ML033280181
| ML033280181 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/14/2003 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Security and Incident Response |
| References | |
| 28401 | |
| Download: ML033280181 (44) | |
Text
Nov. 14, 2003 Page 1 of 1 K>
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- NUCSA-2)
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SUSQUEHANNA STEAM ELECTRIC STATION . PPL Rev. 3 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)-
Section Title Effective Date
.102..2..0 TOC TABLE OF CONTENTS 10/22/2003 1.0 USE AND APPLICATION Pages TRM / 1.0-1 through TRM /.1.0-3 10/04/2002 2.0 PLANT PROGRAMS Pages 2.0-1 through 2.0-2 0813111998 Page TRM / 2.0-3 08/01/2001 Page TRM /2.0-4 06/25/2002 Page TRM / 2.0-5 04102/1999 Pages TRM /2.0-6 and TRM /2.0-7 10122/2003 Page TRM / 2.0-8 03/2912000 Page TRM / 2.0-9 09/0412002 Pages TRM / 2.0-10 and TRM /2.0-1 1, 04/02/1999 Page TRM / 2.0-12 10/22/2003 Page TRM / 2.0-13 06/1612000 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM 04/08/1999 Pages TRM / 3.0-3 03/15/2002 Page TRM /3.0-4 , 04/08/1999 3.1 REACTIVITY CONTROL SYSTEMS Pages 3.1-1,through 3.16 08/31/1998 Pages TRMU 3.1-7,aned TRM / 3.1-8 06/05/2002 PagesTRM 1,3.1-9 and TRM / 3.1-9a * ..~' 02/18/1999 Page-TRM'/ 3:1.-10 02/18/1-999 3.2 CORE OPERATING LIMITS REPORT
- PagejRM / 3.2-1 07/07/1999 Pages TRM / 3.2-2 through TRM / 3.2-37 11/0112003 I 3.3 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM / 3.3-4 1112812000 Pages 3.3-5 through 3.3-8 08/31/1998 Pages TRM / 3.3-9 and TRM / 3.3-9a 12/17/1998 Pages TRM / 3.3-10 and TRM / 3.3-11 12/17/1998 Page TRM / 3.3-12 03/30/2001 Pages TRM / 3.3-13 and TRM / 3.3-14 12/14/1998 Page TRM / 3.3-15 10/22/2003 Page TRM / 3.3-16 06/27/2001 Pages TRM / 3.3-17 and TRM / 3.3-18 06/1412002 Pages TRM / 3.3-19 through TRM / 3.3-21 10/2212003 SUSQUEHANNA - UNIT 1 TRM / LOES-1 EFFECTIVE DATE 11/01/2003
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 3 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page 3.3-22 08/31/1998 Pages TRM / 3.3-23 through TRM / 3.3-25 05/16/2003 Page TRM / 3.3-26 10/22/2003 3.4 REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 10/23/1998 Pages 3.4-6 through 3.4-13 08/31/1998 3.5 EMERGENCY CORE COOLING AND RCIC Pages 3.5-1 through 3.5-3 08131/1998 Page TRM / 3.54 04/17/2000 Pages 3.5-5 through 3.5-7 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 through 3.6-3 08/31/1998 Page TRM / 3.6-4 01/07/2002 Page 3.6-5 08/31/1998
-Pages TRM / 3.6-6 through TRM / 3.6-8 12/31/2002 3.7 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Pages TRM / 3.7-4 through TRM / 3.7-10 - 08/02/1999 Page TRM / 3.7-11 12/29/1999 Pages TRM / 3.7-12 through TRM / 3.7-27 08/02/1999 Pages TRM / 3.7-28 through TRM / 3.7-34 11/1612001 Page TRM / 3.7-34a 10/05/2002 Pages TRM / 3.7-35 through TRM / 3.7-37 02/01/1999 Pages 3.7-38 through 3.7-40 08/31/1998 Pages TRM / 3.7-41 and TRM / 3.7-41 a 08/11/2000 Pages 3.7-42 and 3.7-43 08/31/1998 Pages 3.7-44 through 3.7-48 10/13/1998 Page TRM / 3.7-49 03/08/2003 Pages TRM / 3.7-50 and TRM / 3.7-51 03/0912001 Pages TRM / 3.7-52 and TRM / 3.7-53 04/15/2003 Page TRM / 3.7-54
