ML15029A640
| ML15029A640 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/29/2015 |
| From: | Borton K Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML15029A640 (66) | |
Text
10 CFR 50.90 January 29, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station, Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278
Subject:
MELLLA+ License Amendment Request - Supplement 1 Supplemental Reload Licensing Report
Reference:
- 1.
Exelon letter to the NRC, "License Amendment Request - Maximum Extended Load Line Limit Analysis Plus," dated September 4, 2014 (ADAMS Accession No. ML14247A503)
In accordance with 10 CFR 50.90, Exelon Generation Company, LLC (EGC) requested amendments to Facility Operating License Nos. DPR-44 and DPR-56 for Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3, respectively (Reference 1). Specifically, the proposed changes would revise the Renewed Operating Licenses to allow operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) operating domain which utilizes use of the Detect and Suppress - Confirmation Density (DSS-CD) stability solution.
This supplement provides a copy of the Supplemental Reload Licensing Report (SRLR) for PBAPS Unit 2 Cycle 21 in accordance with Section 1.1.1 of Reference 1 for NRC staff confirmation. This SRLR was prepared to specifically evaluate implementation of MELLLA+
during Unit 2 Cycle 21.
As the PBAPS MELLLA+ application is the first for multiple units, the following summary is also provided regarding any differences between the PBAPS Units 2 and 3 SRLRs. The Peach Bottom Unit 2 Cycle 21 MELLLA+ SRLR is representative of the Peach Bottom Unit 3 Cycle 21 MELLLA+ SRLR. The Peach Bottom Unit 2 Cycle 21 and Unit 3 Cycle 21 MELLLA+ SRLRs will both reflect:
Reactor cores comprised of GNF2 fuel at EPU (3951 MWt) conditions The MELLLA+ operating domain Transient analysis results based on bounding core flow conditions (MELLLA+ and ICF (Increased Core Flow))
Reload analysis performed using NRC-approved methodologies, consistent with GESTAR II (General Electric Standard Application for Reactor Fuel).
U. S. Nuclear Regulatory Commission MELLLA+ LAA Supplement 1 Supplemental Reload Licensing Report January 29, 2015 Page2 The only differences between the M+ SALA for each unit will be typical unit-specific differences like the individual bundle designs arid the core loading pattern; there are no differences related to the implementation of MELLLA+.
EGC has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration provided to the U.S. Nuclear Regulatory Commission in the referenced LAA. The supplemental information provided in this submittal does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. Further, the additional information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
In accordance with 1 O CFR 50.91, "Notice for public comment; State consultation,*
paragraph (b), EGC is notifying the Commonwealth of Pennsylvania and the State of Maryland of this application by transmitting a copy of this letter along with the attachments to the designated State Officials.
There are no regulatory commitments contained in this letter.
Should you have any questions concerning this letter, please contact Mr. David Neff at (610) 765-5631.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 29th day of January 2015.
Respectfully, Kevin F. Borton Manager, Licensing-Power Uprate Exelon Generation Company, LLC
Attachment:
Supplemental Reload Licensing Report for PBAPS Unit 2 Cycle 21 I
cc:
USNRC Region I, Regional Administrator USNRC Senior Resident Inspector, PBAPS USNRC Project Manager, PBAPS R. A. Janati, Commonwealth of Pennsylvania S. T. Gray, State of Maryland w/attachments w/attachments w/attachments w/attachments w/attachments
Peach Bottom Atomic Power Station Unit 2 MELLLA+ License Amendment Request - Supplement 1 Supplemental Reload Licensing Report for PBAPS Unit 2 Cycle 21
G Global Nuclear Fuel A Joint Venture of GE, Toshiba, & Hitachi 001N2150-SRLR Revision 1 Class I January 2015 Supplemental Reload Licensing Report for Peach Bottom Unit 2 Reload 20 Cycle 21 Extended Power Uprate (EPU)/Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
Copyright 2014 Global Nuclear Fuel-Americas, LLC All Rights Reserved
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 2 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 Corporation ("Recipient") in support of the operating license for Peach Bottom Unit 2 (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.
This SRLR is intended for the Extended Power Uprate (EPU) / Maximum Extended Load Line Limit Analysis Plus (MELLLA+) license for Peach Bottom Unit 2 Cycle 21. This SRLR is applicable for the MELLLA+ domain with a rated power of 3951 MWt.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 3 Acknowledgement The engineering and reload licensing analyses, which form the technical basis of this Supplemental Reload Licensing Report, were performed by GNF-A/GEH Nuclear Analysis personnel. The Supplemental Reload Licensing Report was prepared by Rachel Shapiro. This document has been verified by Mike Smith.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 4 Table of Contents
- 1.
Plant Unique Items 5
- 2.
Reload Fuel Bundles 5
- 3.
Reference Core Loading Pattern 6
- 4.
Calculated Core Effective Multiplication and Control System Worth 6
- 5.
Standby Liquid Control System Shutdown Capability 6
- 6.
Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 7
- 7.
Selected Margin Improvement Options 10
- 8.
Operating Flexibility Options 11
- 9.
Core-wide AOO Analysis Results 12
- 10. Rod Withdrawal Error AOO Summary 14
- 12. Overpressurization Analysis Summary 17
- 13. Fuel Loading Error Results 18
- 14. Control Rod Drop Analysis Results 18
- 15. Stability Analysis Results 19
- 16. Loss-of-Coolant Accident Results 23 Appendix A Analysis Conditions 44 Appendix B Thermal-Mechanical Compliance 45 Appendix C Decrease in Core Coolant Temperature Event 46 Appendix D Off-Rated Limits 47 Appendix E TRACG04 AOO Supplementary Information 52 Appendix F Interim Methods LTR (NEDC-33173P-A Revision 4) Supplemental Information 53 Appendix G MELLLA+ LTR (NEDC-33006P-A Revision 3) Supplemental Information 57 Appendix H List of Acronyms 60
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 5 The basis for this report is General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A-20, December 2013; and the U.S. Supplement, NEDE-24011-P-A-20-US, December 2013.
A proprietary Fuel Bundle Information Report (FBIR) supplements this licensing report. The FBIR references the thermal-mechanical linear heat generation rate limits and also provides a description of the fuel bundles to be loaded. The document number for this report is 001N6160.1-FBIR Revision 1.
