RS-09-171, Supplemental Information Supporting the Request for a License Amendment to Modify Operating License in Support of the Use of Lsotope Test Assemblies

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 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 Nuclear Warrenville, IL 60555 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. ME1643),"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 14'h day of December 2009.

~ a n a g e-r 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 ~ t a c h ~

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.

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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.

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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 A 0 0 Analysis - Initial Condition Parameters

7. Selected Margin Improvement Options

8. Operating Flexibility Options

9. Core-wide A 0 0 Analysis Results

10. Rod Withdrawal Error A 0 0 Summary

11. 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 11-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 Fuel Type Number Loaded Irradiated:

GE14-P1OSNAB420-15GZ-120T-l50-T6-2870 (GE14C) 11 20 GE 14-P10SNAB419-14GZ-120T-150-T6-2871 (GE 14C) 11 16 GE 14-P 1OSNAl3417-15GZ-120T-150-T6-3028 (GE14C) 12 40 GE14-P1OSNAB418-14GZ-120T-150-T6-3027 (GE14C) 12 80 GE 14-P10SNAB418-1 5 - l20T-150-T6-3029 (GE 14C) 12 16 GE 14-P1OSNAB422-13GZ-120T-150-T6-3031 (GE14C) 12 52 GE 14-P1OSNAB422-15GZ-120T-150-T6-3025 (GE14C) 12 40 GE 14-P1OSNAB4 19-14GZ-120T-150-T6-3030 (GE 14C) 12 40 GE 14-P1OSNAB4 13-16GZ-120T-150-T6-3026 (GE14C) 12 24 New:

GE 14-P10SNAB418-15GZ-120T-150-T6-3241 (GE 14C) 13 72 GE14-P1OSNAB422-13GZ-120T-150-T6-3239 (GE14C) 13 56 GE14-PlOSNAB418-15GZ-120T-l50-T6-3242 (GE14C) 13 64 GE14I-PlOSCOB405- 13GZ-120T-150-T6-3243 (GE141) 13 8 GE14-PlOSNAB418-15GZ-120T-150-T6-3240 (GE14C) 13 96 Total: 624 Page 5

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0

3. Reference Core Loading Pattern Core Average Cycle Exposure Exposure 3441 6 MWdMT 207 17 M W d M T Nominal previous end-of-cycle exposure:

(3 1222 MWdST) (18794 MWdST)

Minimum previous end-of-cycle exposure (for cold 33733 MWdfMT 20034 MWcUMT shutdown considerations): (30603 MWdST) (18175 MWdST) 13298 MWd/MT 0 MWdMT Assumed reload beginning-of-cycle exposure:

(12064 MWdST) (0 MWcUST)

Assumed reload end-of-cycle exposure (rated 3 1985 MWd/MT 18686 MWdMT conditions): (29016 MWdST) (16952 MWdST)

Reference core loading pattern: Figure 1

4. -

Core Reactivity and Control System Worth No Voids, 20°C Cycle exposure at which R occurs

5. Standby Liquid Control System Shutdown Capability Shutdown Margin (Ak)

Boron (ppm)

(at 160°C, Xenon Free)

(at 20°C)

Analytical Requirement Achieved 850 LO.O1O 0.026 Page 6

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0

6. Reload Unique GETAB A 0 0 Analysis - Initial Condition Parameters '

Operating domain: ICF (HBB)

Exposure range : BOC to EOC ( Application Condition: 1,2,3,4 )

Peaking Factors Bundle Bundle Fuel Initial Local Radial Axial R-Factor Power Flow Design MCPR (MWt) (1000 lblhr)

GE14C 1.45 1.41 1.32 1.040 7.640 116.6 1.22 Operating domain: ICF & FWTR with PROOS (HBB)

Exposure range : BOC to EOC ( Application Condition: 2 )