- 07129/1999 3.8 ELECTRICAL POWER Pages TRM / 3.8-1 and TRM / 3.8-2 04/02/2002 Page 3.8-3 08/31/1998 Page TRM / 3.8-4 12/31/2002 Pages TRM / 3.8-5 and TRM / 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM / 3.8-9 08/31/1998 Page TRM / 3.8-10 07/1912001 Page TRM / 3.8-11 04/02/2002 SUSQUEHANNA - UNIT I TRM / LOES-2 EFFECTIVE DATE 11/01/2003
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 3 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)'
Section Title Effective Date Page TRM / 3.8-11 a 04102/2002 Pages 3.8-12 through 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM /3.8-17 04102/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 Page 3.8-20 08/31/1998 Pages TRM / 3.8-21 through TRM / 3.8-23 06/06/1999 Pages 3.8-24 and 3.8-25 08/31/1998 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Pages 3.10-1 through 3.10-4 08/31/1998 Page TRM / 3.10-5 03/08/2003 Page TRM /3.10-6 06/05/2002 Page TRM / 3.10-7 04/07/2000 Corrected Page TRM / 3.10-8 04/1712002 3.11 RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-121 08/31/1998 Pages 3.11-13 through 3.11-16 09/01/1998 Pages 3.11-17 through 3.11-21 08/31/1998 Pages TRM / 3.11-22 through TRM / 3.11-24 04/02/2002 Pages 3.11-25 through 3.11-32 . 09/01/1998 Pages 3.11-33 through 3.11-47 08/31/1998 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-5 02105/1999 4.0 ADMINISTRATIVE CONTROLS Pages 4.0-.1 through 4.0-8 08/31/1998 SUSQUEHANNA - UNIT 1 TRM / LOES-3 EFFECTIVE DATE 11/01/2003
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev.-3 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)-
Section Title Effective Date B3.0 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 08/31/1998 Pages TRM / B 3.0-11 through TRM / B 3.0-15 03115/2002 B3.1 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 07/1311999 Page B 3.1-4 08/31/1998 Pages TRM IB 3.1-5 through TRM / B 3.1-7 07/1311999 PageTRM/B3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 04/07/2000 Page B 3.3-2 08/31/1998 Pages TRM / B 3.3-3 and TRM / B 3.3-3A 12/2912000 Pages TRM / B 3.3-4 through TRM / B 3.3-6 03/2112003 Pages TRM / B 3.3-7 through TRM / B 3.3-9 03/30/2001 Pages B 3.3-10 through B 3.3-12 08/31/1998 Page TRM / B 3.3-13 10/22/2003 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 06/14/2002 Page TRM / B 3.3-14b 06/14/2002 Pages TRM / B 3.3-15 and TRM I B 3.3-16 10/22/2003 Page TRM / B 3.3-17 04/07/2000 Pages TRM / B3.3-18 and TRM I B 3.3-19 05/16/2003 Page TRM / B 3.3-20 10/22/2003 Page TRM / B 3.3-21 05/16/2003 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 08/31/1998 Page TRM / B 3.4-5 10/15/1999 Page B 3.4-6 08/31/1998 B3.5 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 09/23/1999 Page TRM / B 3.6-5 01/07/2002 SUSQUEHANNA - UNIT 1 TRM/LOES4 EFFECTIVE DATE 11/01/2003
SUSQUEHANNA STEAM ELECTRIC STATION . PPL Rev. 3 LIST OF EFFECTTIESECTIONS (TECHNICAL REQUIREMENTS MANUAL)'
Section Title Effective Date
. 2. /...
