel Oscillation Magnitude for Clinton, GE-NE-0000-0035-0307-RO, September 2005.

3. Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology Jor Reload Applications, Licensing Topical Report, NEDO-32465-A, August 1996. 4. Plant-Specific Regional Mode DIVOM Procedure Guideline, GE-NE-0000-0028-97 14-R1, June 2005. 5. Backup Stability Protection (BSP) for Inoperable Option 111 Solution, 06-02-0 1 19-260, July 2002. 6. Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload I1 Cycle 12, 0000-0067-220 1 -SRLR, December 2007. 16. Loss-of-Coolant Accident Results 16.1 10CFR50.46 Licensing Results The ECCS-LOCA analysis is based on the SAFERIGESTR-LOCA methodology. The licensing results applicable to all fuel types in the new cycle are summarized in the following table. Table 16.1-1 Licensing Results The SAFEWGESTR-LOCA analysis results are documented in Reference 1 for GE14C in Section 16.4. This core contains GE14I Isotope Test Assemblies (ITAs), and the GE14C Licensing Results are applicable to these ITAs as described in the Technical Evaluation documented by Reference 1 for GE14I in Section 16.4.

Fuel Type GE 14C GE14I Page 18 Licensing Basis PCT (OF) 1570 1570 Local Oxidation

("/.I < 1.00 < 1.00 Core-Wide Metal-Water Reaction ("/.I < 0.10 < 0.10 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 16.2 10CFR50.46 Error Evaluation The 10CFR50.46 errors applicable to the Licensing Basis PCT are shown in the following table.

Table 16.2-1 Impact on Licensing Basis Peak Cladding Temperature for GE14C The GE14C Licensing Basis PCT remains below the 10CFR50.46 limit of 2200 OF 10CFR50.46 Error Notifications The GE14C 10CFR50.46 errors are applicable to the GE14I ITAs as described in the Technical Evaluation documented by Reference 1 for GE14I in Section 16.4, and the GE14I Licensing Basis PCT remains below 2200 OF. Page 19 PCT Impact (OF) +5 +15 0 0 +5 0 0 +25 Number 2001-02 2002-01 2002-04 2002-05 2003-01 2003-05 2006-01 Subject Impact of SAFER Pressure Rate Inconsistency on the PCT SAFER Core Spray Injection Elevation Error Impact of SAFER04 Computer Platform Change on the PCT Impact of WEVOL S1 Volume Error on the PCT Impact of Safer LeveWolume Table Error on PCT Impact of Postulated Hydrogen-Oxygen Recombination Impact of Top Peaked Power Shape for Small Break LOCA Analysis Total PCT Adder (OF)

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 16.3 ECCS-LOCA Operating Limits The ECCS-LOCA MAPLHGR limits for all bundles in this cycle are shown in the tables below.

Table 16.3-1 MAPLHGR Limits Bundle Type(s): GE 14-P 10SNAB4 17- 15GZ- 120T- 150-T6-3028 (GE 14C)

GE14-PlOSNAB418-14GZ-120T-150-T6-3027 (GE 14C) GE14-PlOSNAB418-15GZ-120T-150-T6-3029 (GE14C) GE14-PlOSNAB422- 13GZ-120T-150-T6-303 1 (GE14C) GE 14-PlOSNAB422-15GZ- 120T- 150-T6-3025 (GE 14C) GE 14-P 10SNAB4 19- 14GZ- 120T- 150-T6-3030 (GE 14C)

GE14-P10SNAB413-16GZ-120T-150-T6-3026 (GE14C) GE14-P1OSNAB418-15GZ-120T-150-T6-3240 (GE14C) GE 141-P 1 OSCOB405-13GZ- 120T- 150-T6-3243 (GE 141) GE 14-P 10SNAB4 18- 15GZ- 120T- 150-T6-3242 (GE 14C)

GE14-PlOSNAB422-13GZ-120T-150-T6-3239 (GE14C) GE14-P10SNAB418-15GZ-120T-150-T6-3241 (GE14C) GE14-PlOSNAB420-15GZ-120T-150-T6-2870 (GE14C) GE14-P10SNAB419-14GZ-120T-150-T6-2871 (GE14C) The single loop operation multiplier on LHGR and MAPLHGR, and the ECCS analytical initial MCPR values applicable to each fuel type in the new cycle core are shown in the table below.

