ML030840715
| ML030840715 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/17/2003 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 28401 | |
| Download: ML030840715 (42) | |
Text
Mar.
17, 2003 Page 1
of 1
MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-12921 USER INFORMATIQN:
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TRM APPROVED AMENDMENT TO UNIT 2 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE DATE 0311012003 Replace the following pages of the Technical Requirements Manual with the enclosed pages.
The revised pages are identified by Effective Date and contain vertical lines indicating the area of change.
G:\\Lic Docs\\TRM Word\\TRM Removelnsert\\RemlnsShellUnitl,2.doc 316103 EFFECTIVE REMOVE PAGES INSERT PAGES DATE TRM I LOES-1 through TRM I LOES-6 TRM / LOES-1 through TRM I LOES-6 03/10/2003 TRM / 3 2-2 through 3 2-30 TRM /3 2-2 through 3 2-35 03/10/2003
.4 4
.4 4
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title TOC 1.0 Effective Date TABLE OF CONTENTS USE AND APPLICATION Page TRM / 1.0-1 Page TRM / 1.0-2 Page TRM / 1.0-3 2.0 PLANT PROGRAMS Page 2.0-1 Pages TRM / 2.0-2 through TRM / 2.0-4 Pages TRM / 2.0-5 through TRM / 2.0-7 Page TRM / 2.0-8
- Page TRM / 2.0-9 Pages TRM / 2.0-10 through TRM / 2.0-12 Page TRM/ 2.0-13 3.0 3.1 3.2 3.3 APPLICABILITY Pages TRM / 3.0-1 and TRM /
Page TRM / 3.0-3 Page TRM / 3.0-4 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.,1!-)
Pages TRM / 3.1-7 and8TRM f 3.1`8 Pages TRM / 3.1-9fnd TRM /3.1-9a Page TRM / 3.i-10 \\
Pages 3.1-11 throughh 3.113 CORE OPERATING -LIMITS REPORT Page, 3.2-1 \\,_
Pag s TR'M h3.2-2 through TRM /3.2-35 INSTRUMENTATION K Pag'esTRM / 3.3-1 through TRM / 3.3-3
\\P'Ae TRM / 3.3-4 Pages 3.3-5 through 3.3-8 Pages TRM / 3.3-9 and TRM / 3.3-9a Pages TRM / 3.3-10 and TRM / 3.3-11 Page TRM / 3.3-12 Pages TRM / 3.3-13 through TRM / 3.3-15 Page TRM / 3.3-16 Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM / 3.3-19 through TRM / 3.3-20 Pages 3.3-21 and 3.3-22 Pages TRM / 3.3-23 through TRM / 3.3-25 04/02/2002 08/31/1998 10/04/2002 08/31/1998 08/31/1998 06/2512002 04/1211999 0813012001 09/06/2002 04/12/1999 06/16/2000 0410811999 03/15/2002 04108/1999 08/31/1998 06105/2002 02/18/1999 02/18/1999 08/31/1998 08/31/1998 03/10/2003 07/16/1999 11/28/2000 08/31/1998 12/17/1998 12/17/1998 03/30/2001 12114/1998 06/27/2001 06/14/2002 12/14/1998 08/31/1998 04/02/1999 SUSQUEHANNA
- UNIT 2 TRM/LOES-1 EFFECTIVE DATE 03/10/2003 I
SUSQUEHANNA -UNIT 2 TRM / LOES-1 EFFECTIVE DATE 03/10/2003
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title 3.4 3.5 3.6 37 Effective Date REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-13 EMERGENCY CORE COOLING AND RCIC Pages 3.5-1 through 3.5-3 Page TRM / 3.5-4 Pages 3.5-5 through 3.5-7 CONTAINMENT Pages 3.6-1 through 3.6-4 Page TRM / 3.6-5 Page 3.6-6