Pages TRM / B 3.6-6 through TRM / B 3.6-11 12/31/2002 B3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Pages TRM / B 3.7-3 through TRM / B 3.7-7 08/02/1999 Page TRM / B 3.7-7a 08/02/1999 Pages TRM / B 3.7-8 through TRM / B 3.7-10 08/02/1999 Page TRM / B 3.7-10a 08/02/1999 Pages TRM / B 3.7-11 and TRM I B 3.7-1 la 08/02/1999 Pages TRM / B 3.7-12 through TRM / B 3.7-14 08/02/1999 Pages TRM'/ B 3.7-14a and TRM / B 3.7-14b 08/02/1999 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRMIB 3.7-21 through TRM/B 3.7-21 a 05/11/2001 Pages TRM/B 3.7-22 and TRM/B 3.7-23 04/07/2000 Pages B 3.7-24 through B 3.7-30 08/31/1998 Pages TRM / B 3.7-31 and TRM I B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04/15/2003 Pages TRM / B.3.7-34 and TRM / B 3.7-35 07/05/2000 B3.8 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRMJ/ B 3.8-2 04/02/2002 Page TRM / B 3.8-2a ': . 04/02/2002 Page TRM / B 3.8-3 04/02/2002 Page.TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 -. 04/02/2002 Page TRM / B 3.8-4a 04/02/2002 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-17 04/02/2002 B.3.9 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7' 08/31/1998 B 3.10 MISCELLANEOUS BASES
- Pages B 3.10-1 through B 3.10-2 08/31/1998 Page TRM / B 3.10-3 03/0812003 Pages TRM / B 3.10-4 and TRM /B3.10-5 08/23/1999 Pages TRM / B 3.10-6 and TRM / B 3.10-7 04/17/2002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/30/1998 Page TRM / B 3.11-10 02/0111999 Pages TRM/B 3.11-11 and TRM/B 3.11-1 1a 04/07/2000 Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 SUSQUEHANNA - UNIT I TRM / LOES-5 EFFECTIVE DATE 11/01/2003
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 3 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANlUAL)'
Section Title Effective Date Page TRM B 3.11-14 11/01/1999 PageTRMlB3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/30/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM B 3.11-20a 04/02/2002 Page TRM B 3.11-21 04/02/2002 Page TRM I B 3.11-22 0912612003 Page TRM / B 3.11-23 04/0212002 Page TRMI B 3.11-23a 04/02/2002 Page TRMI B 3.11-24 03/2112003 Page TRM/B3.11-25 04/1512003 Pages B 3.11-26 through B 3.11-35 08/30/1998 Page TRM / B 3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 02/05/1999 NFMTRMI WAxMOESA=o
.SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 11/01/2003
Core Operating Limhits Report (COLR)
PPL Rev. 1 3.2.1 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)
TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.
APPLICABILITY: Specified in the referenced Technical Specifications.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits A.1 Perform action(s) Specified in not met. described in referenced referenced Technical Specification. Technical Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY
-NOTE N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT 1 TRM / 3.2-1 EFFECTIVE DATE 7/07/1999
PPL Rev. 1 PL-NF-02-001
- Rev. 2
.. Page 1 of 36 Susquehanna SES Unit 1 Cycle 13 CORE OPERATING LIMITS REPORT Nuclear Fuels.
Engineering November 2003 SUSQUEHANNA UNIT 1 TRM/3.2-2 EFFECTIVE DATE 11/01/2003
PPL Rev. I PL-NF-02-001 Rev. 2 Page 2 of 36 CORE OPERATING LIMITS.REPORT . . r REVISION DESCRIPTION INDEX Rev. Affected No. Sections Description/Purpose of Revision 0 ALL Issuance of this COLR is in support of Unit I Cycle 13 operation.
1 5.0 This revision adds a text box to all appropriate plots. This text box indicates 6.0 that for all bypass operable cases, four bypass valves are assumed 8.0 operable. For the bypass inoperable cases, the text box indicates that two or more bypass valves are assumed inoperable.
This revision was generated'in response to Facility Operating License Amendment 210 which altered SR 3.7.6.1.
This revision is administrative in nature and no underlying calculations or plotted data were altered.
TOC This revision adds the Power ?Flow map to the COLR. Section 1.0 was 1.0 revised to include the stability regions as part of the COLR. The Power /
9.0 Flow map was added as Section 9.0. The Reference section was 10.0 renumbered as Section .10.0 and a stability reference added.
This revision is administrative in nature since the Power I Flow map is already included in NDAP-QA-0338.
FORM NFP-QA-008-2, Rev. I SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-02-001 Rev. 2
--~. Page 3 of 36 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 13 CORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
.............. 4 2.0 DEFINITIONS ............... .5 3.0 SHUTDOWN MARGIN ......... ;6 3.0 H T O N M R I ......................................................................................... 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 POWER FLOW MAP ........................................................33
10.0 REFERENCES
.. 35 SUSQUEHANNA UNIT 1 TRM/3 .2-4 SEFFECTIVE DATE 11/01/2003
PPL Rev. I PL-NF-02-001 Rev. 2
- . Page 4 of 36
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 13 is prepared in accordance with the requirements of Susquehanna Unit 1, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, APRM setpoints, and stability regions presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.
SUSQUEHANNA UNIT 1 TRM/3.2-5 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 5 of 36 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.