Page 20 MAPLHGR Limit kW/ft 12.82 12.82 12.82 8.00 5 .OO Average Planar Exposure GWdIMT 0.00 16.00 2 1.09 63.50 70.00 GWdIST 0.00 14.5 1 19.13 57.61 63.50 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Table 16.3-2 Initial MCPR and Single Loop Operation Multiplier on LHGR and MAPLHGR The ECCS-LOCA MAPLHGR limits bound a feedwater temperature reduction of 120 OF for both the GE14C and GE141 fuel types.

Fuel Type GE14C GE14I The GE14C 10CFR50.46 initial MCPR and single loop operation multiplier on LHGR and MAPLHGR are applicable to the GE14I ITAs as described in the Technical Evaluation documented by Reference 1 for GE141 in Section 16.4. 16.4 References Initial MCPR 1.270 1.270 The SAFERIGESTR-LOCA analysis base reports applicable to the new cycle core are listed below. Single Loop Operation Multiplier on LHGR and MAPLHGR 0.76 0.76 References for GE14C 1. Project Task Report Clinton Power Station Extended Power Uprate Task T0407: ECCS- LOCA SAFEWGESTR, GE-NE-A22-00 1 10-27-02, Rev. 1, September 200

1. References for GE14I 1. Safety Analysis Report to Support Introduction of GEI4i Isotope Test Assemblies (ITAs) in Clinton Power Station, NEDC-33505P, Rev. 0, June 2009.

Page 2 1 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 ElElmEl ++ mama Figure 1 Reference Core Loading Pattern Fuel Type Page 22 A=GEI4-PlOSNAB417-15GZ-120T-150-T6-3028 (Cycle 12) B=GEl4-PIOSNAB418-14GZ-120T-150-T6-3027 (Cycle 12) C=GE 14-PI OSNAB4 18- 15GZ- 120T- 150-T6-3029 (Cycle 12) D=GE14-P10SNAB422-13GZ-120T-150-T6-3031 (Cycle 12) E=GE 14-P 10SNAB422-15GZ- 120T- 150-T6-3025 (Cycle 12) F=GE14-P10SNAB419-14GZ-120T-150-T6-3030 (Cycle 12) G=GE14-P1OSNAB413-16GZ-120T-l50-T6-3026 (Cycle 12) H=GE14-P1 OSNAB420-15GZ-120T-150-T6-2870 (Cycle 1 1) I=GE14-P10SNAB422-13GZ-120T-150-T6-3239 (Cycle 13) J=GE14-PlOSNAB4 18-1 5GZ-120T-150-T6-3240 (Cycle 13) K=GE14-P1OSNAB418-15GZ-120T-150-T6-3240 (Cycle 13) L=GE14-P10SNAB418-15GZ-120T-150-T6-3242 (Cycle 13) M=GE 14-P 1 OSNAB418-15GZ- 120T- 150-T6-3241 (Cycle 13) N=GE14I-P1OSCOB405-13GZ-120T-150-T6-3243 (Cycle 13) O=GE14-P10SNAB4 18- 15GZ- 120T- 150-T6-3242 (Cycle 13) P=GE14-PlOSNAB422-13GZ-120T-150-T6-3239 (Cycle 13) Q=GE14-PIOSNAB4I8-15GZ-120T-150-T6-3241 (Cycle 13) R=GE14-P10SNAB420-15GZ-120T-150-T6-2870 (Cycle 1 1) S=GE14-PlOSNAB419-14GZ-120T-l50-T6-2871 (Cycle 11)

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 -Ei-Neuhonflux/10 x Aq SurFdce Hsat flux iL--COrelnletflw -c Core Het Subcoding 150.0 - +- OOme Press Rise (psi) Valve flw ZZ%V*b -+- Bypass Valve flm 150 o Figure 2 Plant Response to FW Controller Failure ( EOC ICF (HBB) ) -a- Level(incbREF-SEP-SKRT) x Vessel Steam flw + Turbine Steam Flow -c- Feedwater Rcw Page 23 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 NeLltron Flux1 10 -x-AvgSurfaceWRux 6- Core Inlet FlcMI Figure 3 Plant Response to Turbine Trip w/o Bypass ( EOC ICF (HBB) ) Page 24 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 +~onflux/lO

