ML041320455
| ML041320455 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/05/2004 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML041320455 (43) | |
Text
May. 05, 2004 Page I of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004-20204 USER INFORMATION: e Name: CH*R M EMPL#:028401 CA#:0363 Address: NU Phone#: 2 TRANSMI AL INFORMATION:
TO: 05/05/2004 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:
TRM1 - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 02/23/2004 ADD MANUAL TABLE OF CONTENTS DATE: 05/04/2004 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT 3.2.1 REMOVE: REV:2 ADD: REV: 3 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT LOES REMOVE: REV:6 ADD: REV: 7 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 UST OFEFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date TOC TABLE OF CONTENTS 01/21/2004 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 08/31/1998 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 03129/2000 Page TRM /2.0-9 09/04/2002 Pages TRM / 2.0-10 and TRM / 2.0-11 04/02/1999 Page TRM /2.0-12 *10/22/2003 Page TRM 12.0-13 06/16/2000 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRI 04/08/1999
,:", lI . l,'-,
MINI 110plallp k ;,
3.1 REACTIVITY CONTR L SY Ms Pages 3.1-1 thro 08/31/1998 Pages TRM / 317 alIPRM / 3.1-8 06/05/2002 PagesgTR ind TRM / 3.1-9a 02/18/1999 Page TRMli/31-W,10" 02/18/1999 3.2 CORE QERaFgtiG LIMITS REPORT 07/07/1999 mPag TRM / 3.2-2 through TRM / 3.2-37 03/15/2004 3.3 STRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM /3.3-4 11/28/2000 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 13.3-13 and TRM / 3.3-14 12/14/1998 Page TRM /3.3-15 10/22/2003 Page TRM / 3.3-16 06127/2001 Pages TRM / 3.3-17 and TRM / 3.3-18 06/14/2002 Pages TRM / 3.3-19 through TRM / 3.3-21 10/22/2003 SUSQUEHANNA - UNIT 1 TRM/LOES-1 EFFECTIVE DATE 03/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 LIST OF-EFFECTIVE SEC77ONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page 3.3-22 08/31/1998 Pages TRM 13.3-23 through TRM / 3.3-25 05/16/2003 Page TRM / 3.3-26 10/2212003 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 - 08/31/1998 Page TRM 1 3.5-4 04/1712000 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 I 3.6-4 01/0712002 Page 3.6-5 08/31/1998 Pages TRM / 3.6-6 through TRM 13.6-8 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 08102/1999 Page TRM I 3.7-11 12/29/1999 Pages TRM I 3.7-12 through TRM I 3.7-27 08102/1999 Pages TRM /3.7-28 through TRM / 3.7-32 11/16/2001 Page TRM / 3.7-33 01109/2004 Page TRM 13.7-34 11/16/2001 Page TRM / 3.7-34a 10/05/2002 Pages TRM I 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 08/1112000 Pages 3.7-42 and 3.7-43 08131/1998 Pages 3.7-44 through 3.7-48 10113/1998 Page TRM 13.7-49 03/08/2003 Pages TRM /3.7-50 and TRM 13.7-51 03/09/2001 Pages TRM 13.7-52 and TRM 13.7-53 04/15/2003 Page TRM /3.7-54 07/29/1999 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 / 3.84 12131/2002 Pages TRM /3.8-5 and TRM / 3.8-6 04/0212002 Pages TRM I 3.8-7 through TRM / 3.8-9 08/31/1998 SUSQUEHANNA - UNIT 1 TRM I LOES-2 EFFECTIVE DATE 03/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 UST OF-EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM / 3.8-10 07/19/2001 Page TRM / 3.8-11 04/02/2002 Page TRM / 3.8-11 a 04/0212002 Pages 3.8-12 through 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM / 3.8-17 04/02/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 Page 3.8-20 08/31/1998 Pages TRM 13.8-21 through TRM 13.8-23 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 06105/2002 Page TRM / 3.10-7 04/07/2000 Corrected Page TRM / 3.10-8 04/17/2002 3.11 RADIOACTIVE EFFLUENTS' Pages 3.11 -1 through 3.11-12 08/31/1998 Pages 3.11-13 through 3.11-16 09/01/1998 Pages 3.11-17 and 3.11-18 08/31/1998 Page TRM 13.11-19 01/21/2004 Pages 3.11-20 and 3;11-21 08/31/1998 Pages TRM /3.11-22 through TRM / 3.11-24 04/02/2002 Page 3.11-25 09/01/1998 Pages TRM /3.11-26 through TRM /3.11-32 01/21/2004 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 02/05/1999 4.0 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/1998 SUSQUEHANNA - UNIT 1 TRM I LOES-3 EFFECTIVE DATE 03/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 LIST 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 I B 3.0-15 03/15/2002 B3.1 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 07/13/1999 Page B 3.1-4 08/31/1998 Pages TRM I B 3.1-5 through TRM / B 3.1-7 07/13/1999 Page TRM / B 3.1-8 02/18/1999 B3.2 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 I B 3.3-4 through TRM / B 3.3-6 03/21/2003 Pages TRM / B 3.3-7 through TRM / B 3.3-9 03/30/2001 Pages B 3.3-1-0 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 / B 3.3-16 10/22/2003 Page TRM / B 3.3-17 04/07/2000 Pages TRM / B3.3-18 and TRM / B 3.3-19 05/16/2003 Page TRM I B 3.3-20 10/22/2003 PageTRM/B3.3-21 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 E Pages B 3.5-1 through B 3.5-5 08/3111998 B3.6 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 I LOES-4 EFFECTIVE DATE 03/15/2004