- 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: TRACG04 AOO Supplementary Information Appendix F: Interim Methods LTR (NEDC-33173P-A Revision 4) Supplemental Information Appendix G: MELLLA+ LTR (NEDC-33006P-A Revision 3) Supplemental Information Appendix H: List of Acronyms
- 2. Reload Fuel Bundles Fuel Type Cycle Loaded Number Irradiated:
GNF2-P10DG2B406-12G6.0-100T2-150-T6-3337 (GNF2) 19 56 GNF2-P10DG2B393-15GZ-100T2-150-T6-3334 (GNF2) 19 20 GNF2-P10DG2B388-6G8.0/6G7.0/2G6.0-100T2-150-T6-3336 (GNF2) 19 36 GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (GNF2) 19 32 GNF2-P10DG2B392-15GZ-100T2-150-T6-3332 (GNF2) 19 4
GNF2-P10DG2B399-11G7.0/2G6.0-100T2-150-T6-4130 (GNF2) 20 48 GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (GNF2) 20 112 GNF2-P10DG2B397-14GZ-100T2-150-T6-4128 (GNF2) 20 40 GNF2-P10DG2B403-12GZ-100T2-150-T6-4129 (GNF2) 20 88 New:
GNF2-P10DG2B417-2G8.0/10G7.0-100T2-150-T6-4288 (GNF2) 21 88 GNF2-P10DG2B409-14GZ-100T2-150-T6-4287 (GNF2) 21 72 GNF2-P10DG2B402-13G8.0-100T2-150-T6-4286 (GNF2) 21 88 GNF2-P10DG2B403-14GZ-100T2-150-T6-4285 (GNF2) 21 80 Total:
764
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 6
- 3. Reference Core Loading Pattern Core Average Exposure Cycle Exposure Nominal previous end-of-cycle exposure:
37403 MWd/MT (33931 MWd/ST) 18005 MWd/MT (16334 MWd/ST)
Minimum previous end-of-cycle exposure (for cold shutdown considerations):
37072 MWd/MT (33631 MWd/ST) 17675 MWd/MT (16034 MWd/ST)
Assumed reload beginning-of-cycle exposure:
16822 MWd/MT (15261 MWd/ST) 0 MWd/MT (0 MWd/ST)
Assumed reload end-of-cycle exposure (rated conditions):
33467 MWd/MT (30361 MWd/ST) 16645 MWd/MT (15100 MWd/ST)
Reference core loading pattern:
Figure 1
- 4. Calculated Core Effective Multiplication and Control System Worth Beginning of Cycle, keffective Uncontrolled (20°C) 1.110 Fully controlled (20°C) 0.954 Strongest control rod out (most reactive condition, 20°C) 0.985 R, Maximum increase in strongest rod out reactivity during the cycle (k) 0.000 Cycle exposure at which R occurs 0 MWd/MT (0 MWd/ST)
- 5. Standby Liquid Control System Shutdown Capability Boron (ppm)
(at 20°C)
Shutdown Margin (k)
(at 160°C, Xenon Free)
Analytical Requirement Achieved 660 0.010 0.026
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 7
- 6. Reload Unique Anticipated Operational Occurrences (AOO) Analysis Initial Condition Parameters 1 Operating domain: ICF (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.42 1.48 0.98 7.321 122.5 1.64 Operating domain: ICF (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.37 1.32 0.97 7.098 127.2 1.61 Operating domain: MELLLA+ (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.41 1.47 0.98 7.307 91.5 1.43 Operating domain: MELLLA+ (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.37 1.26 0.98 7.108 95.1 1.43 1 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 8 Operating domain: ICF & FWTR (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.48 1.55 0.98 7.648 120.2 1.60 Operating domain: ICF & FWTR (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.38 1.32 0.97 7.114 127.9 1.64 Operating domain: MELLLA & FWTR (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.41 1.55 0.98 7.272 110.0 1.62 Operating domain: MELLLA & FWTR (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.37 1.30 0.97 7.076 114.4 1.60
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 9 Operating domain: ICF (UB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.38 1.25 0.97 7.130 126.0 1.70 Operating domain: MELLLA+ (UB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.36 1.40 0.97 7.050 93.2 1.53 Operating domain: ICF & FWTR (UB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.38 1.27 0.97 7.128 126.7 1.75 Operating domain: MELLLA & FWTR (UB)
Exposure range
( Application Condition: 1, 2, 3 )
Peaking Factors Fuel Design Local Radial Axial R-Factor Bundle Power (MWt)
Bundle Flow (1000 lb/hr)
Initial MCPR GNF2 1.0 1.37 1.27 0.97 7.091 113.3 1.69
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 10
- 7. Selected Margin Improvement Options 2 Recirculation pump trip:
Yes Rod withdrawal limiter:
No Thermal power monitor:
Yes Improved scram time:
Yes (Option B)
Measured scram time:
No Exposure dependent limits:
Yes Exposure points analyzed:
2 Table 7-1 Cycle Exposure Range Designation Name Exposure Range 3 BOC to MOC BOC21 to EOR21-4860 MWd/MT (4409 MWd/ST)
MOC to EOC EOR21-4860 MWd/MT (4409 MWd/ST) to EOC21 BOC to EOC BOC21 to EOC21 2 Refer to the GESTAR basis document identified at the beginning of this report for the margin improvement options currently supported therein.
3 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.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 11
- 8. Operating Flexibility Options 4 5 The following information presents the operational domains and flexibility options which are supported by the reload licensing analysis.
Extended Operating Domain (EOD):
Yes EOD type: Maximum Extended Load Line Limit Analysis Plus (MELLLA+)
Minimum core flow at rated power:
83.0 %
Increased Core Flow:
Yes Flow point analyzed throughout cycle:
110.0 %
Feedwater Temperature Reduction:
Yes Feedwater temperature reduction during cycle:
55.0°F Final feedwater temperature reduction:
90.0°F ARTS Program:
Yes Single Loop Operation:
Yes Equipment Out of Service:
Safety/relief valves Out of Service:
Yes (credit taken for 10 valves)
TBV Out-of-Service Yes EOC RPT Out-of-Service Yes 4 Refer to the GESTAR basis document identified at the beginning of this report for the operating flexibility options currently supported therein.
5 Feedwater Temperature Reduction and Single Loop Operation are prohibited in the MELLLA+ domain.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 12
Exposure range
( Application Condition: 1, 2, 3 )
Uncorrected CPR/ICPR Event Flux
(% rated)
(% rated)
GNF2 Fig.
Load Rejection w/o Bypass 206.4 104.4 0.133 2
FW Controller Failure 140.6 106.3 0.096 3
Operating domain: ICF (UB)
Exposure range
( Application Condition: 1, 2, 3 )
Uncorrected CPR/ICPR Event Flux
(% rated)
(% rated)
GNF2 Fig.
Load Rejection w/o Bypass 297.3 106.5 0.178 4
FW Controller Failure 186.1 108.1 0.151 5
Operating domain: ICF with TBVOOS (HBB)
Exposure range
( Application Condition: 2 )
Uncorrected CPR/ICPR Event Flux
(% rated)
(% rated)
GNF2 Fig.
Inadvertent HPCI /L8 183.3 112.6 0.141 6
FW Controller Failure 184.3 108.3 0.137 7
6 Exposure range designation is defined in Table 7-1. Application condition number is defined in Section 11.
7 The Heat Flux (Q/A) (% rated) output is not available from TRACG04, so the Simulated Thermal Power (STP) (%
rated) is shown.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 13 Operating domain: ICF with TBVOOS (UB)
Exposure range
( Application Condition: 2 )
Uncorrected CPR/ICPR Event Flux
(% rated)
(% rated)
GNF2 Fig.
Inadvertent HPCI /L8 227.4 114.1 0.187 8
FW Controller Failure 240.3 110.1 0.184 9
Operating domain: ICF with RPTOOS (HBB)
Exposure range
( Application Condition: 3 )
Uncorrected CPR/ICPR Event Flux
(% rated)
(% rated)
GNF2 Fig.
Load Rejection w/o Bypass 290.0 106.9 0.171 10 FW Controller Failure 231.8 110.2 0.154 11 Operating domain: ICF with RPTOOS (UB)
Exposure range
( Application Condition: 3 )
Uncorrected CPR/ICPR Event Flux
(% rated)
(% rated)
GNF2 Fig.
Load Rejection w/o Bypass 407.9 108.7 0.206 12 FW Controller Failure 319.1 111.9 0.193 13
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 14
- 10. Rod Withdrawal Error AOO Summary The Rod Withdrawal Error (RWE) event was analyzed in the GE BWR Licensing Report Maximum Extended Load Line Limit and ARTS Improvement Program Analyses for Peach Bottom Atomic Power Station Unit 2 and 3, NEDC-32162P, Rev. 2, March 1995.
RWE Results:
EIS and RPTOOS RBM Setpoint (%)
CPR 108.0 0.20 111.0 0.21 114.0 0.25 117.0 0.30 TBVOOS RBM Setpoint (%)
CPR 108.0 0.27 111.0 0.28 114.0 0.29 117.0 0.30 The more limiting of the cycle specific and the generic CPR values are reported in the table above. The RWE OLMCPR is determined by adding the CPR for the desired RBM setpoint from the table above to the SLMCPR in Section 11.