- Pages TRM / 3.6-7 through TRM / 3.6-9 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 Page 3.7-3 Pages TRM / 3.7-4 through TRM / 3.7-10 Page TRM / 3.7-11 Pages TRM / 3.7-12 through TRM / 3.7-27 Pages TRM / 3.7-28 through TRM / 3.7-32 Page TRM / 3.7-33 Pages TRM / 3.7-34 through TRM / 3.7-36 Pages 3.7-37 through 3.7-39 Pages TRM / 3.7-40 and TRM / 3.7-40a Pages 3.7-41 and 3.7-42 Pages 3.7-43 through 3.7-47 Page TRM / 3.7-48 Pages TRM / 3.7-49 and TRM / 3.7-50 Page TRM / 3.7-51 Pages TRM / 3.7-52 and TRM / 3.7-53 ELECTRICAL POWER Pages TRM / 3.8-1 and TRM / 3.8-2 Page 3.8-3 Page TRM / 3.8-4 Pages TRM / 3.8-5 and TRM / 3.8-6 Pages TRM / 3.8-7 through TRM / 3.8-8 Page TRM / 3.8-9 Page 3.8-10 Page TRM / 3.8-11 Page TRM / 3.8-11 a Pages 3.8-12 through 3.8-14 Pages TRM / 3.8-15 through TRM / 3.8-17 Page 3.8-18 3.8 10/23/1998 08/31/1998 08/31/1998 04/17/2000 08/31/1998 08/31/1998 01/0712002 08/31/1998 12/31/2002 07/29/1999 08/31/1998 08/02/1999 01/21/2000 08/02/1999 11/16/2001 10/05/2002 02/01/1999 08/31/1998 08/11/2000 08/31/1998 10/13/1998 03/08/2003 03109/2001 07/05/2000 07/29/1999 04/02/2002 08/31/1998 12/31/2002 04/02/2002 08/31/1998 08/2412001 08/3111998 04/02/2002 04/02/2002 08/31/1998 04102/2002 02/01/1999 EFFECTIVE DATE 03/10/2003 SUSQUEHANNA -UNIT 2 TRM / LOES-2
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM /3.8-19 Page TRM / 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25 3.9 3.10 3.11 3.12 4.0 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 MISCELLANEOUS Pages 3.10-1 through 3.10-4 Page TRM / 3.10-5 Page TRM / 3.10-6 Page TRM / 3.10-7 Page TRM / 3.10-8 RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-12 Pages 3.11-13 through 3.11-16 Pages 3.11-17 through 3.11-21 Pages TRM / 3.11-22 through TRM / 3.11-24 Pages 3.11-25 through 3.11-32 Pages 3.11-33 through 3.11-47 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-5 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 04/02/2002 02/01/1999 06/06/1999 08/31/1998 08/31/1998 08/30/1998 03/08/2003 06/05/2002 04/07/2000 Corrected 04/17/2002 08/31/1998 09/01/1998 08/31/1998 04/02/2002 09/01/1998 08/31/1998 02/05/1999 08/31/1998 EFFECTIVE DATE 03/10/2003 SUSQUEHANNA - UNIT 2 TRM / LOES-3
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title B 3.0 B 3.1 B 3.2 B 3.3 B 3.4 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 CONTAINMENT BASES Page TRM / B 3.6-1 Page TRM / B 3.6-2 Page B 3.6-3 Page TRM I B 3.6-4 Page TRM I B 3.6-5 Pages TRM / B 3.6-6 through TRM / B 3.6-11 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM / B 3.0-11 through TRM I B 3.0-15 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 Page B 3.1-4 Pages TRM / B 3.1-5 through TRM / B 3.1-7 Page TRM / B 3.1-8 Pages B 3.1-9 and B 3.1-10 CORE OPERATING LIMITS BASES Page B 3.2-1 INSTRUMENTATION BASES Page TRM/B 3.3-1 Page B 3.3-2 Pages TRM/B 3.3-3 and TRM / B 3.3-3A Page TRM / B 3.3-4 Pages TRM / B 3.3-5 and TRM I B 3.3-5a Page TRM / B 3.3-6 Pages TRM / B 3.3-7 through TRM / B 3.3-9 Pages B 3.3-10 through B 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM / B 3.3-14b Page B 3.3-15 Page TRM/B 3.3-16 Pages B 3.3-17 through B 3.3-20 Pages TRM / B 3.3-21 through TRM I B 3.3-23 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 Page TRM / B 3.4-5 Page B 3.4-6 08/31/1998 07/26/2001 02/01/1999 08/31/1998 0912311999 01/07/2002 12/31/2002 SUSQUEHANNA