+ Avg Surface Heat Flux *c4Yelnlet~

--- - + Dome Press Rise (psi) 00 30 60 Ti (-) rt Level(inchREF-SEP-SKRT) m.0 -x- vessel Steam Flow ..-+ TLsbine Steam Rw 1 .o -e Feedwater Flanl h E m

• 8 3 3 0.0 4 8 s u" i? 'F: .$ 0.0 2 -1.0 -100.0 -2.0 0.0 3.0 6.0 0.0 3.0 6.0 Ti (=) x-h-'? (-1 Figure 4 Plant Response to Load Rejection w/o Bypass ( EOC ICF (HBB) ) Page 25 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 -+ L&(imbREF-SEP-SKRT) 200.0 ~~ -u- Vessel Steam Fb --a- Turbine Steam Flow -+--F*dWaterFkM Figure 5 Plant Response to Pressure Regulator Failure ( EOC ICF & FWTR with PROOS (HBB) ) Page 26 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 *NeufrOnflux/IO

-+ AVJ SurFace Heat Flux m.0 +- Bypass Valve Fh 150.0 1 2 lW.0 s 50.0 0.0 0.0 5.0 10.0 Ti (=) 150 o *void ReactMty 3t Doppler Reach@ + Scram RecMy TmI RecMy + L&(inchREF-SEP-SKRT) x Vessel Steam Fcw -n- Turbine Steam Flow -+- Fedwater Row Figure 6 Plant Response to FW Controller Failure ( EOC ICF & FWTR with TBVOOS (HBB) ) Page 27 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 rt Level(incMiEF-SEP-SKRT) 3x0 x- Vessel Stem Flow -+ TUFbine Steam Rw FeedwaterFkW4 Figure 7 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB) Page 28 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 In ~ine 11 I 1 / --&--Extended Operating Domain -x- BSP Scram Reglon Boundary + BSP Controlled Entry Reglon Boundary I I 1 I 8 I , 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (%) Figure 8 BSP Region Boundaries for Normal Feedwater Temperature Operation Page 29 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0

• Extended Operating Domain +-----------

+ + ----- i-tt+&t+-kt+tCtt+-tC-t+!~

!!;I; I! i: I I i i i: -ktttC-+-t

-+ + Cii 0 10 20 30 40 50 60 70 80 90 100 110 120 Core Flow (%) Figure 9 BSP Region Boundaries for Reduced Feedwater Temperature Operation Page 30 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix A Analysis Conditions The reactor operating conditions used in the reload licensing analysis for this plant and cycle are presented in Table A-1. The pressure relief and safety valve configuration for this plant are presented in Table A-2. Additionally, the operating flexibility options listed in Section 8 are supported by the reload licensing analysis.

15 Table A-1 Reactor Operating Conditions Table A-2 Pressure Relief and Safety Valve Configuration Parameter Thermal power, MWt Core flow, Mlblhr Reactor pressure (core mid-plane), psia Inlet enthalpy, Btdlb Non-fuel power fraction Steam flow, Mlblhr Dome pressure, psig Turbine pressure, psig Analysis Value Valve Type l5 Only 14 of 16 safetyirelief valves are considered operational except for the MSIV Closure (Flux Scram) which used only 1 1 of 16 safetyirelief valves.

Page 3 1 ICF NFWT 3473.0 90.4 1056.4 527.1 0.036 15.17 1025.0 936.6 Dual Mode SafetyIRelief Valve ICF RFWT 3473.0 90.4 1027.5 508.7 0.036 13.04 997.6 93 1.2 Number of Valves 1133.0 (Relief Mode) 1200.0 (Safety Mode)

Lowest Setpoint (psi&

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix B Thermal-Mechanical Compliance A thermal-mechanical compliance check is performed for all analyzed transients to assure that the fuel will operate without violating the thermal-mechanical design limits. These limits are designed such that reactor operation within these limits provides assurance that the fuel will not exceed any thermal- mechanical design or licensing limits during all modes of operation. The fuel thermal-mechanical limits are met for the current cycle. Page 32 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix C Decrease in Core Coolant Temperature Event The Loss-of-Feedwater Heating event was analyzed at 100% rated power using the BWR Simulator Code. The use of this code is consistent with the approved methodology.