The ARTS RWE analysis validated that the following MCPR values provide the required margin for full withdrawal of any control rod during this cycle:
For Power < 90%: MCPR 1.70 For Power 90%: MCPR 1.40 The RBM operability requirements have been evaluated and shown to be sufficient to ensure that the SLMCPR and cladding strain criteria will not be exceeded in the event of a RWE.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 15
1.15 Single Loop Operation (SLO) safety limit:
1.15 Stability MCPR Design Basis:
See Section 15 ECCS MCPR Design Basis:
See Section 16 (Initial MCPR)
Non-pressurization Events:
Exposure range: BOC to EOC GNF2 Rod Withdrawal Error (114.0 % RBM Setpoint) 1.40 (EIS, RPTOOS) 1.44 (TBVOOS)
Loss of Feedwater Heating 1.27 Fuel Loading Error (Mislocated) 1.38 Fuel Loading Error (Misoriented) 1.35 Rated Equivalent SLO Pump Seizure 11 1.43 8 Exposure range designation is defined in Table 7-1.
9 For SLO, the MCPR operating limit is equal to the two loop value.
10 The safety limit values presented include a 0.02 adder in accordance with Interim Methods LTR Safety Evaluation Report Limitation and Condition 9.5, as noted in Appendix F.
11 The cycle-independent OLMCPR for the recirculation pump seizure event for GNF2 is 1.60 based on the cycle-specific SLO SLMCPR. When adjusted for the off-rated power/flow conditions of SLO, this limit corresponds to a rated OLMCPR of 1.43. This limit does not require an adjustment for the SLO SLMCPR.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 16 Limiting Pressurization Events OLMCPR Summary Table: 12 Appl.
Cond.
Exposure Range Option A Option B GNF2 GNF2 1
Equipment In Service BOC to MOC 1.41 1.33 MOC to EOC 1.48 1.40 2
TBV Out-of-Service BOC to MOC 1.43 1.34 MOC to EOC 1.52 1.43 3
EOC RPT Out-of-Service BOC to MOC 1.56 1.39 MOC to EOC 1.64 1.47 Pressurization Events: 13 Operating domain: ICF (HBB)
Exposure range
( Application Condition: 1, 2, 3 )
Option A Option B GNF2 GNF2 Load Rejection w/o Bypass 1.41 1.33 Operating domain: ICF (UB)
Exposure range
( Application Condition: 1, 2, 3 )
Option A Option B GNF2 GNF2 Load Rejection w/o Bypass 1.48 1.40 Operating domain: ICF with TBVOOS (HBB)
Exposure range
( Application Condition: 2 )
Option A Option B GNF2 GNF2 Inadvertent HPCI /L8 1.43 1.34 12 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.
13 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.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 17 Operating domain: ICF with TBVOOS (UB)
Exposure range
( Application Condition: 2 )
Option A Option B GNF2 GNF2 Inadvertent HPCI /L8 1.52 1.43 Operating domain: ICF with RPTOOS (HBB)
Exposure range
( Application Condition: 3 )
Option A Option B GNF2 GNF2 Load Rejection w/o Bypass 1.56 1.39 Operating domain: ICF with RPTOOS (UB)
Exposure range
( Application Condition: 3 )
Option A Option B GNF2 GNF2 Load Rejection w/o Bypass 1.64 1.47
- 12. Overpressurization Analysis Summary14 Event Pdome (psig)
Pv (psig)
Plant
Response
MSIV Closure (Flux Scram) - ICF (HBB) 1313 1341 Figure 14 MSIV Closure (Flux Scram) - MELLLA+
(HBB) 1313 1337 Figure 15 14 Overpressure calculated at an initial dome pressure of 1035 psig.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 18
- 13. Fuel Loading Error Results Variable water gap misoriented bundle analysis: Yes 15 Misoriented Fuel Bundle CPR GNF2-P10DG2B403-14GZ-100T2-150-T6-4285 (GNF2) 0.19 GNF2-P10DG2B402-13G8.0-100T2-150-T6-4286 (GNF2) 0.19 GNF2-P10DG2B409-14GZ-100T2-150-T6-4287 (GNF2) 0.19 GNF2-P10DG2B417-2G8.0/10G7.0-100T2-150-T6-4288 (GNF2) 0.14 GNF2-P10DG2B399-11G7.0/2G6.0-100T2-150-T6-4130 (GNF2) 0.19 GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (GNF2) 0.16 GNF2-P10DG2B397-14GZ-100T2-150-T6-4128 (GNF2) 0.20 GNF2-P10DG2B403-12GZ-100T2-150-T6-4129 (GNF2) 0.18
- 14. Control Rod Drop Analysis Results Peach Bottom Unit 2 operates in a banked position withdrawal sequence; therefore, the control rod drop accident analysis is not required. NRC approval is documented in NEDE-24011-P-A-US.
15 Includes a 0.02 penalty due to variable water gap R-factor uncertainty.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 19
- 15. Stability Analysis Results Exelon is seeking approval for operating Peach Bottom Unit 2 in the MELLLA+ operating domain.
Operation within the MELLLA+ operating domain requires the use of the Detect and Suppress Solution -
Confirmation Density (DSS-CD) stability solution. Stability results for operation at EPU with MELLLA+ and DSS-CD are contained in this section.
15.1 Stability DSS-CD Solution Peach Bottom Unit 2 will implement the stability DSS-CD solution using the Oscillation Power Range Monitor (OPRM) as described in Reference 1 in Section 15.4. Plant-specific analyses for the DSS-CD Solution are provided in Reference 2 in Section 15.4. The Detect and Suppress function of the DSS-CD solution based on the OPRM system relies on the Confirmation Density Algorithm (CDA), which constitutes the licensing basis. The Backup Stability Protection (BSP) solution may be used by the plant in the event that the OPRM system is declared inoperable.
The CDA enabled through the OPRM system and the BSP solution described in Reference 2 in Section 15.4 provide the stability licensing bases for Peach Bottom Unit 2 Cycle 21. The safety evaluation report for Reference 1 in Section 15.4 concludes that the DSS-CD solution is acceptable subject to certain cycle-specific limitations and conditions. These cycle-specific limitations and conditions are met for Peach Bottom Unit 2 Cycle 21.
15.2 Detect and Suppress Evaluation A reload DSS-CD evaluation has been performed in accordance with the licensing methodology described in Reference 1 in Section 15.4 to confirm the Amplitude Discriminator Setpoint (SAD) of the CDA established in Reference 2 in Section 15.4. The Cycle 21 DSS-CD evaluation and the results for the DSS-CD Reload Confirmation Applicability Checklist documented in Table 15-1 demonstrate that: 1) the DSS-CD Solution is applicable to Peach Bottom Unit 2 Cycle 21; and, 2) the SAD=1.10 established in Reference 2 in Section 15.4 is confirmed for operation of Peach Bottom Unit 2 Cycle 21.
The SAD=1.10 setpoint is applicable to TLO and to SLO. The SAD=1.10 setpoint is applicable for a rated feedwater temperature equal to or greater than 371.5F in the MELLLA+ domain per Reference 2 in Section 15.4.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 20 Table 15-1 DSS-CD Reload Confirmation Applicability Checklist Parameter DSS-CD Criterion Peach Bottom Unit 2 Cycle 21 Results Acceptance BWR Product Line BWR/3-6 design BWR/4 Confirmed Fuel Product Line GNF2 and earlier GE designs GNF2 Confirmed Operating Domain (TLO)
EPU/MELLLA+ including currently licensed operational flexibility features EPU/MELLLA+
including currently licensed operational flexibility features Confirmed Operating Domain (SLO)
EPU/MELLLA including currently licensed operational flexibility features EPU/MELLLA including currently licensed operational flexibility features Confirmed Rated TFW Reduction 120 °F (EPU/MELLLA)
No TFW Reduction (MELLLA+ Extension) 90 °F (EPU/MELLLA)
Confirmed Margin for TLO see Table 2-4 in Reference 2 in Section 15.4 0.179 Confirmed Margin for SLO see Table 2-5 in Reference 2 in Section 15.4 0.281 Confirmed 15.3 Backup Stability Protection Reference 1 in Section 15.4 describes two BSP options that are based on selected elements from three distinct constituents: BSP Manual Regions, BSP Boundary, and Automated BSP (ABSP) setpoints.