- UNIT 2 TRM I LOES-4 EFFECTIVE DATE 03/10/2003 Effective Date 08/31/1998 03/15/2002 07/13/1999 08/31/1998 07/13/1999 02/18/1999 08/31/1998
'08/31/1998 04/07/2000 08/31/1998 12/29/2000 01/07/2002 12/17/1998 12/17/1998 03/30/2001 08/31/1998 06/25/2002 06/14/2002 06/14/2002 08/31/1998 04/07/2000 08/31/1998 04/02/1999 08/31/1998 10/15/1999 08/31/1998 B 3.5 B 3.6 SUSQUEHANNA -UNIT 2 TRM /LOES-4 EFFECTIVE DATE 03/10/2003
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title B 3.7 B 3.8 B.3.9 Effective Date PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Pages TRM I B 3.7-3 through TRM / B 3.7-7 Page TRM / B 3.7-7a Pages TRM I B 3.7-8 through TRM I B 3.7-10 Page TRM / B 3.7-1Oa Pages TRM / B 3.7-11 through TRM / B 3.7-14 Page TRM I B 3.7-14a Pages TRM I B 3.7-15 and TRM / B 3.7-16 Pages B 3.7-17 through B 3.7-20 Pages TRM I B 3.7-21 through TRM/B 3.7-21a Pages TRM/B 3.7-22 and TRM/B 3.7-23
- Pages B 3.7-24 through B 3.7-30 Pages TRM / B 3.7-31 and TRM / B 3.7-32 Page TRM I B 3.7-33 Pages TRM / B 3.7-34 and TRM / B 3.7-35 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRM / B 3.8-2 Page TRM / B 3.8-2a Page TRM / B 3.8-3 Page TRM 1 B 3.8-3a Page TRM / B 3.8-4 Page TRM / B 3.8-4a Page TRM / B 3.8-5 Pages TRM / B 3.8-6 through TRM / B 3.8-17 REFUELING OPERATIONS BASES Pages B 3.9-1 and B 3.9-2 Pages B 3.9-3 through B 3.9-7 08/31/1998 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08102/1999 08/02/1999 02/01/1999 08131/1998 05/11/2001 04/07/2000 08/31/1998 03/09/2001 07/29/1999 07/05/2000 04/02/2002 04102/2002 04/02/2002 04/02/2002 04/02/2002 04/02/2002 08/31/1998 04/02/2002 08/31/1998 10/23/1998 B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 Page TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM / B 3.10-5 Pages TRM I B 3.10-6 and TRM / 3.10-7 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Pages TRM / B 3.11-10 Pages TRM/B 3.11-11 and TRM/B 3.11-11 a Pages TRM/B 3.11-12 and TRM/B 3.11-13 Page TRM / B 3.11-14 Page TRM / B 3.11-15 Pages B 3.11-16 through B 3.11-19 08131/1998 03/08/2003 08/23/1999 04/17/2002 08/31/1998 02/01/1999 04/0712000 02/01/1999 11/01/1999 02/01/1999 08/31/1998 EFFECTIVE DATE 03/10/2003 SUSQUEHANNA - UNIT 2 TRM / LOES-5
SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / B 3.11-20 Page TRM / B 3.11-20a Pages TRM / B 3.11-21 through TRM / B 3.11-23 Page TRM / B 3.11-23a Page B 3.11-24 Page TRM / B 3.11-25 Pages B 3.11-26 through TRM / B 3.11-35 Pages TRM / B 3.11-36 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 04/02/2002 04/02/2002 04/02/2002 04102/2002 08/31/1998 11/01/1999 08/31/1998 02/12/1999 02/05/1999 EFFECTIVE DATE 03/10/2003 SUSQUEHANNA - UNIT 2 TRM / LOES-6
PL-NF-03-001 Rev. 0 Page 1 of 34 Susquehanna SES Unit 2 Cycle 12 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2003
~Ij ppI SUSQUEHANNA UNIT 2 TRM/3.2-2 EFFECTIVE DATE 03/10/2003 I
PL-NF-03-O01 Rev. 0 Page 2 of 34 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.