The transient plots, neutron flux and heat flux values normally reported in Section 9 are not an output of the BWR Simulator Code; therefore, those items are not included in this document. The OLMCPR result is shown in Section 1 1. Page 33 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix D Off-Rated Limits Off-Rated Power Dependent Limits The ARTS MCPRp and LHGRFACp thermal limits in this appendix have been validated this cycle for operation with Equipment-In-Service, PROOS, 1 Turbine Bypass Valve OOS (1 TBVOOS) and Turbine Bypass System OOS (TBSOOS). These limits support FFWTR of 120°F, 24 month cycle operation (Reference D-7) and the established EOOS options in References D-1 and D-2. The Effect of the PLU Power Level on Off-Rated Limits The results of Reference D-3 show that the generic Kp and LHGRFACp are validated, i.e., the PLU LRNBP is bounded by the Equipment-In-Service limits for the 0.3 14 second TT delay. The Effect of Feedwater Riser Flow Asymmetry on Thermal Limits The results of Reference D-4 show that the asymmetric effect in core enthalpy distribution on thermal limits due to the difference in flow to each of the 4 feedwater risers is insignificant. Reference D-4 concluded that for a feedwater riser flow deviation of 2.5% or less, the impact on MCPR thermal margins is less than 1% and no adjustment to the OLMCPRs is required. However, it was determined that when operating with FWHOOS or FFWTR up to 50°F, an adjustment of 1% to the LHGR limits is required.

The Effect of Rated Dome Pressure at Reactor Powers of 70% to 100% on Thermal Limits To reduce excessive recirculation pump shaft seal wear associated with pressure reductions, Reference D-5 supports operation between 70% and 100% rated thermal power with rated dome pressure. There is no impact to the licensing and analysis bases based on this operation. However, changes to the pressure regulator to maintain rated dome pressure as power decreases should be gradual in order to avoid a plant scram due to pressure and power perturbations. Shroud Repair Impact on Thermal Limits The analyses addressed in this report do not invalidate the statements made in Reference D-6 with respect to the shroud repair impact on Transient and Accident analyses for Clinton Power Station. Potential Violation of Low Pressure Technical Specification Limit Evaluations of Pressure Regulator Failure Maximum Demand (Open) transients have shown that the typical PRFO (for plants known to be vulnerable) results in the dome pressure dropping below 785 psig for a short duration (approximately 5 seconds). The recommendations associated with lOCFR Part 21 Communication SC05-03 (Reference D-8) have not changed. Page 34 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 MCPRp Limits for:

Equipment-In-Service Limits for Power

< 33.3% Power (%) 2 1.6 33.3 MCPRp Limits for:

PROOS Limits for Power

< 33.3% Page 35 Power (%) 21.6 33.3 MCPRp Limits for:

1 TBVOOS Limits for Power < 33.3% Limit for Flow > 50.0% MCPRp 2.46 2.17 Power (%) 21.6 33.3 Limit for Flow 550.0% MCPRp 2.20 1.97 Limits for Power L 33.3% Limit for Flow > 50.0% MCPRp 2.49 2.17 Power (%) 33.3 70.0 70.0 100.0 Limit for Flow 550.0% MCPRp 2.20 1.97 Limits for Power L 33.3% Limit for Flow > 50.0% MCPRp 2.46 2.17 Limit Kp 1.35 1 1.212 1.150 1 .ooo Power (%) 33.3 70.0 100.0 Limit for Flow 5 50.0% MCPRp 2.20 1.97 Limits for Power L 33.3% Limit MCPRp 2.170 1.673 1.310 Power (%) 33.3 70.0 70.0 100.0 Limit Kp 1.35 1 1.212 1.150 1 .ooo Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 MCPRp Limits for:

TBSOOS Limits for Power

< 33.3 % Power (%) 2 1.6 33.3 LHGRFACp Limits for:

Equipment-In-Service Limits for Power < 33.3% Page 36 Power (%) 21.6 33.3 LHGRFACp Limits for:

PROOS Limits for Power < 33.3 % Limit for Flow > 50.0% MCPRp 2.46 2.17 Power (%) 2 1.6 33.3 Limit for Flow < 50.0% MCPRp 2.20 1.97 Limits for Power 2 33.3 % Limit for Flow