The Manual BSP region boundaries and the BSP Boundary were calculated for Peach Bottom Unit 2 Cycle 21 for normal feedwater temperature operation and reduced feedwater temperature. The endpoints of the regions are defined in Table 15-2 and Table 15-3. The Scram Region boundary, the Controlled Entry Region boundary, and the BSP Boundary are shown in Figure 16 and in Figure 17 for the normal and reduced feedwater temperature, respectively.
The ABSP APRM Simulated Thermal Power setpoints associated with the ABSP Scram Region are determined for Cycle 21 and are defined in Table 15-4. These ABSP setpoints are applicable for both TLO and SLO.
The BSP Boundary and the Manual BSP region boundaries for normal feedwater temperature operation are adequate to bound a variation in normal feedwater temperature of -10F.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 21 Table 15-2 BSP Endpoints for Normal Feedwater Temperature Endpoint Power
(%)
Flow
(%)
Definition A1 77.7 53.6 Scram Region Boundary, HFCL B1 40.5 31.0 Scram Region Boundary, NCL A2 64.5 50.0 Controlled Entry Region Boundary, MELLLA B2 28.1 30.1 Controlled Entry Region Boundary, NCL A3 100 99.0 BSP Boundary Intercept, MELLLA B3 60.5 44.9 BSP Boundary Intercept, MELLLA Line Table 15-3 BSP Endpoints for Reduced Feedwater Temperature Endpoint Power
(%)
Flow
(%)
Definition A1 67.1 53.4 Scram Region Boundary, MELLLA B1 35.1 30.7 Scram Region Boundary, NCL A2 69.3 56.2 Controlled Entry Region Boundary, MELLLA B2 28.1 30.1 Controlled Entry Region Boundary, NCL Note: The BSP Boundary for Reduced Feedwater Temperature is defined by the MELLLA line, per Reference 1 in Section 15.4.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 22 Table 15-4 ABSP Setpoints for the Scram Region Parameter Symbol Value Slope of ABSP APRM flow-biased trip linear segment.
mTrip 1.65 ABSP APRM flow-biased trip setpoint power intercept.
Constant Power Line for Trip from zero Drive Flow to Flow Breakpoint value.
PBSP-Trip 40.5 %RTP ABSP APRM flow-biased trip setpoint drive flow intercept.
Constant Flow Line for Trip.
WBSP-Trip 46.7 %RDF Flow Breakpoint value WBSP-Break 25.0 %RDF 15.4 References
- 1. GE Hitachi Boiling Water Reactor, Detect and Suppress Solution - Confirmation Density, NEDC-33075P-A, Revision 8, November 2013.
- 2. Safety Analysis Report for Peach Bottom Atomic Power Station Units 2 & 3 Maximum Extended Load Line Limit Analysis Plus, NEDC-33720P, Revision 0, September 2014.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 23
- 16. Loss-of-Coolant Accident Results 16.1 10CFR50.46 Licensing Results The ECCS-LOCA GNF2 analysis is based on the SAFER/PRIME ECCS-LOCA methodology. NRC approval of the PRIME methodology is contained in the Final Safety Evaluation in Reference 2 for GNF2 in Section 16.4. The licensing results applicable to the GNF2 fuel type in the new cycle are summarized in the following table.
Table 16.1-1 Licensing Results Fuel Type Licensing Basis PCT
(°F)
Local Oxidation
(%)
Core-Wide Metal-Water Reaction
(%)
GNF2 1920
< 4.00
< 0.10 The SAFER/PRIME ECCS-LOCA analysis results for the GNF2 fuel type are documented in Reference 1 for GNF2 in Section 16.4.
For GNF2, the small break Appendix K ECCS-LOCA result at EPU power and MELLLA+ core flow is 1910 °F as documented in Reference 1. The small break Appendix K ECCS-LOCA result at EPU power and rated core flow is 1905 °F as documented in Reference 1.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 24 16.2 10CFR50.46 Error Evaluation The 10CFR50.46 errors applicable to the GNF2 Licensing Basis PCT are shown in the following table.
Table 16.2-1 Impact on Licensing Basis Peak Cladding Temperature for GNF2 10CFR50.46 Error Notifications Number Subject PCT Impact
(°F) 2014-01 SAFER04A E4-Maintenance Update Changes 0
2014-02 SAFER04A E4-Mass Non-Conservatism
+10 2014-03 SAFER04A E4-Minimum Core DP Model
-10 2014-04 SAFER04A E4-Bundle/Lower Plenum CCFL Head
+5 Total PCT Adder (°F)
+5 After accounting for the error impact, the GNF2 Licensing Basis PCT with the total PCT adder remains below the 10CFR50.46 limit of 2200 °F.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 25 16.3 ECCS-LOCA Operating Limits The ECCS-LOCA MAPLHGR operating limits for all fuel bundles in this cycle are shown in the following table.
Table 16.3-1 MAPLHGR Limits Bundle Type(s): GNF2-P10DG2B403-14GZ-100T2-150-T6-4285 (GNF2)
GNF2-P10DG2B402-13G8.0-100T2-150-T6-4286 (GNF2)
GNF2-P10DG2B406-12G6.0-100T2-150-T6-3337 (GNF2)
GNF2-P10DG2B393-15GZ-100T2-150-T6-3334 (GNF2)
GNF2-P10DG2B409-14GZ-100T2-150-T6-4287 (GNF2)
GNF2-P10DG2B417-2G8.0/10G7.0-100T2-150-T6-4288 (GNF2)
GNF2-P10DG2B388-6G8.0/6G7.0/2G6.0-100T2-150-T6-3336 (GNF2)
GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (GNF2)
GNF2-P10DG2B392-15GZ-100T2-150-T6-3332 (GNF2)
GNF2-P10DG2B399-11G7.0/2G6.0-100T2-150-T6-4130 (GNF2)
GNF2-P10DG2B397-14GZ-100T2-150-T6-4128 (GNF2)
GNF2-P10DG2B403-12GZ-100T2-150-T6-4129 (GNF2)
Average Planar Exposure MAPLHGR Limit GWd/MT GWd/ST kW/ft 0.00 0.00 13.78 19.31 17.52 13.78 67.00 60.78 7.50 70.00 63.50 6.69 The power and flow dependent LHGR multipliers are sufficient to provide adequate protection for the off-rated conditions from an ECCS-LOCA analysis perspective. The MAPLHGR multipliers can either be set to unity or set equal to the LHGR multipliers, which remain compliant with the basis of the ECCS-LOCA analysis with no loss of ECCS-LOCA margin.
The single loop operation multipliers on LHGR and MAPLHGR and the ECCS-LOCA analytical initial MCPR values, applicable to the GNF2 fuel type in the new cycle core are shown in the following table.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 26 Table 16.3-2 Initial MCPR and Single Loop Operation Multiplier on LHGR and MAPLHGR Fuel Type Initial MCPR Single Loop Operation Multiplier on LHGR and MAPLHGR GNF2 1.25 0.73 The GNF2 SLO multiplier applies to the EPU operating domain only, and SLO operation in the MELLLA+ domain is not permitted.