SUSQUEHANNA UNIT 1 TRM/3 .2-6 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 6 of 36 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 ppison 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, "Rn. 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 UR" 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. -
,SUSQUEHANNA UNIT 1 ' TRM/3 .2-7 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 - PL-NF-02-00.1 Rev. 2 Page 7 of 36 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 DescriDtion The APLHGRs forATRIUMm-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.
SUSQUEHANNA UNIT 1 TRM/3 .2-8 EFFECTIVE DATE 11/01/2003
Q) q C, (A,
SSES UNIT 1 CYCLE 13 C=
12 0.0,11.'5 _ _ _ 15000,11.'5
{EEENCE T.S.3~
-4
~-4 11
___ __E_ ETERMINING __ 3_
_ io 10
.E
--4 C.I a:
-U I-om mc 8 5X
<v e~ 8
. 0
.C I
6
-n 5 _ _ _ --.-
-n 59400,6.7 C-4 Il
'-S -- t000 - - -000 I-. 0 10000 20000. . 30000 40000 50000 60000 70000 I'
Average Planar Exposure (MWDIMTU)
IoM la
.,w 0 7 AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS -1 to<
m W;4 z
-n AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION 6
.I 0h ATRIUMTM.10 FUEL ,Iw 6 FIGURE 4.2-1 1. 0) Q-a
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 9 of 36 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 (ATRIUMT ' 1-10) 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 I 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 . I _
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.
SUSQUEHANNA'UNIT 1 - TRM/3.2-10 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 *PL-NF-02-001 Rev. 2 Page 10 of 36 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2 EFFECTIVE DATE 11/01/2003
(02 Li C)
(A SSES UNIT 1 CYCLE 13 2.3 (A
0-4
!Al 0I r%3 1-SA 1!
0 a.
C)
-n m
m CD, 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) X A MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW .
EOC.RPT AND MAIN TURBINE BYPASS OPERABLE 6 TWO LOOP OPERATION (BOC TO EOC) a FIGURE 5.2-1
(9; c) C; SSES UNIT 1 CYCLE 13 C,) 3.0 m 2.9 2.8
-4 2.7 2.6 4
2.5 C.,-
2.4 xEn 2.3
- 0) I-1~3 = 2.2 CA, ED A.2.1
<- 2.0 1.9 m
7n
-n 1.8 m
C-.)
-4 1.7 ri 1.6 m (100.1.53) 1.5 I-. (100,1.47)
'-S C) 1.4 CD, 1.3 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
- CD) 0 MCPR OPERATING LIMIT VERSUS CORE POWER 0 &)n-EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 13 of 36 Main Turbine Bypass Inoperable I EOC-RPT-
- Operable SUSQUEHANNA UNIT I TRM/3.2 EFFECTIVE DATE 11/01/2003
0C2. C0 IC0.
Ln 2.3 SSES UNIT I CYCLE 13 1 1 I C
rr m
2.2 4 -4 4 4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM D INSERTION TIME C-2.1 4 4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 4-1~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
I I I 2;0 I I I_
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 E 1.9 Jow c (30l1.78) . USED IN DETERMINING MFLCPR -U (30,1.78)..I_ cu I-
'-A
(.1n ! 1.8
_, . (108,1.75) 0 _ .__ __R_ _ _ _ _ _ _ A B 0.
0 1.7 (37 1.1
- 75) _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
mn
-n 1.6 m
C-4
'-4 m
1.5 L-41 l
REFERENCE:
TYS. 3.2.2l m
t-as 1.4 . , .. . ;.~~4 (A) 1.3 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) m_o0 < z M.,
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 7
- 0 MAIN TURBINE BYPASS INOPERABLE I EOC.RPT OPERABLE .- 4
-b I wn TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2.3
(
(9 C(2 3.0 SES UNIT 1 CYCLE 113 (AZ m 2.9 . = ~LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.7 ._(25,2.64) - l INSERTION TIME
-4i .___.__\_ CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.6 2.5 2.4 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 E 2.3 a) -u
!:Al
, 2.2 u
=~~~~~~~~~~UE INDETERMINING MFLCPR- (-
I!