I i
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 UST OFEFFECTWESECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM / B 3.6-6 through TRM / B 3.6-11 12131/2002 B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 0813111998 Pages TRM I B 3.7-3 through TRM / B 3.7-7 08102/1999 Page TRM I B 3.7-7a 08/02/1999 Pages TRM / B 3.7-8 through TRM I B 3.7-10 08/02/1999 Page TRM / B 3.7-1Oa 08/02/1999 Pages TRM / B 3.7-11 and TRM / B 3.7-11 a 08/0211999 Pages TRM I B 3.7-12 through TRM / B3.7-14 08/02/1999 Page TRM I B 3.7-14a 0810211999 Page TRM I B 3.7-14b 01109/2004 Pages TRM / B 3.7-15 and TRM I B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08131/1998 Page TRMIB 3.7-21 through TRMIB 3.7-21a 05/11/2001 Pages TRMIB 3.7-22 and TRMIB 3.7-23 04/07/2000 Pages B 3.7-24 through B 3.7-30 08/31/1998 Pages TRM I B 3.7-31 and TRM I B 3.7-32 03/0912001 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 TRM I B 3.8-2 04/02/2002 Page TRM / B3.8-2a 04/02/002 PageTRM/B3.8-3 04102/2002 Page TRM / B 3.8-3a 04/0212002 Page TRM / B 3.8-4 04/02/2002 Page TRM / B 3.8-4a 04/02/2002 Page TRM / B 3.8-5 08131/1998 Pages TRM I 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 08131/1998 B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 08131/1998 Page TRM / B 3.10-3 03/08/2003 Pages TRM / B 3.10-4 and TRM / B 3.10-5 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 PageTRM/B3.11-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.11-1 1a 04107/2000 SUSQ.UERANNA - UNIT I TRM I LOES-5 EFFECTIVE DATE 03/15/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 7 UST OF EFFECTIVE SECT7ONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 Page TRM /B 3.11-14 11/01/1999 Page TRM / B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08/30/1998 Page TRM /B 3.11-20 04/0212002 Page TRM / B 3.11-20a 04/02/2002 Page TRM / B 3.11-21 04/02/2002 Page TRM / B 3.11-22 09126/2003 Page TRM / B 3.11-23 04/02/2002 Page TRM / B 3.11-23a 04/02/2002 Pages TRM / B 3.11-24 and TRM /B 3.11-25 01/21/2004 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 Adept TRM1 text LOES 3/9/04 SUSQUEHANNA - UNIT 1 TRM I LOES-6 EFFECTIVE DATE 03/1512004
Core Operating Limits Report (COLR)
PPL Rev. 3 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. 3 PL-NF-04-001 Rev. 0 Page 1 of 36 Susquehanna SES Unit 1 Cycle 14 -
CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering March 2004 pp SUSOUEHANNA UNIT 1 TRM/3.2-2 EFFECTIVE DATE 03/15/2004
PL .
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 2 of 36 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. Affected No. I Sections DescriptionlPurpose of Revision 0 ALL Issuance of this COLR is in support of Unit 1 Cycle 14 operation.
FORM NFP-QA-008-2, Rev. I SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 3 of 36 SUSQUEHANNA STEAM ELECTRIC STATION Unit I Cycle 14 CORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
................................... 4 2.0 DEFINITIONS. .................................................................................... 5....................
3.0 SHUTDOWN 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 POWER I FLOW MAP ....................................................... 33
10.0 REFERENCES
............................................................................................................35 SUSQUEHANNA UNIT 1 TRM/3.2-4 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 4 of 36
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT (COLR) for Susquehanna Unit 1 Cycle 14 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 I TRM/3.2-5 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 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 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 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 poison bumup, 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, UR". 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.