16.4 References The SAFER/PRIME ECCS-LOCA analysis base reports applicable to the new cycle core are:
References for GNF2
- 1. Project Task Report, Exelon Generation Company LLC, Peach Bottom Atomic Power Station, Units 2 & 3 MELLLA+ Task T0407: ECCS-LOCA Performance, 0000-0162-2354-R0, Revision 0, December 2013.
- 2. Licensing Topical Report, The PRIME Model for Analysis of Fuel Rod Thermal-Mechanical Performance, Part 1 - Technical Bases - NEDC-33256P-A, Revision 1, Part 2 -
Qualification - NEDC-33257P-A, Revision 1, and Part 3 - Application Methodology -
NEDC-33258P-A, Revision 1, September 2010.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 27 60 10 19 11 19 19 8 8 8 8 19 19 20 21 20 58 9 8 19 8 26 24 22 22 22 22 24 26 20 19 8 9 56 19 20 8 1 23 26 4 25 4 24 24 4 25 4 26 23 1 20 8 10 54 11 8 22 4 4 4 4 5 4 5 5 4 5 4 4 4 4 22 8 11 52 8 1 25 4 13 12 28 6 27 3 27 27 3 27 6 28 12 13 4 25 8 1 50 11 8 19 25 4 4 12 25 6 6 7 26 5 5 26 7 6 6 25 12 4 4 25 19 19 11 48 20 8 25 4 25 12 25 6 22 3 25 5 24 24 5 25 3 22 6 25 12 25 4 25 8 8 46 9 8 22 4 4 12 26 6 25 3 22 5 25 3 3 25 5 22 3 25 6 26 12 4 4 22 8 9 44 20 8 10 4 13 12 25 6 28 12 22 5 24 3 24 24 3 24 5 22 12 28 6 25 12 13 4 10 8 19 42 21 11 23 4 12 25 6 25 12 22 2 23 3 26 5 5 26 3 23 2 22 12 25 6 25 12 4 23 11 8 40 19 8 26 4 28 6 22 3 22 2 25 3 27 2 24 24 2 27 3 25 2 22 3 22 6 28 4 26 8 9 38 9 26 4 4 6 6 3 22 5 23 3 26 5 22 7 7 22 5 26 3 23 5 22 3 6 6 4 4 26 19 36 8 24 25 5 27 7 25 5 24 3 27 5 28 3 26 26 3 28 5 27 3 24 5 25 7 27 5 25 24 8 34 20 22 4 4 3 26 5 25 3 26 2 22 3 25 5 5 25 3 22 2 26 3 25 5 26 3 4 4 22 11 32 8 22 24 5 27 5 24 3 24 5 24 7 26 5 22 22 5 26 7 24 5 24 3 24 5 27 5 24 22 8 30 8 22 24 5 27 5 24 3 24 5 24 7 26 5 22 22 5 26 7 24 5 24 3 24 5 27 5 24 22 8 28 19 22 4 4 3 26 5 25 3 26 2 22 3 25 5 5 25 3 22 2 26 3 25 5 26 3 4 4 22 8 26 8 24 25 5 27 7 25 5 24 3 27 5 28 3 26 26 3 28 5 27 3 24 5 25 7 27 5 25 24 8 24 19 26 4 4 6 6 3 22 5 23 3 26 5 22 7 7 22 5 26 3 23 5 22 3 6 6 4 4 26 9 22 9 19 26 4 28 6 22 3 22 2 25 3 27 2 24 24 2 27 3 25 2 22 3 22 6 28 4 26 8 19 20 21 8 23 4 12 25 6 25 12 22 2 23 3 26 5 5 26 3 23 2 22 12 25 6 25 12 4 23 11 21 18 20 8 10 4 13 12 25 6 28 12 22 5 24 3 24 24 3 24 5 22 12 28 6 25 12 13 4 10 8 20 16 9 8 22 4 4 12 26 6 25 3 22 5 25 3 3 25 5 22 3 25 6 26 12 4 4 22 8 9 14 8 1 25 4 25 12 25 6 22 3 25 5 24 24 5 25 3 22 6 25 12 25 4 25 20 1 12 11 19 8 25 4 4 12 25 6 6 7 26 5 5 26 7 6 6 25 12 4 4 25 8 19 11 10 8 20 25 4 13 12 28 6 27 3 27 27 3 27 6 28 12 13 4 25 19 8 8 11 20 22 4 4 4 4 5 4 5 5 4 5 4 4 4 4 22 20 11 6 10 8 8 1 23 26 4 25 4 24 24 4 25 4 26 23 1 8 8 10 4 9 11 19 8 26 24 22 22 22 22 24 26 8 19 8 9 2 11 8 20 19 19 8 8 8 8 19 19 20 19 11 1 3 5 7 9 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 Fuel Type 1=GNF2-P10DG2B393-15GZ-100T2-150-T6-3334 (Cycle 19) 2=GNF2-P10DG2B403-14GZ-100T2-150-T6-4285 (Cycle 21) 3=GNF2-P10DG2B403-14GZ-100T2-150-T6-4285 (Cycle 21) 4=GNF2-P10DG2B417-2G8.0/10G7.0-100T2-150-T6-4288 (Cycle 21) 5=GNF2-P10DG2B402-13G8.0-100T2-150-T6-4286 (Cycle 21) 6=GNF2-P10DG2B409-14GZ-100T2-150-T6-4287 (Cycle 21) 7=GNF2-P10DG2B402-13G8.0-100T2-150-T6-4286 (Cycle 21) 8=GNF2-P10DG2B406-12G6.0-100T2-150-T6-3337 (Cycle 19) 9=GNF2-P10DG2B393-15GZ-100T2-150-T6-3334 (Cycle 19) 10=GNF2-P10DG2B388-6G8.0/6G7.0/2G6.0-100T2-150-T6-3336 (Cycle 19) 11=GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (Cycle 19) 12=GNF2-P10DG2B409-14GZ-100T2-150-T6-4287 (Cycle 21) 13=GNF2-P10DG2B417-2G8.0/10G7.0-100T2-150-T6-4288 (Cycle 21) 19=GNF2-P10DG2B388-6G8.0/6G7.0/2G6.0-100T2-150-T6-3336 (Cycle 19) 20=GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (Cycle 19) 21=GNF2-P10DG2B392-15GZ-100T2-150-T6-3332 (Cycle 19) 22=GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (Cycle 20) 23=GNF2-P10DG2B397-14GZ-100T2-150-T6-4128 (Cycle 20) 24=GNF2-P10DG2B399-11G7.0/2G6.0-100T2-150-T6-4130 (Cycle 20) 25=GNF2-P10DG2B403-12GZ-100T2-150-T6-4129 (Cycle 20) 26=GNF2-P10DG2B392-15GZ-100T2-150-T6-3335 (Cycle 20) 27=GNF2-P10DG2B397-14GZ-100T2-150-T6-4128 (Cycle 20) 28=GNF2-P10DG2B403-12GZ-100T2-150-T6-4129 (Cycle 20)
Figure 1 Reference Core Loading Pattern
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 28 Figure 2 Plant Response to Load Rejection w/o Bypass
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 29 Figure 3 Plant Response to FW Controller Failure
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 30 Figure 4 Plant Response to Load Rejection w/o Bypass
( EOC ICF (UB) )
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 31 Figure 5 Plant Response to FW Controller Failure
( EOC ICF (UB) )
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 32 Figure 6 Plant Response to Inadvertent HPCI/L8
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 33 Figure 7 Plant Response to FW Controller Failure
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 34 Figure 8 Plant Response to Inadvertent HPCI/L8
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 35 Figure 9 Plant Response to FW Controller Failure
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 36 Figure 10 Plant Response to Load Rejection w/o Bypass
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 37 Figure 11 Plant Response to FW Controller Failure
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 38 Figure 12 Plant Response to Load Rejection w/o Bypass
( EOC ICF with RPTOOS (UB) )
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 39 Figure 13 Plant Response to FW Controller Failure
( EOC ICF with RPTOOS (UB) )
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 40 Figure 14 Plant Response to MSIV Closure (Flux Scram) - ICF (HBB)
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 41 Figure 15 Plant Response to MSIV Closure (Flux Scram) - MELLLA+ (HBB)
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 42 Figure 16 Manual BSP Regions and BSP Boundary for Normal Feedwater Temperature Operation
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 43 Figure 17 Manual BSP Regions and BSP Boundary for Reduced Feedwater Temperature Operation
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 44 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.