Peaking Factors Bundle Bundle Fuel Initial Local Radial Axial R-Factor Power Flow Design MCPR (MWt) (1000 lblhr)

GE 14C 1.45 1.48 1.32 1.040 8.022 114.6 1.21 Operating domain: ICF & FWTR with TBVOOS (HBB)

Exposure range : BOC to EOC ( Application Condition: 4 )

Peaking Factors Bundle Bundle Fuel Initial Local Radial Axial R-Factor Power Flow Design MCPR (MWt) (1000 Iblhr)

GE 14C 1.45 1.42 1.32 1.040 7.704 116.6 1.27

' Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Selected Margin Improvement Options Recirculation pump trip: Yes Rod withdrawal limiter: Yes Thermal power monitor: Yes Improved scram time: Yes (ODYN Option B)

Measured scram time:

Exposure dependent limits:

Exposure points analyzed:

Table 7-1 Cycle Exposure Range Designation Name Exposure Range BOC to EOC BOC13 to EOC13 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.

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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: Yes Flow point analyzed throughout cycle: 107.0 %

Feedwater Temperature Reduction: Yes Feedwater temperature reduction during cycle: 120.0°F Final feedwater temperature reduction: 120.0°F ARTS Program: No Single Loop Operation: Yes Equipment Out of Service:

Safetylrelief valves Out of Service: Yes (credit taken for 14 valves)

ADS Out of Service: Yes PROOS: Yes 1 TCVOOS: Yes 1 TSVOOS: Yes 1 MSIVOOS: Yes 1 TBVOOS: Yes Turbine Bypass System 0 0 s : 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.

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Clinton 0000-0099-4244-SRLR Reload 12 Revision 0

9. Core-wide A 0 0 Analysis Results '

Methods used: GEMINI, GEXL-PLUS Operating domain: ICF (HBB)

Exposure range : BOC to EOC ( Application Condition: 1,2,3,4 )

Uncorrected ACPR Flux Q/A Event CE14C Fig.

(% rated) (% rated)

FW Controller Failure 125 104 0.09 2 Turbine Trip wlo Bypass 156 100 0.13 3 Load Rejection wlo Bypass 143 100 0.11 4 Operating domain: ICF & FWTR with PROOS (HBB)

Exposure range : BOC to EOC ( Application Condition: 2 )

Uncorrected ACPR Flux Q/A Event GE14C Fig.

(% rated) (% rated)

Pressure Regulator Failure 141 106 0.12 5 Operating domain: ICF & FWTR with TBVOOS (HBB)

Exposure range : BOC to EOC ( Application Condition: 4 )

Uncorrected ACPR Flux Q/A Event GE14C Fig.

(% rated) (% rated)

FW Controller Failure 171 107 0.18 6

10. Rod Withdrawal Error A 0 0 Summary A cycle specific Rod Withdrawal Error (RWE) analysis was performed to c o n f m 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.

'Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.

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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-~ressurizationEvents:

Exposure range: BOC to EOC All Fuel Types Rod Withdrawal Error 1.20 Loss of Feedwater Heating 1.22 Fuel Loading Error (Mislocated) 1.17 Fuel Loading Error (Misoriented) 1.26 Rated Equivalent SLO Pump Seizure " 1.24

• 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.

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Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 limit in^ Pressurization Events OLMCPR Summary Table:

APP~. Exposure Range Option A Option B Cond.

GE14C GE14C 1 Base (Includes TCV and/or TSV Stuck Closed)

BOC to EOC 1.35 1.25 2 PROOS (Includes TCV and/or TSV Stuck Closed)

BOC to EOC I 1.35 I 1.25 3 lTBVOOS BOC to EOC 1.35 1.25 4 Turbine Bypass System OOS BOC to EOC 1.40 1.30 Pressurization Events: l 3 l 2 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.

l 3 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.