0)~ CD K 2.1 2.0 (40,2.04)A 1.9 m 1.8
-I, m (100,1.75) 1.7 (68.2,1.75) 4-I 1.6
-I 1.5
REFERENCE:
T.S. 3.7.6 and 3.2.2 I.- - ______ _ ___ _,__ . _ _ _ '__
_ .__ _ _ _ _i . . .____
t-S 1.4 CD) 1.3 - _________________
' I _________________ . L . , __________________ . ___________________
20 30 40 . *I 50 60 70 80 90 100 Core Power (% RATED) la' '3 5O I,-
CD N) z MCPR OPERATING LIMIT VERSUS CORE POWER .0 MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE ,0 0 TWO LOOP OPERATION (BOC to EOC) 0?
FIGURE 5.2-4
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 16 of 36 EOC-RPT Inoperable I Main Turbine Bypass Operable SUSQUEHANNA.UNIT I TRM/3.2-17 EFFECTIVE DATE 11/01/2003
0 (i (ii (In 2.3 SSES UNIT I CYCLE 13' I I I .I LEGEND .
'-a 2.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.1 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.0 I'i
. __._____l JSAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE
-Il r- OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 S 1.9 rri Z3 USED IN DETERMINING MFLCPR 10 0
--4 a1.
m- 0.
- a. .,
U 1.7 -* 4 + 4 1 4 4 (30,1.64)
I 1.
A IAk I- (108,1.64) 1.6 1.5
REFERENCE:
T.S. _X 3.2.21 - ~~~. T.'.
. .1 ..
1.4 1.3 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE 4w 6 TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5
0I C (j (A1 SSES UNIT 1' CYCLE 13 ' ' r 3.0 r 'r' '
VI)
I I I I 2.9 I I LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.7 .
--I CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I-a 2.6 I I. I _
2.5 i i i Ii I I',
2.4 (25,2.41) . (30,2.41)
_ SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE L
-4I OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 HE2.3 CA) 0I
.\___.__. USEID IN DETERMINING MFLCPR . D
-u
. r,
= 2.2 I-O 2.1
& 2.0 1.9 n, ____________ ~(40,1.90) A
-n, 1.8
_ _ _B_ __ __
1.7 P1 (100,1.64) 1.6 (74,1.64) m IRr-FFRFNr-F;. T-s. a~a4i and ~22I2 I-a 1.5 - ~~~z~~a-I *t i
-t t~~~~ - . .',..
1- I r\3 CDO 1.4 1.3 20 30 40 I .1 50
. . 1 60 I _ _
70 I-_ _ _ I 80
_ _ _ _ I 90 100 Coro Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER - co X
0
_b EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE , 0 CD -&
TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2.6
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 19 of 36
-Table 6.3-1 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 SUSQUEHANNA UNIT 1 TRM/3 .2- 20 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 20 of 36 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 Onerable The LHGR for ATRIUM'm-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.
Main Turbine Bvpass 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.
SUSQUERANNA UNIT 1 ' TRM/3.2-21 EFFECTIVE DATE 11/01/2003
0 C-,-.
C/)
SSES UNIT 1 CYCLE 13 16 (A
_ ____ __ _ _ _ __ I I I I I-II I IIIIIIIII_
C=
14 111
_ _- _ _ _ _ _ _ _ _ _ _ ____OPERABLE
.- SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE PER SR 3.7.6.1 AND 3.7.6.2 0.0,13.4 15000.0,13.4
REFERENCE:
T.S.3.2.3 I.
- 12 USED IN DETERMINING FDLRXj 4.'
m DI, r-T 7-4 0 r-
'-4 c 0 .
G 0-
--4 m8
. 59400.0,8.0 m 6 I-J _ _ _ _ _ _ _ _ _ _ _ I _ _ _ - - 1 1 1 1 I I. I
.C.,
4 0 10000 ' 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWDIMTU) . TDm Z
. to 0 7 LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE
. N MAIN TURBINE BYPASS OPERABLE ATRIUMTM-10 FUEL 1CA)
'. _m 0
FIGURE 6.2-1
PPL Rev. 1 PL-NF-02-001
, Rev.2 g .Page.22 of 36 II I1 I I I1 I I .1 I r go a,
g N 9
m I' 0 CD
< U U-r1 1 ~~~ ,I 40 o ox 0 0
- c. _ _ I _ It In I LU o Cl aw C,
ri a:
w W-0 I IA I0 CD 0
0.
0.
Ww 0 .
UJ CO) z 1Ht A17 1 . l 1 -~~~~~~~~~~~ 03 0D 07 x F1
- a. L.: 0 ww LuW 0IL 2: I-w-i ' -I I 1 /1 .1 I 1-I I I I CO 'mj 0
II Il/I CD 6 C.) za,
< Ul I (U 2
~
- LU 0
L> 0.
x
<L LU Z I-L..