Table A-1 Reactor Operating Conditions Analysis Value16 Parameter ICF NFWT MLP NFWT ICF RFWT MEL RFWT Thermal power, MWt 3951.0 3951.0 3951.0 3951.0 Core flow, Mlb/hr 112.8 85.1 112.8 101.5 Reactor pressure (core mid-plane), psia 1067.0 1061.9 1049.2 1047.2 Inlet enthalpy, Btu/lb 524.5 515.1 513.1 508.9 Non-fuel power fraction 17 N/A N/A N/A N/A Steam flow, Mlb/hr 16.18 16.14 14.55 14.53 Dome pressure, psig 1034.8 1034.7 1018.6 1018.4 Turbine pressure, psig 963.8 964.1 960.7 960.6 Table A-2 Pressure Relief and Safety Valve Configuration Valve Type Number of Valves Lowest Setpoint (psig)
Safety/Relief Valve 11 1169.1 Spring Safety Valve 3
1297.8 16 The label MLP indicates MELLLA+ flow and the label MEL indicates MELLLA flow.
17 For TRACG methodology, the direct moderator heating is a function of moderator density.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 45 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.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 46 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 11. The Inadvertent HPCI start-up event with a Level 8 turbine trip OLMCPR results are summarized in Section
- 11.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 47 Appendix D Off-Rated Limits Off-Rated Power Dependent Limits The off-rated power dependent limits to be applied for Equipment In-Service, TBVOOS, and RPTOOS are documented in Reference D-1. The Kp/MCPRp and LHGRFACp limits provided in Reference D-1 have been validated for this cycle. However, the power dependent limits are adjusted for updated values of Pbypass and RPmin.
The MCPRp limits provided in Reference D-1 are based on a SLMCPR of 1.10; therefore, the below Pbypass MCPRp limits have been scaled for the cycle-specific SLMCPR in Section 11.
The off-rated power dependent limits support PROOS at power levels >90% rated thermal power in all application conditions. The off-rated power dependent limits support PLUOOS at power levels < 55%
rated thermal power and >90% rated thermal power in all application conditions. The conclusions in Reference D-2 remain valid.
MCPRp Limits for:
Equipment In Service Limits for Power < 26.7%
Flow > 60.0%
Flow 60.0%
Power (%)
Limit MCPRp Power (%)
Limit MCPRp 23.0 2.99 23.0 2.67 26.7 2.83 26.7 2.60 Limits for Power 26.7%
Power (%)
Limit Kp 26.7 1.352 40.0 1.352 55.0 1.317 65.0 1.131 85.0 1.082 100.0 1.000
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 48 MCPRp Limits for:
TBV Out-of-Service Limits for Power < 26.7%
Flow > 60.0%
Flow 60.0%
Power (%)
Limit MCPRp Power (%)
Limit MCPRp 23.0 4.15 23.0 3.64 26.7 3.78 26.7 3.25 Limits for Power 26.7%
Power (%)
Limit Kp 26.7 1.659 40.0 1.479 55.0 1.373 65.0 1.155 85.0 1.082 100.0 1.000 MCPRp Limits for:
EOC RPT Out-of-Service Limits for Power < 26.7%
Flow > 60.0%
Flow 60.0%
Power (%)
Limit MCPRp Power (%)
Limit MCPRp 23.0 2.99 23.0 2.67 26.7 2.83 26.7 2.60 Limits for Power 26.7%
Power (%)
Limit Kp 26.7 1.352 40.0 1.352 55.0 1.317 65.0 1.131 85.0 1.082 100.0 1.000
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 49 LHGRFACp Limits for:
Equipment In Service Limits for Power < 26.7%
Flow > 60.0%
Flow 60.0%
Power (%)
Limit Power (%)
Limit 23.0 0.508 23.0 0.508 26.7 0.522 26.7 0.522 Limits for Power 26.7%
Power (%)
Limit 26.7 0.748 40.0 0.756 55.0 0.771 65.0 0.817 85.0 0.959 100.0 1.000 LHGRFACp Limits for:
TBV Out-of-Service Limits for Power < 26.7%
Flow > 60.0%
Flow 60.0%
Power (%)
Limit Power (%)
Limit 23.0 0.410 23.0 0.397 26.7 0.417 26.7 0.442 Limits for Power 26.7%
Power (%)
Limit 26.7 0.635 40.0 0.655 55.0 0.714 65.0 0.817 85.0 0.930 100.0 1.000
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 50 LHGRFACp Limits for:
EOC RPT Out-of-Service Limits for Power < 26.7%
Flow > 60.0%
Flow 60.0%
Power (%)
Limit Power (%)
Limit 23.0 0.508 23.0 0.508 26.7 0.522 26.7 0.522 Limits for Power 26.7%
Power (%)
Limit 26.7 0.748 40.0 0.756 55.0 0.771 65.0 0.817 85.0 0.959 100.0 1.000 Off-Rated Flow Dependent Limits The off-rated flow dependent limits are documented in Reference D-1. The MCPRf and LHGRFACf limits provided in Reference D-1 have been validated for this cycle. The flow dependent limits are based on a single pump runout with no mechanical scoop tube setpoint. The flow dependent limits are based on a bounding pump runout limited to 100% rated core flow. Flow dependent limits are provided for operation up to a maximum of 110% rated core flow.
The MCPRf limits provided in Reference D-1 are based on a SLMCPR of 1.12; the MCPRf limits have been scaled for the cycle-specific SLMCPR in Section 11.
MCPRf Limits for:
Equipment In Service Limits for a Maximum Runout Flow of 110.0%
Flow (%)
Limit MCPRf 30.0 1.57 79.0 1.28 110.0 1.28 MCPRf Limits for:
TBV Out-of-Service Limits for a Maximum Runout Flow of 110.0%
Flow (%)
Limit MCPRf 30.0 1.57 79.0 1.28 110.0 1.28
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 51 MCPRf Limits for:
EOC RPT Out-of-Service Limits for a Maximum Runout Flow of 110.0%
Flow (%)
Limit MCPRf 30.0 1.57 79.0 1.28 110.0 1.28 LHGRFACf Limits for:
Equipment In Service Limits for a Maximum Runout Flow of 110.0%
Flow (%)
Limit 30.0 0.706 70.0 0.973 80.0 1.000 110.0 1.000 LHGRFACf Limits for:
TBV Out-of-Service Limits for a Maximum Runout Flow of 110.0%
Flow (%)
Limit 30.0 0.706 70.0 0.973 80.0 1.000 110.0 1.000 LHGRFACf Limits for:
EOC RPT Out-of-Service Limits for a Maximum Runout Flow of 110.0%
Flow (%)
Limit 30.0 0.706 70.0 0.973 80.0 1.000 110.0 1.000 References D-1.
Peach Bottom Atomic Power Station Units 2 and 3 TRACG Implementation for Reload Licensing Transient Analysis, 0000-0135-9000-R0, August 2011.
D-2.