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Clinton 0000-0099-4244-SRLR Reload 12 Revision 0

12. Overpressurization Analysis Summary PSI Pdome Pv Plant Event

(~sig) (psi& (psi@ Response MSIV Closure (Flux Scram) - ICF (HBB) 1294 1298 1322 Figure 7

13. Fuel Loading Error Results Variable water gap misoriented bundle analysis: Yes l4 Misoriented Fuel Bundle ACPR GEI4-P1OSNAB417-15GZ-120T-150-T6-3028 (GE14C) 0.13 GE14-PlOSNAB418-14GZ-120T-150-T6-3027 (GE14C) 0.16 GE14-P I OSNAB418- 15GZ-120T-150-T6-3029 (GE 14C) 0.12 GE14-PI 0SNAB422-13GZ-120T-150-T6-3031 (GE 14C) 0.16 GE14-PlOSNAB422-15GZ-120T-150-T6-3025(GE14C) 0.17 GE 14-P10SNAB419-14GZ-120T-150-T6-3030 (GE 14C) 0.16 GE14-PlOSNAB413-16GZ-12OT-150-T6-3026 (GE14C) 0.16 GE 14-P1OSNAB418-15GZ-120T-150-T6-3240 (GE14C) 0.16 GE 14-PlOSNAB418- 15GZ-120T-150-T6-3242 (GE 14C) 0.13 GE14-P1OSNAB422-13GZ-120T-150-T6-3239 (GE14C) 0.12 GE14-P10SNAB418-15GZ-120T-150-T6-3241 (GE14C) 0.12 GE 141-P1OSCOB405- 13GZ-120T-150-T6-3243 (GE141) 0.14 l4 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.

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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.

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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 OPRM Amplitude OLMCPR(SS) OLMCPR(2PT)

Setpoint 1.05 1.222 1.138 1.06 1.251 1.165 1.07 1.281 1.194 1.08 1.312 1.223 1.09 1.346 1.254 I

1.19 1.779 1.658 1.20 1.836 1.711 OLMCPR Off-rated Rated Power Acceptance OLMCPR OLMCPR (see Criteria (945% flow Section 11) 15.3 Backup Stability Protection 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.

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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.

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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-0000-0028-9714-R1, June 2005.

5. Backup Stability Protection (BSP) for Inoperable Option 111 Solution, 06-02-0 119-260, July 2002.

6. Supplemental Reload Licensing Report for Clinton Power Station Unit 1 Reload I 1 Cycle 12, 0000-0067-2201-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 Licensing Core-Wide Local Metal-Water Fuel Type Basis PCT Oxidation Reaction (OF) ("/.I ("/.I GE 14C 1570 < 1.00 < 0.10 GE14I 1570 < 1.00 < 0.10 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.

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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 10CFR50.46 Error Notifications PCT Impact Number Subject (OF)

Impact of SAFER Pressure Rate Inconsistency on the 2001-02 +5 PCT 2002-01 SAFER Core Spray Injection Elevation Error +15 Impact of SAFER04 Computer Platform Change on the 2002-04 0 PCT 2002-05 Impact of WEVOL S1 Volume Error on the PCT 0 2003-01 Impact of Safer LeveWolume Table Error on PCT +5 2003-05 Impact of Postulated Hydrogen-Oxygen Recombination 0 Impact of Top Peaked Power Shape for Small Break 2006-01 0 LOCA Analysis Total PCT Adder ( O F ) +25 The GE14C Licensing Basis PCT remains below the 10CFR50.46 limit of 2200 OF 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.

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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-P10SNAB417-15GZ-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-T6-3031 (GE14C)

GE 14-PlOSNAB422-15GZ-120T-150-T6-3025 (GE 14C)

GE 14-P10SNAB419-14GZ-120T-150-T6-3030 (GE 14C)

GE14-P10SNAB413-16GZ-120T-150-T6-3026 (GE14C)

GE14-P1OSNAB418-15GZ-120T-150-T6-3240 (GE14C)

GE 141-P1OSCOB405- 13GZ-120T-150-T6-3243 (GE 141)

GE 14-P10SNAB418-15GZ-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)

Average Planar Exposure MAPLHGR Limit GWdIMT GWdIST kW/ft 0.00 0.00 12.82 16.00 14.51 12.82 2 1.09 19.13 12.82 63.50 57.61 8.00 70.00 63.50 5 .OO 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.