LUJ a,
CO co rl, I 1 /I I- I I- - CD 0
El 0)
- 0) tu, z .
z.
CD I I-CZ 40 LU z
C)
=~~~ I-1
- 04 Ini 11111
== °r f~ I I TT C.-
0 Q
N .C c (tuMqI)a!wnfe2 UOpwJausO ;eaH Jleaur SUSQUEHANNA UNIT 1 TRM 3.2-23 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 23 of 36 "9 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.
K)~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
SUSQUEHANNA UNIT 1 , TRM/3.2-24 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 24 of 36 Table 7.2-1 .-
APRM Setpoint for Two Loop Operation Trip Setpoint Allowable Value S 5 (0.58W + 59%) T S < (0.58W + 62%) T' 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 S5 (.8W A + 57%) T'l SRB * (0.58W + 45%) T SRB * (0.58W + 48%) T where: S and SRB are in percent of RATED THERMAL POWER W = Loop recirculation flow as a percentage of the loopI 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 7.2-1 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.
SUSQUEHANNA UNIT 1 TRM/3.2 EFFECTIVE DATE 11/01/2003
0i (Ii 0i Ln SSES UNIT 1 CYCLE 13 jJ CA U) 18 R~~~~~~~EFERENCE: T.S. 3.2.4
'4i 16
-I 15000,15.0 l-_ l _ __ _ __ _ _ _ _ _ _ _ _ _ USEDINDETERMINING FDLRC J
4 0.0,1 5.0 E:
n E14 C .0 C. o . -u lfi2 u 1 0
- I-o0 Q)
Q-0 01 ZI m
m 59400,9.1 8
C-I m l I-nj 6
0 10000 20doo 30000 40000. 50000 60000 70000 I--&
Average Planar Exposure (MWDIMTU)
C.,
to0 I-7 LINEAR HEAT'GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE *0* Z p"J - 1 ATRIUMm -10 FUEL FIGURE 7.2-1 .0&
PPL Rev. 1. PL-NF-02-001 Rev. 2 Page 26 of 36 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Soecification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUMThU-1 0 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 (ATRIUM'-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 I 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.
SUSQUEHANNA UNIT 1 TRM/3.2-27 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 27 of 36 Average Power Range Monitor (APRM) Gain And Setnoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined in Section 7.0.
SUSQUEHANNA UNIT 1 TRM/3.2 EFFECTIVE DATE 11/01/2003
0~ I-,.'
CLI SSES UNIT I CYCLE 13 12 m
. X l ] [] 1 1 _ _ __ _ _ _ REFERENCE T.S. 3.4.1 and ___
11
--I g-a _-__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 1 USEDINDETERMINING MAPRAT
-10
.0.
E 0.0,9.2 15t0009.2-7------ -
--4 cS 9
I-u tDo c I-
- 0. ;0 00 CD 04-D 8
c 0 7 07 m
-4 Ei 6 \
A59400.4
'-a 5
I.- 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWDIMTU)
CA) . t o<,
- 'c z AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE
. co SINGLE LOOP OPERATION
. o Ca ATRIUMTM-10 FUEL ' 0 °4 FIGURE 8.2-1
C)11 C c l SSES UNIT 1 CYCLE 13 (A
I I I0 I LEGEND c-'
2.5 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 __ _ _~~_. _ _ _I
. ~~ ~ ~ ~~~~~~ I..
CA) . I I t: 2.3- USED IN DETERMINING MFLCPR E .
-n
-u I' (108,2.20) c (30,2.20) I-0 2.2 1 4 'A B - ~ ~ . CD I
'*1 0 cL 0.
~1~
CA)
CD 2.0 -
MI, I-.
'- I -l a.
N, 1.9 - ---
REFERENCE:
T.S. 3.4.1 and 3.2.21 - t 1 4 I .
I II CA) I* .
1.8 I*- 4. 4. ________ I- .
30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbmlhr) fIV 0 I-5 z
.c0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW '1 SINGLE LOOP OPERATION (BOC to EOC) N CD FIGURE 8.2-2 -.0)
0al Q) C-)
CA SSES UNIT I CYCLE 13 3.5 'p 1 I -
.CA I I 3.4 LEGEND 1-4 3.3 3.2 3.'