Evaluation of Power Load Unbalance Out-of-Service and Pressure Regulator Out-of-Service between 90% and 100% RTP for Peach Bottom Units 2 and 3, 0000-0163-9619-R0, July 2013.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 52 Appendix E TRACG04 AOO Supplementary Information Reference E-1 provides the results of the evaluations supporting the application of TRACG04 for AOO analyses for Peach Bottom. Section 11 of this report presents the MCPR limits based on the TRACG04 methodology of Reference E-2.
The safety evaluation report for licensing topical report NEDE-32906P (Reference E-2) concluded that the application of TRACG04 methods to AOO and overpressure transient analyses were acceptable subject to certain limitations and conditions. Peach Bottom Unit 2 Cycle 21 MELLLA+ is in compliance with these limitations and conditions.
References E-1.
Peach Bottom Atomic Power Station Units 2 and 3 TRACG Implementation for Reload Licensing Transient Analysis, 0000-0135-9000-R0, August 2011.
E-2.
Migration to TRACG04/PANAC11 from TRACG02/PANAC10 for TRACG AOO and ATWS Overpressure Transients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 53 Appendix F Interim Methods LTR (NEDC-33173P-A Revision 4)
Supplemental Information The safety evaluation for licensing topical report NEDC-33173P-A Revision 4 (Reference F-1) concluded that the application of GEH/GNF methods to expanded operating domains was acceptable subject to certain limitations and conditions. Several of these limitations and conditions request that additional, application-specific information be provided in the SRLR. The information provided below responds to these requests for the identified items.
Limitation and Condition 9.5 (SLMCPR 2)
Limitation and Condition 9.5 states:
For operation at MELLLA+, including operation at the EPU power levels at the achievable core flow state-point, a 0.01 value shall be added to the cycle-specific SLMCPR value for power-to-flow ratios up to 42 MWt/Mlbm/hr, and a 0.02 value shall be added to the cycle-specific SLMCPR value for power-to-flow ratios above 42 MWt/Mlbm/hr.
For operation at MELLLA+, a 0.02 value was added to the cycle specific SLMCPR. The SLMCPR values reported in Section 11 reflect this adder.
Limitation and Condition 9.8 (ECCS-LOCA 2)
Limitation and Condition 9.8 states:
The ECCS-LOCA will be performed for all statepoints in the upper boundary of the expanded operating domain, including the minimum core flow statepoints, the transition statepoint, as defined in Reference F-2 and the 55 percent core flow statepoint. The plant-specific application will report the limiting ECCS-LOCA results as well as the rated power and flow results. The SRLR will include both the limiting statepoint ECCS-LOCA results and the rated conditions ECCS-LOCA results.
This limitation and condition is satisfied by the Appendix K PCTs reported in Reference 1 in Section 16.4. Detail to appear in the SRLR conforms to direction resolved with NRC Staff during review process (see RAI 25.b). The SRLR reports the bounding Licensing Basis PCT for all statepoints analyzed.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 54 Limitation and Condition 9.10/9.11 (Transient LHGR 2/3)
Limitation and Condition 9.10 states:
Each EPU and MELLLA+ fuel reload will document the calculation results of the analyses demonstrating compliance to transient T-M acceptance criteria. The plant T-M response will be provided with the SRLR or COLR, or it will be reported directly to the NRC as an attachment to the SRLR or COLR.
Limitation and Condition 9.11 states:
To account for the impact of the void history bias, plant-specific EPU and MELLLA+
applications using either TRACG or ODYN will demonstrate an equivalent to 10 percent margin to the fuel centerline melt and the 1 percent cladding circumferential plastic strain acceptance criteria due to pellet-cladding mechanical interaction for all of limiting AOO transient events, including equipment out-of-service. Limiting transients in this case, refers to transients where the void reactivity coefficient plays a significant role (such as pressurization events). If the void history bias is incorporated into the transient model within the code, then the additional 10 percent margin to the fuel centerline melt and the 1 percent cladding circumferential plastic strain is no longer required.
Appendix B documents the fact that the results for all analyzed transients demonstrate compliance with thermal-mechanical acceptance criteria.
Table F-1 summarizes the percent margin to the Thermal Overpower and Mechanical Overpower acceptance criteria.
As referenced in Appendix E (Reference E-2) the void history bias was incorporated into the transient model within the TRACG04 code, and therefore the 10 percent margin to the fuel centerline melt and the 1 percent cladding circumferential plastic strain acceptance criteria is no longer required.
Table F-1 Margin to the Thermal Overpower and Mechanical Overpower Acceptance Criteria Criteria GNF2 Thermal Overpower 0.9%
Mechanical Overpower 17.7%
Limitation and Condition 9.17 (Steady-State 5 Percent Bypass Voiding)
Limitation and Condition 9.17 states:
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 55 The instrumentation specification design bases limit the presence of bypass voiding to 5 percent (LRPM (sic) levels). Limiting the bypass voiding to less than 5 percent for long term steady operation ensures that instrumentation is operated within the specification.
For EPU and MELLLA+ operation, the bypass voiding will be evaluated on a cycle-specific basis to confirm that the void fraction remains below 5 percent at all LPRM levels when operating at steady-state conditions within the MELLLA+ upper boundary.
The highest calculated bypass voiding at any LPRM level will be provided with the plant-specific SRLR.
The bypass voiding was evaluated for the licensed core loading and confirmed that the bypass void fraction remained below 5 percent at all LPRM levels when operating at steady-state conditions within the licensed upper boundary.
Limitation and Condition 9.18 (Stability Setpoints Adjustment)
Limitation and Condition 9.18 states:
The NRC staff concludes that the presence bypass voiding at the low-flow conditions where instabilities are likely can result in calibration errors of less than 5 percent for OPRM cells and less than 2 percent for APRM signals. These calibration errors must be accounted for while determining the setpoints for any detect and suppress long term methodology. The calibration values for the different long-term solutions are specified in the associated sections of this SE, discussing the stability methodology.
This limitation and condition is not applicable to DSS-CD because the significant conservatisms in the current licensing methodology and associated MCPR margins are more than sufficient to compensate for the overall uncertainty in the OPRM instrumentation.
Limitation and Condition 9.19 (Void-Quality Correlation 1)
Limitation and Condition 9.19 states:
For applications involving PANCEA(sic)/ODYN/ISCOR/TASC for operation at EPU and MELLLA+, an additional 0.01 will be added to the OLMCPR, until such time that GE expands the experimental database supporting the Findlay-Dix void-quality correlation to demonstrate the accuracy and performance of the void-quality correlation based on experimental data representative of the current fuel designs and operating conditions during steady-state, transient, and accident conditions.
The OLMCPR limitation requiring an additional 0.01 adder on the OLMCPR does not apply to EPU or MELLLA+ licensing calculations when TRACG04 methods are used (Reference F-3). Therefore, the OLMCPR adder is not applied to Peach Bottom Unit 2 Cycle 21.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 56 References F-1. Applicability of GE Methods to Expanded Operating Domains, NEDC-33173P-A, Revision 4, November 2012.
F-2. General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus, NEDC-33006P-A, Revision 3, June 2009.
F-3. Migration to TRACG04 / PANAC11 from TRACG02 / PANAC10 for TRACG AOO and ATWS Overpressure Transients, NEDE-32906P, Supplement 3-A, Revision 1, April 2010.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 57 Appendix G MELLLA+ LTR (NEDC-33006P-A Revision 3)
Supplemental Information The safety evaluation for licensing topical report NEDC-33006P-A Revision 3 (Reference G-1) approved the operation of GE BWRs in the MELLLA+ expanded operating domain, subject to certain limitations and conditions. Several of these limitations and conditions request that additional, application-specific information be provided in the SRLR. The information provided below responds to these requests for the identified items.