> 50.0% 0.572 0.600 Power (%) 33.3 70.0 70.0 100.0 Limit for Flow 150.0% 0.634 0.689 Limits for Power 2 33.3% Limit for Flow

> 50.0% 0.560 0.560 Limit Kp 1.35 1 1.212 1.150 1 .ooo Power (%) 33.3 100.0 Limit for Flow 5 50.0% 0.560 0.560 Limits for Power > 33.3% Limit 0.689 1 .ooo Power (%) 33.3 40.0 60.0 60.0 100.0 Limit 0.560 0.560 0.709 0.749 1 .ooo Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 LHGRFACp Limits for:

1 TBVOOS Limits for Power < 33.3 % Off-Rated Flow Dependent Limits Power (%) 21.6 33.3 LHGRFACp Limits for:

TBSOOS Limits for Power

< 33.3% The ARTS MCPRf and LHGRFACf thermal limits in this appendix have been validated this cycle for operation with Equipment-In-Service, PROOS, 1 Turbine Bypass Valve OOS (1 TBVOOS) and Turbine Bypass System OOS (TBSOOS). These limits support FFWTR of 120°F, 24 month cycle operation (Reference D-7) and the established EOOS options in References D-1 and D-2. In addition, the flow dependent limits do not change the conclusions documented in References D-3, D-4, D-5, D-6 and D-8. Power (%) 21.6 33.3 Limit for Flow > 50.0% 0.572 0.600 Page 37 Limit for Flow 1 50.0% 0.634 0.689 Limits for Power L 33.3% Limit for Flow > 50.0% 0.572 0.600 MCPRf Limits for:

Equipment-In-Service Limits for a Maximum Runout Flow of 109.0%

Power (%) 33.3 100.0 Limit for Flow 5 50.0% 0.634 0.689 Limits for Power > 33.3% Flow (%) 25.0 84.1 109.0 Limit 0.689 1 .000 Power (%) 33.3 100.0 Limit MCPRf 1.70 1.27 1.27 Limit 0.689 1 .ooo Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 MCPRf Limits for:

PROOS Limits for a Maximum Runout Flow of 109.0% Flow (%) 25.0 84.1 109.0 MCPRf Limits for:

1 TBVOOS Limits for a Maximum Runout Flow of 109.0% Limit MCPRf 1.70 1.27 1.27 Flow (Oh) 0.0 25.0 109.0 MCPRf Limits for:

TBSOOS Limits for a Maximum Runout Flow of 109.0% Limit MCPRf 2.04 1.85 1.20 Flow (%) 0.0 25.0 109.0 LHGRFACf Limits for:

Equipment-In-Service Limits for a Maximum Runout Flow of 109.0% Page 38 Limit MCPRf 2.04 1.85 1.20 Flow (%) 25.0 30.0 82.2 109.0 LHGRFACf Limits for:

PROOS Limits for a Maximum Runout Flow of 109.0% Limit 0.612 0.646 1 .OOO 1 .OOO Flow (%) 25.0 30.0 82.2 109.0 Limit 0.612 0.646 1 .OOO 1 .OOO Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 1 LHGRFACf Limits for: 1 TBVOOS Limits for a Maximum Runout Flow of 109.0% Page 39 Flow (%) 0.0 30.0 40.0 50.0 80.0 98.3 109.0 LHGRFACf Limits for: TBSOOS Limits for a Maximum Runout Flow of 109.0% Limit 0.140 0.410 0.500 0.630 0.860 1 .OOO 1 .OOO Flow (%) 0.0 30.0 40.0 50.0 80.0 98.3 109.0 Limit 0.140 0.4 10 0.500 0.630 0.860 1 .OOO 1 .OOO Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 References for Appendix D: D-1 Evaluation of Operation With Equipment Out-Of-Service for the Clinton Power Station, GE-NE- 0000-0026-1 857-R1, June 28,2004. D-2 Clinton Power Station One Bypass Out of Service or Turbine Bypass System Out of Service Analysis-Final, 0000-0086-4634-R0, November 2008.