I _I I l CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
'CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE
.d 2.' OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (25,2.81) (30,2.81) 1-4 4-0 2.1 E Cr
.5 USED IN DETERMINING MFLCPR CDw 2.1 r-0 i 2.46 3 a0. - 5- \ ~~~~~~~~~~~~~~.1.
C., . . '.
m
-n
-I, m
-4 A . B I 1(100,2.20) 2.2 - 4 -* 4. I~~~~~~~~~~~~~~~r%-----
I' (38.5,2.20) L I I
'-a 1-ai 2.1 *1 1. 4 4 *I Is -
I.-
2.0- .4PERENCE: T.S. 3.4.1 anI 3.2.21.. -t p t i NJ CA) 1.9 I I
~~~~~~~~~~~~~~~~~~~~~~~~. .1. I I 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
I:.0 bvl MCPR OPERATING LIMIT VERSUS CORE POWER m.N 1.z EOC.RPT AND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC) *o CD -h L
FIGURE 8.2-3
0 (i C tn SSES UNIT I CYCLE 13 V) 3.5 I . .
C" LEGEND 3.4 4 1 4 I ._I
'-4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.3 INSERTION TIME
- - 3.2 :- . ClURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME K-
_(25,3.07 IIJ I I . I II 3.1 _II I I I 3.0 T4,2.9 E
9 9 I I
I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
[ -u i 2.8 \_________
\__.__=__= USED IN DETERMINING MFLCPRJ= -u I-,
c CO, 0u
- 2.7 a.
0 -
a 2.6 0.
2 2.5 m
n 2.4
-n C-4
'-4 2.3 * ^at (40,2. 3J0) m A I B I -
2.2 I I (100,2.20)
P1 I~ I
~~~~~~~~
(54.6,2.20)
I1 I
I-2.1 .I __ __ __ __
2.0
REFERENCE:
T.S5 34.1, 3.7.6, and '3.2.
CD) 1.9 _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _
20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER .w 0.
MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE 0) -&
SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4
Cj. (C., K,.
SSES UNIT I CYCLE 13
(/1 3.5 I I I I m 3.4 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.3 INSERTION TIME r-, 3.2 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.1 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE
._________ '_________ OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
._ 2.9 E (25.2.81) (30,2.81)
- 3
,a, 2.8 . \ l ~~~~~~~~~~USED INIDETERMINING MFLCPR (D I-c
.0u C.) 2.7 0
M 2.6 0.
2 2.5 m
-n, 2.4 m
C-,)
2.3 m
2.2 \ . ~ ~~~~~~~A B (100,2.20) m (41.3,2.20) 1I-h 2.1 , .1 . i I-hj
.-4 I-'
2.0
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2 CA) 1.9 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER I to EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE
PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 33 of 36 9.0 POWER / FLOW MAP I
..... ...... .. , 7, 9.1 Technical Specification Reference I Technical Specification 3.4.1 I 9.2 Description' I Monitor reactor conditions to maintain THERMAL POWER / core flow outside of l Stability Regions I and 11of the Power / Flow map, Figure 9.1. I SUSQUEHANNA UNIT 1 TRM/3.2-34 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 *PL-NF-02-001 Rev. 2 Page 34 of 36 120 120
Purpose:
.J-.-L- r -r POWER I FLOW MAP 110 Iniffal / Daba: / -100%R APRM Rod ltod~ne Blockc-- F ~ j.* ^ ~ _ tR110 STBILITYpREGIONI _I r I REr RICTED REGION 100 IMMEDIATE SCRAM REQUIRED
- l r, 100
. RAWEON-17GO2 ,-i STABILITY REGION 11 -I-IMMEDIATELY EXIT REGION ,
.L*,AWON-178-r I r02
-r r r 90 aIu RESTRICTED REGION (As defined In Attachment G to NM -,r y,
- -LI 1 1 -rrC i -
I I*
L..1 II I
Yo. . .. . . .
I I I5r- I NDAP-OA4133)
. ., i l . ,t_ . . _ 113 11 N ' jj .T-- I I I I I 11 I
-4 r.
80 .- T-,-r -n1-11r -I-Irr- 1r1 -L +/- .jI I~~~~~~~~
I I.
- 80
- L .I ss-l-rtslI- L I l l! I 1_ J _lL J _ l_ L~~~~~~
. J..1L .i.J..LL .J.. L L
.- .. , . ,L I I. I I T ~~I I I 1 1I I l1 -.