Affected No.
Sections Description/Purpose of Revision 0
ALL FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 2 Issuance of this COLR is in support of Unit 2 Cycle 12 operation.
EFFECTIVE DATE 03/10/2003 TRM/3.2-3
PL-NF-03-001 Rev. 0 Page 3 of 34 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 12 CORE OPERATING LIMITS REPORT Table of Contents 1.0 INTRO DUCTIO N....................................................................................................
4 2.0 DEFINITIO NS......................................................................................................
5 3.0 SHUTDOW N MARGIN...........................................................................................
6 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)................... 7 5.0 MINIMUM CRITICAL POWER RATIO (MCPR)......................................................
9 6.0 LINEAR HEAT GENERATION RATE (LHGR)........................................................
20 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS............ 23 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION....................................
26 9.0 REFERENC ES............................................................................................................
33 EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-4
PL-NF-03-001 Rev. 0 Page 4 of 34
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 12 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits and APRM setpoints presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-5
PL-NF-03-001 Rev. 0 Page 5 of 34 2.0 DEFINITIONS Terms used in this COLR but not defined in Section 1.0 of the Technical Specifications or Section 1.1 of the Technical Requirements Manual are provided below.
2.1 The AVERAGE BUNDLE EXPOSURE shall be equal to the total energy produced by the bundle divided by the total initial weight of uranium in the fuel bundle.
2.2 The AVERAGE PLANAR EXPOSURE at a specified height shall be equal to the total energy produced per unit length at the specified height divided by the total initial weight of uranium per unit length at that height.
2.3 The FRACTION OF LIMITING POWER DENSITY (FLPD) shall be the LHGR
-existing at a given height divided by the applicable LHGR for APRM Setpoint Limit for that bundle type.
2.4 The FRACTION OF RATED THERMAL POWER (FRTP) shall be the measured THERMAL POWER divided by the RATED THERMAL POWER.
2.5 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.
2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.
2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.
2.8 FDLRC is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR for APRM Setpoint Limit for the applicable fuel bundle type.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-6
PL-NF-03-001 Rev. 0 SPage 6 of 34 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% Ak/k with the highest worth rod analytically determined OR
-b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.
The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4,.and 5. This includes core shuffling.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-7
PL-NF-03-001 Rev. 0 Page 7 of 34 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUMTM-10 fuel shall not exceed the limit shown in Figure 4.2-1.
The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Two Loop operation.
The APLHGR limits for Single Loop operation are provided in Section 8.0.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-8
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PL-NF-03-001 Rev. 0 Page 9 of 34 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specification Reference Technical Specification 3.2.2, 3.7.6, and 3.3.4.1 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUMTM-1 0) shall be the greater of the Flow Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a)
EOC-RPT and Main Turbine Bypass Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b)
Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC c)
EOC-RPT Inoperable / Main Turbine Bypass Operable Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 5.2-1 through 5.2-6 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
5.3 Average Scram Time Fraction Table 5.3-1 provides the relationship between average scram time to control rod position and scram time fraction. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-10
PL-NF-03-0O01 Rev. 0 Page 10 of 34 EOC-RPT and Main Turbine Bypass Operable EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-11
SSES UNIT 2 CYCLE 12 USED IN DETERMINING MFLCPR S.