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Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Table 16.3-2 Initial MCPR and Single Loop Operation Multiplier on LHGR and MAPLHGR Single Loop Operation Fuel Type Initial MCPR Multiplier on LHGR and MAPLHGR GE14C 1.270 0.76 GE14I 1.270 0.76 The ECCS-LOCA MAPLHGR limits bound a feedwater temperature reduction of 120 O F for both the GE14C and GE141 fuel types.

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 The SAFERIGESTR-LOCA analysis base reports applicable to the new cycle core are listed below.

References for GE14C

1. Project Task Report Clinton Power Station Extended Power Uprate Task T0407: ECCS-LOCA SAFEWGESTR, GE-NE-A22-00110-27-02, 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.

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Clinton 0000-0099-4244-SRLR Reload 12 Revision 0

++

ElElmEl mama Fuel Type A=GEI4-PlOSNAB417-15GZ-120T-150-T6-3028(Cycle 12) K=GE14-P1OSNAB418-15GZ-120T-150-T6-3240 (Cycle 13)

B=GEl4-PIOSNAB418-14GZ-120T-150-T6-3027(Cycle 12) L=GE14-P10SNAB418-15GZ-120T-150-T6-3242 (Cycle 13)

C=GE 14-PIOSNAB418-15GZ-120T-150-T6-3029 (Cycle 12) M=GE14-P1OSNAB418-15GZ-120T-150-T6-3241 (Cycle 13)

D=GE14-P10SNAB422-13GZ-120T-150-T6-3031 (Cycle 12) N=GE14I-P1OSCOB405-13GZ-120T-150-T6-3243 (Cycle 13)

E=GE14-P10SNAB422-15GZ-120T-150-T6-3025 (Cycle 12) O=GE14-P10SNAB418-15GZ-120T-150-T6-3242 (Cycle 13)

F=GE14-P10SNAB419-14GZ-120T-150-T6-3030(Cycle 12) P=GE14-PlOSNAB422-13GZ-120T-150-T6-3239(Cycle 13)

G=GE14-P1OSNAB413-16GZ-120T-l50-T6-3026(Cycle 12) Q=GE14-PIOSNAB4I8-15GZ-120T-150-T6-3241(Cycle 13)

H=GE14-P1OSNAB420-15GZ-120T-150-T6-2870 (Cycle 1 1) R=GE14-P10SNAB420-15GZ-120T-150-T6-2870(Cycle 1 1)

I=GE14-P10SNAB422-13GZ-120T-150-T6-3239 (Cycle 13) S=GE14-PlOSNAB419-14GZ-120T-l50-T6-2871 (Cycle 11)

J=GE14-PlOSNAB418-15GZ-120T-150-T6-3240 (Cycle 13)

Figure 1 Reference Core Loading Pattern Page 22

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0

-Ei-Neuhonflux/10 +- OOme Press Rise (psi) x A q SurFdce Hsat flux Valve flw iL--COrelnletflw ZZ%V*b

-+- Bypass Valve flm

-c Core Het Subcoding 150.0 -

-a- Level(incbREF-SEP-SKRT) x Vessel Steam flw 150 o +Turbine Steam Flow

-c- Feedwater Rcw Figure 2 Plant Response to FW Controller Failure

( EOC ICF (HBB) )

Page 23

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 NeLltron Flux110

-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 +Dome Press Rise (psi)

+Avg Surface Heat Flux

• c4Yelnlet~

00 30 60 T i (-)

rt Level(inchREF-SEP-SKRT)

-x- vessel Steam Flow m.0 ..-+ TLsbine Steam R w 1 .o

-e Feedwater Flanl h

E m

8 3 0.0 3

4 u"8 s i?