D-3 Clinton Off-Rated Analyses Below the PLU Power Level, GE-NE-0000-0042-4570-RO, September 2005. D-4 Clinton Assessment of Feedwater Riser Flow Deviation, GENE-0000-0030-8309-RO, March 2005. D-5 Clinton Power Station Operation at Rated Dome Pressure for Reactor Powers of 70% to 100%, GE-NE-0000-0036-8 186-00, April 2005. D-6 AmerGen Energy Co, LLC Clinton Power Station BWRVIP-04A Core Shroud Repair Design Submittal to the Nuclear Regulatory Commission (NRC), GENE-0000-0023-6259-05, Revision 0, March 2005. D-7 Clinton Power Station 24-Month Cycle Evaluation, TO900 Transient Analysis, GE-NE-0000-0038-5368-RO, June 2005. D-8 lOCFR21 Reportable Condition NotiJication:

Potential to Exceed Low Pressure Technical SpeciJication Limit, MFN 05-021, March 29,2005. Page 40 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix E Option B Scram Speeds An evaluation (Reference E-I) has been completed for Clinton Power Station (CPS) to derive Option B scram times that can be used in pressurization event transient analysis to improve MCPR operating limits (OLMCPR).

The CPS specific Option B scram times result in approximately 0.1 improvement in the OLMCPR for fast pressurization events such as the FWCF, LRNBP and TTNBP. The results of the pressurization events (FWCF, LRNBP and TTNBP) in Sections 6 and 9 with the corresponding figures are based on Option B scram times. The Pressure Regulator Failure event is based on Option A scram times. Reference for Appendix E: E-1 Option B Scram Times for Clinton Power Station, GE-NE-0000-0000-7456-OlP, February 2002. Page 41 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix F Final Feedwater Temperature Reduction (FFWTR)

The reload transient analyses were performed using a Final Feedwater Temperature Reduction (FFWTR) of 120.0°F. The 120.0°F FFWTR reported in Section 8 is not consistent with Reference F-1 and is not currently licensed for Clinton Power Station. The reload transient analyses do not by themselves allow plant operation with 120.0°F FFWTR but are bounding for the FFWTR of 50.0" F in Reference F- 1. Reference for Appendix F: F-1 Safety Analysis Report for Clinton Power Station Extended Power Uprate, NEDC-32989P, June 200 1. Page 42 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix G GE141 Fuel Introduction Reference G-1 provided the results of the cycle-independent evaluations supporting the introduction of GE141 fuel in Clinton Power Station.

These GE141 bundles, also referred to as GE141 Isotope Test Assemblies (ITAs), were designed for mechanical, nuclear and thermal-hydraulic compatibility with the GE14C fuel designs. The Cycle 13 core was designed such that the ITAs would be placed in non-limiting locations with respect to thermal limit margins and shutdown margins. Section 11 of this report presents the GE14C cycle-dependent MCPR limits; an adder of 0.07 should be applied to these results for the GE141 ITAs. References for Appendix G: G-1. Safety Analysis Report to Support Introduction ofGEI4i Isotope Test Assemblies (ITAs) in Clinton Power Station, NEDC-33505P Revision 0, GE Hitachi Nuclear Energy (Proprietary), June 2009; and Errata and Addenda Number I, December 4,2009. Page 43 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix H Calculated BSP Region End Points The BSP region end points reported in Section 15 represent the proposed BSP region. The proposed BSP region is conservative and bounds the calculated BSP region end points. To support the initial introduction of GE14I Isotope Test Assemblies (ITAs), this appendix provides the calculated BSP region end points and decay ratios. These calculated powerlflow points and decay ratios represent typical calculations for Clinton Power Station (CPS).

The plant- and cycle-specific calculations provide reasonable assurance that the thermal hydraulic stability as prescribed by Option I11 with respect to the size of the BSP regions is maintained with ITAs in the CPS core. Table H-1 BSP Region Calculated Intercepts for Normal Feedwater Temperature (380°F or higher) Page 44 Region Boundary Intercept A1 (430°F) B1 (430°F) A2 (430°F) B2 (430°F) A1 (380°F) B1 (380°F) A2 (380°F) B2 (38OoF) Power (Yo) 49.7 49.3 55.8 37.7 53.7 42.4 61.5 38.4 Flow 3 1.6 32.7 39.0 33.2 36.5 33.0 46.1 33.2 Core DR 0.797 0.781 0.798 0.800 0.796 0.798 0.797 0.788 Highest Channel DR 0.392 0.368 0.349 0.317 0.370 0.340 0.303 0.3 11 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Table H-2 BSP Region Calculated Intercepts for Reduced Feedwater Temperature (310°F or higher)