9 1
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.4 4
1 4-4 1
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-
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- 4.
I 100 90 (108,1.49)
(108,1.47)
Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-1 C
(/')
crn JCD
"-r N>
(7 1
- 4.
1 2.3 2.2 2.1 2.0 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1
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MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2
(
SSES UNIT 2 CYCLE 12 I
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_ _LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (25,2.30)
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__USED IN DETERMINING MFLCPR (80,1.49)
REFERENCE:
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PL-NF-03-O01 Rev. 0 Page 13 of 34 Main Turbine Bypass Inoperable / EOC-RPT Operable EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-14
(
SSES UNIT 2 CYCLE 12 Cr)
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REFERENCE:
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70 80 90 B
(108,1.79)
Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)
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E1.9 C
4 I-1.8 0
p51.7 1.6 1.5 1.4 1.3 m
-I1~
m m
m C)
--0 C-'
30 100 110 "0 CD CD -
Z o
0 op 0)
L z;;_
I I
I II I
SSES UNIT 2 CYCLE 12 40 50 60 70 80 90 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4
(
(.A C=
-N Z)
(
--A 70 CA W) 3.0 2.9 2.8 2.7 2.6 2.5 2.4 2_.4 E "fl2.3 C. 2.1 0
o.2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3
-1
-- t I-1 C-)
m O
c:)
co rri 0=
-4 P1 20 30 (100,1.79) 100
-u :u -0 0CDr C<
-D Z o
-n CA 0
4:*.
PL-NF-03-O01 Rev. 0 Page 16 of 34 EOC-RPT Inoperable I Main Turbine Bypass Operable EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-17
USED IN DETERMINING MFLCPR
- 4.
1 4
1 4-I 4-I 1
1 1"
I T
.r% -A I
I i
i v
4 EE EN E 3...
and3..2 60 70
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 50 A-B 80 I
90 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5 V.
(-I) c-f P1
=
N-3
-- I IN)
C SSES UNIT 2 CYCLE 12 C.
---t CA)
Ic i---
2.3 2.2 2.1 2.0 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
._E 1.9 CD S1.8 C.
0 o1.7 1.6 1.5 1.4
- 4.
1 4
4-1 4
V~1 "1-1
"~1-1 C-,)
I-I
-- q P1" f--I N)
CD) c::
co 1.3 30 40 (108,1.56) 110 100 0 CD r; (a
(D Z
_ 0 "TI 6
o 9'
0
.0 co 0
I I
I I
t
-030,1..
C
(
SSES UNIT 2 CYCLE 12 V)
Ln
(.A m
Nz
_(25,2.31) 4 4
1 4
4 1r,,% i
I 4-4 4
4-I 4
1 I
USED IN DETERMINING MFLCPR R3Aa
- B
-t
REFERENCE:
T.S. 3.3.4.1 and 3.2.21 (74,1.56)-
30 40 50 60 70 80 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6 90 (100,1.56) 100 S(D (0
CD
..L0 0
CA)
(
II I
I I LEGEND
,CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I I N,
I-.
3.0 2.9 2.8 2.7 2.6 2.5 2.4 E
l2.3 01 "E 2.1 0
.2.0 0
1.9 1.8 1.7 1.6 1.5 1.4 1.3 m
-'1 n
CA)
CI 20 r-t
,-n z
CA) 0 0
I
PL-NF-03-001 Rev. 0 Page 19 of 34 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)
Position 45 0.470 0.480 0.490 0.500 0.510 0.520 39 0.630 0.676 0.722 0.768 0.814 0.860 25 1.500 1.582 1.664 1.746 1.828 1.910 5
2.700 2.848 2.996 3.144 3.292 3.440 Scram Time -
0.000 0.200 0.400 0.600 0.800 1.000 Fraction Average Scram Realistic Maximum Insertion Time Allowable EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-20
PL-NF-03-001 Rev. 0 Page 20 of 34 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The LHGR limits are specified below as a function of Main Turbine Bypass operability for each fuel type as follows:
Main Turbine Bypass Operable The LHGR for ATRIUMTM-10 fuel shall not exceed the LHGR limit determined
-from Figure 6.2-1.