'F:

0.0 2 -1.0

-100.0 -2.0 0.0 3.0 6.0 0.0 3.0 6.0 T i (=) 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)

-u- Vessel Steam F b 200.0 ~~

--a-Turbine Steam Flow

-+--FdWaterFkM Figure 5 Plant Response to Pressure Regulator Failure

( EOC ICF & FWTR with PROOS (HBB) )

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Clinton 0000-0099-4244-SRLR Reload 12 Revision 0

• NeufrOnflux/IO

-+ AVJ SurFace Heat Flux

+- Bypass Valve F h 150.0 m.0 1

2 lW.0 s

50.0 0.0 0.0 5.0 10.0 T i (=)

+L&(inchREF-SEP-SKRT) *void ReactMty x Vessel Steam Fcw 3t Doppler Reach@

150o -n- Turbine Steam Flow +Scram R e c M y

-+- Fedwater Row TmI R e c M y 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) x- Vessel Stem Flow 3x0 -+TUFbine Steam R w FeedwaterFkW4 Figure 7 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)

Page 28

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 I n~ine 1 1 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 - t t + & t + - k t + t C t t + - t C - t + ! ~  ! ! ; I ; I ! i : I I i i i  : - k t t t C - + - 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 Analysis Value ICF ICF Parameter NFWT RFWT Thermal power, MWt 3473.0 3473.0 Core flow, Mlblhr 90.4 90.4 Reactor pressure (core mid-plane), psia 1056.4 1027.5 Inlet enthalpy, Btdlb 527.1 508.7 Non-fuel power fraction 0.036 0.036 Steam flow, Mlblhr 15.17 13.04 Dome pressure, psig 1025.0 997.6 Turbine pressure, psig 936.6 93 1.2 Table A-2 Pressure Relief and Safety Valve Configuration Number of Lowest Setpoint Valve Type Valves (psi&

Dual Mode SafetyIRelief Valve 1133.0 (Relief Mode) 1200.0 (Safety Mode) l 5 Only 14 of 16 safetyirelief valves are considered operational except for the MSIV Closure (Flux Scram) which used only 11 of 16 safetyirelief valves.

Page 3 1

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.

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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.

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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 10CFR Part 21 Communication SC05-03 (Reference D-8) have not changed.

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Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 MCPRp Limits for:

Equipment-In-Service Limits for Power < 33.3%

Power (%) Limit for Flow > 50.0% Limit for Flow 550.0%

MCPRp MCPRp 2 1.6 2.46 2.20 33.3 2.17 1.97 Limits for Power L 33.3%

Power (%) Limit Kp 33.3 1.351 70.0 1.212 70.0 1.150 100.0 1.ooo MCPRp Limits for:

PROOS Limits for Power < 33.3%

Power (%) Limit for Flow > 50.0% Limit for Flow 550.0%

MCPRp MCPRp 21.6 2.49 2.20 33.3 2.17 1.97 Limits for Power L 33.3%

Power (%) Limit MCPRp 33.3 2.170 70.0 1.673 100.0 1.310 MCPRp Limits for:

1 TBVOOS Limits for Power < 33.3%

Power (%) Limit for Flow > 50.0% Limit for Flow 5 50.0%

MCPRp MCPRp 21.6 2.46 2.20 33.3 2.17 1.97 Limits for Power L 33.3%

Power (%) Limit Kp 33.3 1.351 70.0 1.212 70.0 1.150 100.0 1.ooo Page 35

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 MCPRp Limits for:

TBSOOS Limits for Power < 33.3 %

Power (%) Limit for Flow > 50.0% Limit for Flow < 50.0%

MCPRp MCPRp 2 1.6 2.46 2.20 33.3 2.17 1.97 Limits for Power 2 33.3 %

Power (%) Limit Kp 33.3 1.351 70.0 1.212 70.0 1.150 100.0 1.ooo LHGRFACp Limits for:

Equipment-In-Service Limits for Power < 33.3%

Power (%) Limit for Flow > 50.0% Limit for Flow 150.0%

21.6 0.572 0.634 33.3 0.600 0.689 Limits for Power 2 33.3%

Power (%) Limit 33.3 0.689 100.0 1.ooo LHGRFACp Limits for:

PROOS Limits for Power < 33.3 %

Power (%) Limit for Flow > 50.0% Limit for Flow 5 50.0%

2 1.6 0.560 0.560 33.3 0.560 0.560 Limits for Power > 33.3%

Power (%) Limit 33.3 0.560 40.0 0.560 60.0 0.709 60.0 0.749 100.0 1.ooo Page 36

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 LHGRFACp Limits for:

1 TBVOOS Limits for Power < 33.3 %

Power (%) Limit for Flow > 50.0% Limit for Flow 1 50.0%

21.6 0.572 0.634 33.3 0.600 0.689 Limits for Power L 33.3%

Power (%) Limit 33.3 0.689 100.0 1.000 LHGRFACp Limits for:

TBSOOS Limits for Power < 33.3%

Power (%) Limit for Flow > 50.0% Limit for Flow 5 50.0%

21.6 0.572 0.634 33.3 0.600 0.689 Limits for Power > 33.3%

Power (%) Limit 33.3 0.689 100.0 1.ooo Off-Rated Flow Dependent Limits 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.

MCPRf Limits for:

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

Flow (%) Limit MCPRf 25.0 1.70 84.1 1.27 109.0 1.27 Page 37

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 MCPRf Limits for:

PROOS Limits for a Maximum Runout Flow of 109.0%

Flow (%) Limit MCPRf 25.0 1.70 84.1 1.27 109.0 1.27 MCPRf Limits for:

1 TBVOOS Limits for a Maximum Runout Flow of 109.0%

Flow ( O h ) Limit MCPRf 0.0 2.04 25.0 1.85 109.0 1.20 MCPRf Limits for:

TBSOOS Limits for a Maximum Runout Flow of 109.0%

Flow (%) Limit MCPRf 0.0 2.04 25.0 1.85 109.0 1.20 LHGRFACf Limits for:

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

Flow (%) Limit 25.0 0.612 30.0 0.646 82.2 1.OOO 109.0 1.OOO LHGRFACf Limits for:

PROOS Limits for a Maximum Runout Flow of 109.0%

Flow (%) Limit 25.0 0.612 30.0 0.646 82.2 1.OOO 109.0 1.OOO Page 38

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 1

LHGRFACf Limits for:

1 TBVOOS Limits for a Maximum Runout Flow of 109.0%

Flow (%) Limit 0.0 0.140 30.0 0.410 40.0 0.500 50.0 0.630 80.0 0.860 98.3 1.OOO 109.0 1 .OOO LHGRFACf Limits for:

TBSOOS Limits for a Maximum Runout Flow of 109.0%

Flow (%) Limit 0.0 0.140 30.0 0.4 10 40.0 0.500 50.0 0.630 80.0 0.860 98.3 1.OOO 109.0 1.OOO Page 39

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-0000-0026-1857-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 10CFR21 Reportable Condition NotiJication: Potential to Exceed Low Pressure Technical SpeciJication Limit, MFN 05-021, March 29,2005.

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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 Timesfor Clinton Power Station, GE-NE-0000-0000-7456-OlP, February 2002.

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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.

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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.