Page 45 Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Appendix I List of Acronyms Page 46 FWHOOS FWTR GDC GESTAR GETAB GSF HAL HBB HBOM HCOM HFCL HPCI ICA Feedwater Heaters Out of Senice Feedwater Temperature Reduction General Design Criterion General Electric Standard Application for Reactor Fuel General Electric Thermal Analysis Basis Generic Shape Function Haling Bum Hard Bottom Bum Hot Bundle Oscillation Magnitude Hot Channel Oscillation Magnitude High Flow Control Line High Pressure Coolant Injection Interim Corrective Action Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Page 47 Acronym ICF IMCPR IVM K f Kp L8 LCF LHGR LHGRFACf LHGRFACp LOCA LPRM LRHBP LRNBP LTR MAPFACf MAPFACp MAPLHGR MCPR MCPRf MCPRp MELLLA MELLLA+ MOC MRB MSIV MSIVOOS MSR MSROOS MTU MWd MWd/ST MWd/MT MWt NIA NBP NCL NFWT NOM NTR OLMCPR 00s OPRM Pbypass Description Increased Core Flow Initial MCPR Initial Validation Matrix Off-rated flow dependent OLMCPR multiplier Off-rated power dependent OLMCPR multiplier Turbine Trip on high water level (Level 8) Low Core Flow Linear Heat Generation Rate Off-rated flow dependent LHGR multiplier Off-rated power dependent LHGR multiplier Loss of Coolant Accident Local Power Range Monitor Load Rejection with Half Bypass Load Rejection without Bypass Licensing Topical Report Off-rated flow dependent MAPLHGR multiplier Off-rated power dependent MAPLHGR multiplier Maximum Average Planar Linear Heat Generation Rate Minimum Critical Power Ratio Off-rated flow dependent OLMCPR Off-rated power dependent OLMCPR Maximum Extended Load Line Limit Analysis MELLLA Plus Middle of Cycle Maximal Region Boundaries Main Steam Isolation Valve Main Steam Isolation Valve Out of Service Moisture Separator Reheater Moisture Separator Reheater Out of Service Metric Ton Uranium Megawatt day Megawatt days per Standard Ton Megawatt days per Metric Ton Megawatt Thermal Not Applicable No Bypass Natural Circulation Line Normal Feedwater Temperature Nominal Bum Normal Trip Reference Operating Limit MCPR Out of Service Oscillation Power Range Monitor Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Page 48 Acronym Pdome Psl Pv PCT PHE PLHGR PLU PLUOOS PRFDS PROOS QIA RBM RC RCF RFWT RPS RPT RPTOOS RV RVM RWE SC SL SLMCPR SLO SRLR SIRV SRVOOS S S SSV STU TBV TBVOOS TCV TCVOOS TCVSC TLO TRF TSIP TSV TSVOOS TT TTHBP TTNBP UB Description Peak Dome Pressure Peak Steam Line Pressure Peak Vessel Pressure Peak Clad Temperature Peak Hot Excess Peak Linear Heat Generation Rate Power Load Unbalance Power Load Unbalance Out of Service Pressure Regulator Failure Downscale Pressure Regulator Out of Servlce Heat Flux Rod Block Monitor Reference Cycle Rated Core Flow Reduced Feedwater Temperature Reactor Protection System Recirculation Pump Tnp Recirculation Pump Tnp Out of Service Relief Valve Reload Validation Matnx Rod Withdrawal Error Standard Cycle

Safety Llmit Safety Limlt Mlnimum Critical Power Ratio Single Loop Operation Supplemental Reload Licensing Report SafetyIRelief Valve SafetyIRelief Valve(s) Out of Service Steady State Spnng Safety Valve Short Tons (or Standard Tons) of Uranium Turbine Bypass Valve Turbine Bypass Valves Out of Service Turbine Control Valve Turbine Control Valve Out of Servlce Turbine Control Valve Slow Closure Two Loop Operation Tnp Reference Function Technical Specifications Improvement Program Turbine Stop Valve Turbine Stop Valve Out of Service Turbine Tnp Turbine Tnp wlth Half Bypass Turbine Tnp wlthout Bypass Under Bum - -