Main Turbine Bypass Inoperable The LHGR for ATRIUMTM-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-2.
The LHGR limits in Figures 6.2-1 and 6.2-2 are valid for Two Loop and Single Loop operation.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-21
16 SSES UNIT 2 CYCLE 12 S~16
l"..................."
9.,1 15000,13...
9 9
- ~~~ ~
9 RE ERENCE
.9 3.2.3 1
9 1
USED I ETEN
.12 RE R NC : S323 I,..........
..... U N
EG...........
2......
-6I
~ 1------------------...............
N.
N.
4 0
10 20 I0 I0 50 60 70000 6o 10
- d.
- 9.
..J J..
9=
o
'*.9....
'........9
9" 9"
"9, 9
-o 9.i.
9 9..t
.o.
o 9
9.i.
.0.
0...
I....
i 9
I O
Average Planar Exposure (MWDIMTU) 0 Dr Ci)
(D.
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE
-.L MAIN TURBINE BYPASS OPERABLE 0
ATRIUMTM-10 FUEL FIGURE 6.2-1
(__
(_.
C 16SSES UNIT 2 CYCLE 12 14
- a.
0.0,11.9:
15000,11.9 USED IN DETERMINING FDLRX
.12
.a
- 1.
1 0.0.9.........
II USED IN DETERINING F.LRX I8 C-).
1....................
CD a
6700, 6.36 CA)
I I
I I
I a
.I l
l
. 0 1
I a I a 6
7 a
I a a
i,
a a
a I
a a
Na I
I I a.
A e a a
E a
I a
a I
N))
4 MAIN TURBINE BYPASS INOPERABLE 0
9, TIUMT ATRIU 10 FUEL_
FIGURE 6.2-2
PL-NF-03-O01 Rev. 0 Page 23 of 34 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS 7.1 Technical Specification Reference Technical Specification 3.2.4 and 3.3.1.1 7.2 Description The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRB) shall be established as specified in Table 7.2-1 and Table 7.2-2, including any adjustments per Technical Specification LCO 3.2.4.
Technical Specification LCO 3.2.4 provides an option to adjust the APRM
.setpoints when MFLPD is greater than FRACTION OF RATED THERMAL POWER (FRTP). The adjustment applies to both the APRM flow biased simulated thermal power-upscale scram trip setpoint and flow biased neutron flux-upscale control rod block trip setpoint for Two Loop and Single Loop operation. The APRM setpoints for Specification 3.2.4 are established in Tables 7.2-1 and 7.2-2.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-24
PL-NF-03-001 Rev. 0 Page 24 of 34 Table 7.2-1 APRM Setpoint for Two Loop Operation Trip Setpoint Allowable Value S < (0.58W + 59%) T S5< (0.58W + 62%) T1 SRB < (0.58W + 50% T SRB (0.58W + 53%) T Table 7.2-2 APRM Setpoint for Single Loop Operation Trip Setpoint Allowable Value S < (0.58W + 54%) T S < (0.58W + 57%) T' SRB < (0.58W + 45%) T SRS < (0.58W + 48%) T where: S and SRB are in percent of RATED THERMAL POWER W =
Loop recirculation flow as a percentage of the loop recirculation flow which produces a core flow of 100 million lbs/hr T =
Lowest value of the ratio of FRTP divided by the MFLPD.2 The FLPD is the actual LHGR divided by the applicable LHGR limit for APRM Setpoints. The LHGR limit for APRM setpoints for ATRIUMTM-10 fuel shall be taken from Figure 7.2-1.