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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)

Highest Region Boundary Power Flow Core Channel Intercept (Yo) DR DR A1 (430°F) 49.7 3 1.6 0.797 0.392 B1 (430°F) 49.3 32.7 0.781 0.368 A2 (430°F) 55.8 39.0 0.798 0.349 B2 (430°F) 37.7 33.2 0.800 0.317 A1 (380°F) 53.7 36.5 0.796 0.370 B1 (380°F) 42.4 33.0 0.798 0.340 A2 (380°F) 61.5 46.1 0.797 0.303 B2 (38OoF) 38.4 33.2 0.788 0.3 11 Page 44

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 FWHOOS Feedwater Heaters Out of Senice FWTR Feedwater Temperature Reduction GDC General Design Criterion GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF Generic Shape Function HAL Haling Bum HBB Hard Bottom Bum HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection ICA Interim Corrective Action Page 46

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Acronym Description ICF Increased Core Flow IMCPR Initial MCPR IVM Initial Validation Matrix Kf Off-rated flow dependent OLMCPR multiplier Kp Off-rated power dependent OLMCPR multiplier L8 Turbine Trip on high water level (Level 8)

LCF Low Core Flow LHGR Linear Heat Generation Rate LHGRFACf Off-rated flow dependent LHGR multiplier LHGRFACp Off-rated power dependent LHGR multiplier LOCA Loss of Coolant Accident LPRM Local Power Range Monitor LRHBP Load Rejection with Half Bypass LRNBP Load Rejection without Bypass LTR Licensing Topical Report MAPFACf Off-rated flow dependent MAPLHGR multiplier MAPFACp Off-rated power dependent MAPLHGR multiplier MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MCPRf Off-rated flow dependent OLMCPR MCPRp Off-rated power dependent OLMCPR MELLLA Maximum Extended Load Line Limit Analysis MELLLA+ MELLLA Plus MOC Middle of Cycle MRB Maximal Region Boundaries MSIV Main Steam Isolation Valve MSIVOOS Main Steam Isolation Valve Out of Service MSR Moisture Separator Reheater MSROOS Moisture Separator Reheater Out of Service MTU Metric Ton Uranium MWd Megawatt day MWd/ST Megawatt days per Standard Ton MWd/MT Megawatt days per Metric Ton MWt Megawatt Thermal NIA Not Applicable NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature NOM Nominal Bum NTR Normal Trip Reference OLMCPR Operating Limit MCPR 00s Out of Service OPRM Oscillation Power Range Monitor Pbypass Reactor power level below which the TSV position and the TCV fast closure scrams are bypassed Page 47

Clinton 0000-0099-4244-SRLR Reload 12 Revision 0 Acronym Description Pdome Peak Dome Pressure Psl Peak Steam Line Pressure Pv Peak Vessel Pressure PCT Peak Clad Temperature PHE Peak Hot Excess PLHGR Peak Linear Heat Generation Rate PLU Power Load Unbalance PLUOOS Power Load Unbalance Out of Service PRFDS Pressure Regulator Failure Downscale PROOS Pressure Regulator Out of Servlce QIA Heat Flux RBM Rod Block Monitor RC Reference Cycle RCF Rated Core Flow RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Tnp RPTOOS Recirculation Pump Tnp Out of Service RV Relief Valve RVM Reload Validation Matnx RWE Rod Withdrawal Error SC Standard Cycle SL Safety Llmit SLMCPR Safety Limlt Mlnimum Critical Power Ratio SLO Single Loop Operation SRLR Supplemental Reload Licensing Report SIRV SafetyIRelief Valve SRVOOS SafetyIRelief Valve(s) Out of Service SS Steady State SSV Spnng Safety Valve STU Short Tons (or Standard Tons) of Uranium TBV Turbine Bypass Valve TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Servlce TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TRF Tnp Reference Function TSIP Technical Specifications Improvement Program TSV Turbine Stop Valve TSVOOS Turbine Stop Valve Out of Service TT Turbine Tnp TTHBP Turbine Tnp wlth Half Bypass TTNBP Turbine Tnp wlthout Bypass UB Under Bum - -

Page 48