,, II - r. i-i- l lK ll lr Il
-Ta1 4.
.liiir I n-4 1-l-rr t- il-rr--l I r T . 11.1.
70 B . . . L!!_I_'
- 70 L. ll l I Il l I
. .J -:-L .- a _-L- -:-L J_'L I I-. -I-i-_:
4 -l-,
- I1I-4 i -h IaI I
- ,;,0 - ir
_ L +/- .1 l tff.rII I a
- Ilj-Il 11 bllJ- *T -I t:- .. _1_ r C.1- - IT 1 _ rs ai .J L-I II I I I I I I I I I il; . I l I 60 . -I- L. _L t I 1 .... . I .\ . ..
- 60 0 -1J.. L .. L L J L 0.
. --,~-r 4 -- r n--r_ li ra 50 a t App~~ro x a a. .a. T i *1 - so i all I r Circu lii
.~~~~~~L - L.. - .l ,1Z L I-S. 4 J u u l Iii:.,, -,- .. L _IL L : 1 40 - 40 ill~ ~ ~ ~ ~ ~~~J t J L J-I
. t-lll t-ill ,I__ lii 1111
~~~~~~~~.._J _ L-_1L A _IL L.tlI 30 I I I I. l l II I I § I ;I I / I - I - 30 A& p. x II I t I I ; I I I I _r
. ~ll _ J l J -L atl_L. tl ILLJ__k
. L J J..
,-L J ii lF
!-claeSc~
. t J L .J...t...L L ..j L . . 1LL i .!
20 - 20
.-T n-11 AI- o I l-r
--.- rT -rr
. I
- 111 r * * * *r *
- I -r I *
. _1 t 1It ¢-8_LL, *IX .
ltlt '! lilt L,,L Naur',ar~lai J.,. . -I,-
M_
10 - 10 0 I
- w
- l I ~~~~~~~
0 10 20 30 40 S0 60 70 80 90 100 110 Total Core Flow (Mlbm/hr)
Figure 9.1 Power / Flow Map SUSQUEHANNA UNIT 1 TRM/3.2-35 EFFECTIVE DATE 11/01/2003
PPL Rev. . PL-NF-02-001 Rev.2 Page 35 of 36
10.0 REFERENCES
10.1 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-NF-90-001-A, "Application of Reactor Analysis Methods for BWR Design and Analysis," July 1992.
- 2. 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.
- 3. 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.
- 4. XN-NF-80-19(A), Volume 1, and Volume 1 Supplements I 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.
- 5. ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors," November 1990...
- 6. ANF-1125(P)(A) and ANF-1125(P)(A), Supplement 1, "ANFB Critical Power Correlation," April 1990.
- 7. NEDC-32071P-, "SAFER/GESTR-LOCA Loss of Coolant Accident Analysis,"
GE Nuclear Energy, May 1992.
- 8. NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30,1993).
- 9. 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.
- 10. PL-NF-94-005-P-A, "Technical Basis for SPC 9x9-2 Extended Fuel Exposure at Susquehanna SES," January 1995.
- 11. 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.
SUSQUEHANNA UNIT 1 TRM/3.2-36 EFFECTIVE DATE 11/01/2003
PPL Rev.1 - PL-NF-02-001 Rev. 2 Page 36 of 36
- 12. ANF-89-98(P)(A) Revision 1 and Revision 1 Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs,"Advanced NuclearFuels 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-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," September 1982.
- 15. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," January 1987.
- 16. XN-NF-79-71(P)(A) Revision 2, Supplements 1, 2, and 3, "Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.
- 17. EMF-1997(P)(A) Revision 0, "ANFB-10 Critical Power Correlation,"
July 1998, and EMF-1997(P)(A) Supplement 1 Revision 0, "ANFB-10 Critical Power Correlation: High Local Peaking Results," July 1998.
- 18. PL-NF-90-001, Supplement 3-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Application Enhancements," September 1999.
- 19. Caldon, Inc.,.'TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM'TM System," Engineering Report - 80P, March 1997.
- 20. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM~' or LEFM CheckPlusTm System," Revision 0, Engineering Report ER-160P, May 2000.
- 21. EMF-85-74(P), URODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements I and 2, February 1998.
- 22. EMF-CC-074(P)(A), Volume 4, Revision 0, uBWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2," November 1999.
. SUSQUEHANNA UNIT I TRM/3.2-37 EFFECTIVE DATE 11/01/2003