Limitation and Condition 12.6 (SLMCPR Statepoints and CF Uncertainty)
Limitation and Condition 12.6 states:
Until such time when the SLMCPR methodology (References G-2 and G-3) for off-rated SLMCPR calculation is approved by the staff for MELLLA+ operation, the SLMCPR will be calculated at the rated statepoint (120 percent P/100 percent CF), the plant-specific minimum CF statepoint (e.g., 120 percent P/80 percent CF), and at the 100 percent OLTP at 55 percent CF statepoint. The currently approved off-rated CF uncertainty will be used for the minimum CF and 55 percent CF statepoints. The uncertainty must be consistent with the CF uncertainty currently applied to the SLO operation or as NRC-approved for MELLLA+ operation. The calculated values will be documented in the SRLR.
As requested, the SLMCPR calculated results at specified off-rated power/flow conditions are reported in Table G-1 below, including the low CF statepoint.
Table G-1 Two-Loop SLMCPR Results for MELLLA+ Conditions Power (% Rated)
Flow (% Rated)
SLMCPR 100 100 1.07 100 83 1.12 78.8 55 1.13 100 110 1.07
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 58 Limitation and Condition 12.10.b (ECCS-LOCA Off-Rated Multiplier)
Limitation and Condition 12.10.b states:
LOCA analysis is not performed on cycle-specific basis; therefore, the thermal limits applied in the M+SAR LOCA analysis for the 55 percent CF MELLLA+ statepoint and/or the transition statepoint must be either bounding or consistent with cycle-specific off-rated limits. The COLR and the SRLR will contain confirmation that the off-rated limits assumed in the ECCS-LOCA analyses bound the cycle-specific off-rated limits calculated for the MELLLA+ operation. Every future cycle reload shall confirm that the cycle-specific off-rated thermal limits applied at the 55 percent CF and/or the transition statepoints are consistent with those assumed in the plant-specific ECCS-LOCA analyses.
The off-rated limits assumed in the ECCS-LOCA analyses are confirmed to be consistent with the cycle-specific off-rated LHGR multipliers calculated for the MELLLA+ operation. The off-rated LHGR multipliers provide adequate protection for the MELLLA+ operation.
Limitation and Condition 12.18.d (ATWS TRACG Analysis)
Limitation and Condition 12.18.d states:
In general, the plant-specific application will ensure that operation in the MELLLA+
domain is consistent with the assumptions used in the ATWS analysis, including equipment out of service (e.g., FWHOOS, SLO, SRVs, SLC pumps, and RHR pumps, etc.).
If assumptions are not satisfied, operation in MELLLA+ is not allowed. The SRLR will specify the prohibited flexibility options for plant-specific MELLLA+ operation, where applicable. For key input parameters, systems and engineering safety features that are important to simulating the ATWS analysis and are specified in the Technical Specification (TS) (e.g., SLCS parameters, ATWS RPT, etc.), the calculation assumptions must be consistent with the allowed TS values and the allowed plant configuration. If the analyses deviate from the allowed TS configuration for long term equipment out of service (i.e., beyond the TS LCO), the plant-specific application will specify and justify the deviation. In addition, the licensee must ensure that all operability requirements are met (e.g., NPSH) by equipment assumed operable in the calculations.
This ATWS TRACG Analysis limitation and condition requires that the SRLR specify the prohibited flexibility options for plant-specific MELLLA+ operation, where applicable, as expressed by EOOS options in Section 8.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 59 References G-1. General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus, NEDC-33006P-A, Revision 3, June 2009.
G-2. Methodology and Uncertainties for Safety Limit MCPR Evaluations, NEDC-32601P-A, August 1999.
G-3. Power Distribution Uncertainties for Safety Limit MCPR Evaluations, NEDC-32694P-A, August 1999.
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 60 Appendix H List of Acronyms Acronym Description CPR Delta Critical Power Ratio k
Delta k-effective 2RPT (2PT)
Two Recirculation Pump Trip ABSP Automated Backup Stability Protection ADS Automatic Depressurization System ADSOOS Automatic Depressurization System Out of Service AOO Anticipated Operational Occurrence APRM Average Power Range Monitor ARTS APRM, Rod Block and Technical Specification Improvement Program BOC Beginning of Cycle BSP Backup Stability Protection BWROG Boiling Water Reactor Owners Group COLR Core Operating Limits Report CPR Critical Power Ratio DIRPT Delta MCPR over Initial MCPR for a two-Recirculation Pump Trip DIVOM Delta CPR over Initial MCPR vs. Oscillation Magnitude DR Decay Ratio DS/RV Dual Mode Safety/Relief Valve ECCS Emergency Core Cooling System EIS Equipment in Service ELLLA Extended Load Line Limit Analysis EOC End of Cycle (including all planned cycle extensions)
EOR End of Rated (All Rods Out 100%Power / 100%Flow / NFWT)
EPU Extended Power Uprate ER Exclusion Region FFWTR Final Feedwater Temperature Reduction FMCPR Final MCPR FOM Figure of Merit FW Feedwater FWCF Feedwater Controller Failure FWHOOS Feedwater Heaters Out of Service FWTR Feedwater Temperature Reduction GESTAR General Electric Standard Application for Reactor Fuel GETAB General Electric Thermal Analysis Basis GSF Generic Shape Function HAL Haling Burn HBB Hard Bottom Burn HBOM Hot Bundle Oscillation Magnitude HCOM Hot Channel Oscillation Magnitude HFCL High Flow Control Line HPCI High Pressure Coolant Injection
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 61 Acronym Description ICA Interim Corrective Action 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 LFWH Loss of Feedwater Heating LHGR Linear Heat Generation Rate LHGRFACf Off-rated flow dependent LHGR multiplier LHGRFACp Off-rated power dependent LHGR multiplier LOCA Loss of Coolant Accident LOSC Loss of Stator Cooling LPRM Local Power Range Monitor LRWHBP 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 MSF Modified Shape Function 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 N/A Not Applicable NBP No Bypass NCL Natural Circulation Line NFWT Normal Feedwater Temperature NOM Nominal Burn NTR Normal Trip Reference OLMCPR Operating Limit MCPR
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 62 Acronym Description OOS 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 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 Service Q/A Heat Flux RBM Rod Block Monitor RC Reference Cycle RCF Rated Core Flow RDF Recirculation Drive Flow RFWT Reduced Feedwater Temperature RPS Reactor Protection System RPT Recirculation Pump Trip RPTOOS Recirculation Pump Trip Out of Service RTP Rated Thermal Power RV Relief Valve RVM Reload Validation Matrix RWE Rod Withdrawal Error SC Standard Cycle SL Safety Limit SLMCPR Safety Limit Minimum Critical Power Ratio SLO Single Loop Operation SRI Select Rod Insert SRLR Supplemental Reload Licensing Report S/RV (SRV)
Safety/Relief Valve SRVOOS Safety/Relief Valve(s) Out of Service SS Steady State SSV Spring Safety Valve STU Short Tons (or Standard Tons) of Uranium STP Simulated Thermal Power TBSOOS Turbine Bypass System Out of Service TBV Turbine Bypass Valve TBVO Turbine Bypass Valves Open TBVOOS Turbine Bypass Valves Out of Service TCV Turbine Control Valve TCVOOS Turbine Control Valve Out of Service
Peach Bottom Unit 2 001N2150-SRLR Reload 20 Revision 1 Page 63 Acronym Description TCVSC Turbine Control Valve Slow Closure TLO Two Loop Operation TOPPS Tracking Over-Power Protection System TRF Trip Reference Function TSIP Technical Specifications Improvement Program TSV Turbine Stop Valve TSVOOS Turbine Stop Valve Out of Service TT Turbine Trip TTWHBP Turbine Trip with Half Bypass TTNBP Turbine Trip without Bypass UB Under Burn