The LHGR for APRM setpoint limits in Figure 7.2-J are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable for both Two and Single Loop operation.
For calculated T-values greater than 1.0, a ratio of 1.0 is used in the above equations.
APRM flow biased simulated thermal power-upscale scram allowable value in this table is equal to the value established in Technical Specification 3.3.1.1.
2 For the calculation of T, the value of MFLPD shall be the maximum value of FDLRC.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-25
S 1SSES UNIT 2 CYCLE 12 0
1 0 15000,15.0...
- EDNEEMNN F
E I
- z 1
I...
I...........-
r I..
.US DIDE RMN GFD C
0 c I
IL I.0.
.E rr.
wo C-)
CII I
I I
S I
I I
I I
I
.(U.J.
.S..
S S
I S.
S I
.p.*
S.
l.
S I
I t
I I
,r* =,",,10 S...........................
I il*.
.*"I"I*.
II"
.*I""I*......i" i
iIli....
S S
S S
S o
.S SS
,4 CD0 10000 20000 30000 40000 50000 60000 70000 CD
~~Average Planar Exposure (MWD/MTU)
(Dr LINEAR HEAT GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE cn C
0 oO ATRIUMTM -10 FUEL
- 9.
FIGURE 7.2-1
PL-NF-03-O01 Rev. 0 Page 26 of 34 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.2.4, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUMTM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.
The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Single Loop operation.
Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limit for all fuel types (ATRIUMTM-10) shall be the greater of:
a)
Flow-Dependent MCPR value determined from Figure 8.2-2 OR b)
The Power-Dependent MCPR value determined from one of the following figures, as appropriate:
Figure 8.2-3:
EOC-RPT and Main Turbine Bypass Operable from BOC to EOC Figure 8.2-4:
Main Turbine Bypass Inoperable / EOC-RPT Operable from BOC to EOC Figure 8.2-5:
EOC-RPT Inoperable / Main Turbine Bypass Operable from BOC to EOC The MCPR limits in Figures 8.2-2 through 8.2-5 are valid only for Single Loop operation.
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRMI3.2-27
PL-NF-03-001 Rev. 0 Page 27 of 34 Averagqe Power Range Monitor (APRM) Gain And Setpoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined in Section 7.0.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-28
16SSES UNIT 2 CYCLE 12 S
16 z 14...........
REFERENCE T.S. 3.4.1 and3.2 1 N..
USEDIN DETERMININGMAPRAT N
2 1..
t-U)
I 0
9.:
1....
,.m "C-U m
- ~~~
~
~
~
~
~
- 4.
m "4-,
o 0.
I.
c)0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE OD SINGLE LOOP OPERATION 01 ATR
_TM10 FUEL FIGURE 8.2-1
C-,)
-r m
m N)
CD CD)
W P1 C,)
I-I P-1
.-H PT1 CA) 2.6 2.5 2.4 E2.3 S2.2
- 0.
0 S2.1 2.0 1.9 1.8 4
I
-A B
50 60 70 80 90 I
I I
I D
A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I I
I USED IN DETERMINING MFLCPR Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2 SSES UNIT 2 CYCLE 12 (30,2.20) 4 I -
I r'*
4 I-30 (je2.0
- 1*
I I
40 100 110
-u m CD '
,-D z -n 6
0 0
REFERENCE:
T.S. 3.4.1 and 3.2.21 4
1
-(108,2.20)
(
Cr),7)
"T r'>
30 40 50 60 Core Power (% RATED) 70 80 90 100 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3 SSES UNIT 2 CYCLE 12 3.5 3.4 3.3 3.2 3.1 3.0 C
-I I
I
__LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-- (25,2.75)
USED IN DETERMINING MFLCPR S(30,2.69) i
-A B
(39.4,2.20)
-t
REFERENCE:
T.S. 3.4.1 and 3.2.2I S2.9 E
m 2.8 4s 2.7
- 0.
0 S2.6 C 2.
S2.5 2.4 2.3 2.2 2.1 2.0 1.9 m
-i11 c'1 CD, P1 CD~
CD~
20 (100,2.20) u mD T "m *0 "o CO<
D-Z 0o o 0
- 6.
0
(I 20 30 40 50 60 70 80 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4 C
SSES UNIT 2 CYCLE 12
(.A CI P1 z
-H
-H CA
I'3 "n
-n" m
C--)
-H P1 c:)
C)
C=:)
3.5 3.4 3.3 3.2 3.1 3.0 2.9 m2.8
"* 2.7
- 0.
0 X 2.6 S2.5 2.4 2.3 2.2 2.1 2.0 1.9 (100,2.20) 90 100 (D
- 0
"-0 z -,1 0
Co 0
0..
Co CD Co
-L 0
Co
(.
Cl) rn m
-r N)::
30 40 50 60 70 80 90 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-5 3.5 3.4 3.3 3.2 3.1 3.0 SSES UNIT 2 CYCLE 12 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
- (25,2.76)
S(30,2.69) _...
_____USED IN DETERMINING MFLCPR
-A B
(39.4,2.20)
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2
-4 N)
CA)
CA)
- t 2.9 E
o 2.8 a 2.7
- 0.
0 cc 2.6 S2.5 2.4 2.3 2.2 2.1 2.0 1.9 m
-rI' m
C-,)
--A m
1-4 C=)
CD, 20 (100,2.20) 100 D)CD r;
<O CD -Z c
o-n No 6
o
,p 0
°
PL-NF-03-001 Rev. 0 Page 33 of 34
9.0 REFERENCES
9.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:
- 1. PL-N F-90-001 -A, "Application of Reactor Analysis Methods for BWR Design and Analysis," July 1992.
- 2. PL-NF-90-001, Supplement 1-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Loss of Feedwater Heating Changes and Use of RETRAN MOD 5.1," August 1995.
- 3. PL-NF-90-001, Supplement 2-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: CASMO-3G Code and ANFB Critical Power Correlation," July 1996.
- 4. PL-NF-90-001, Supplement 3-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Application Enhancements," March 2001.
- 5. XN-NF-80-19(A), Volume 1, and Volume 1 Supplements 1 and 2 (March 1983),
and Volume 1 Supplement 3 (November 1990), "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis,"
Exxon Nuclear Company, Inc.
- 6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," September 1982.
- 7. XN-NF-80-1 9(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," January 1987.
- 8. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, Inc. June 1986.
- 9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,
September 1986.
- 10. ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November 1990.
- 11. NE-092-001 A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-34
PL-NF-03-001 Rev. 0 Page 34 of 34 1-2. ANF-89-98(P)(A) Revision 1 and Revision 1 Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 13. ANF-91-048(P)(A), "Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model," January 1993.
- 14. XN-NF-79-71(P)(A) Revision 2, Supplements 1,2, and 3, "Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.
- 15. EMF-1997(P)(A) Revision 0, "ANFB-10 Critical Power Correlation," July 1998, and EMF-1 997(P)(A) Supplement 1 Revision 0, "ANFB-1 0 Critical Power Correlation : High Local Peaking Results," July 1998.
- 16. Caldon, Inc., "TOPICAL REPORT: Improving Thermal Power Accuracy and "Plant Safety While Increasing Operating Power Level Using the LEFM4rM System," Engineering Report - 80P, March 1997.
- 17. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMTm or LEFM CheckPlus System," Revision 0, Engineering Report ER-1 60P, May 2000.
- 18. EMF-85-74(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements 1 and 2, February 1998.
- 19. EMF-2158(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn B2," Siemens Power Corporation, October 1999.
EFFECTIVE DATE 03/10/2003 SUSQUEHANNA UNIT 2 TRM/3.2-35