SUSQUEHANNA UNIT 1 TRM/3.2-7 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 7 of 36 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGRi 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUM'-10fuel 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 03/15/2004
( ( (C SSES UNIT I CYCLE 14 JCA 16
, ,.., *.. .... .. .. . ..... . .. .. .. . .S.S.S.*.*...*.*.* . . . . . . .. . .. .
- 14 I-
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5-5's 4 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU) TUT~
co<'
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS (D Z AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION -h
,ATRIUM -10 FUEL FIGURE 4.2-1
PPL Rev. 3 PL-NF-04-001 Rev. 0 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 (ATRIUM'-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 / EOC-RPT Operable Figure 5.2 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 Averaae 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 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 10 of 36 EOC-RPT and Main Turbine Bypass
-Operable - -
SUSQUEHANNA UNIT 1 TRM/3.2-11 EFFECTIVE DATE 03/15/2004
( (C SSES UNIT I CYCLE 14
.o 2.3 I I . I I rrn LEGEND I:
Z 2.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
-H 2.1 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.0
. SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES Id
- IARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-- E9 1.9 CD. USED IN DETERMINING MFLCPR
-a i: I 1.8 I-1 0"
<I "L1.7 1.6 (30,1.52)
-n P
'1 1.5 (39.9,1.47) 1 4. 4 1 4. 4 I W a. a a - - - 0 _ _ W a W . .-............ _ al (108,1.47) rn CD 1.4 I _I __ __
........ I .. _ .........
., - I I . I .-
B
- I _ (108,1.39)
REFERENCE:
.T.S. 3.2.21 rn I * (66,1.39) w 1.3 I
- I 4. 4. I 4. 4 30 40 50 60 70 80 90 100 110 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
(- (
Cr) c/1 SSES UNIT I CYCLE 14 3.0 LEGEND 2.9 I.
2-2.8 :__TI _ I_ 1CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME H: 2.7 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.6 2.5 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE-PER SR 3.7.6.1 AND 3.7.6.2 W 2.4 I (25,2.30) T -
-c
.a 2.3 lUSED IN DETERMINING MFLCPR o
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'- A M.
-4 4.
82,1.46) 1.5 -1 REFERENC E: T.S. 3.2.2 I-.. I 4. 4 I I - - - - - . - -_ . a0 (100,1.46)
-4 1.4 1i i i (100,1.39) rn II(79,1.39)
Co 1.3 . . _ .
2C I 30 40 50 60 70 80 90 100 rNo Core Power (% RATED) T 4:. z
-n MCPR OPERATING LIMIT VERSUS CORE POWER 0 EOC-RPT AND MAIN TURBINE BYPASS OPERABLE --
0 TWO LOOP OPERATION (BOC TO EOC) 0 FIGURE 5.2-2
PPL Rev. 3 PL-NF-04-001 Rev. 0 .
Page 13 of 36 Main Turbine Bypass Inoperable / EOC-RPT Operable SUSQUEHANNA UNI-T 1 TRM/3.2-14 EFFECTIVE IDATE 03/15/2004
C (
SSES UNIT I CYCLE 14 ci) 2.3 0
2.2 1 4i ul *A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME
-4i 2.1 I Ii - 11li EB: REALISTIC AVERAGE SCRAM INSERTION TIME I-.
2.0 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
-i 1.9 I I I I 03
- 1. USED IN DETERMINING MFLCPR r-I-.
W-- 0. -1 I 0
i 1. (30,1.70)
<a>1.7- i I A -4 * - B l (108,1.70) 1.6 T11
-Ti 1.5 C-4 . . .I
-4 P1- 1.4 . REFERENE: T.S. 3.7.6 a 1.3 , I ., .
30 40 50 60 70 80 90 100 110 N\) Xu X Total Core Flow (MLB/HR) 0, m r-(D *Z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW .t, 0 n MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE O 0 TWO LOOP OPERATION (BOC TO EOC) 8?
FIGURE 5.2-3
( ( C SSES UNIT I CYCLE 14
.CD- 3.0 c~
m LEGEND c 2.9 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM I5 2.8 f__ I I C=
INSERTION TIME i-i 2.7 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.6 __ __
(25,2.49) 2.5 2.4 . J I_ I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 H 9 .e
.3i2.3 N I I I I USED IN DETERMINING MFLCPR c .- 2.2 T r-i 2.1:
ID 0*
= 2.0 c 1.9 (40,1.94) 1.8 m l ~B.
m 1.7 (100,1.70)
-Il (65.5,1.70)
H 1.6 A-4 m 1.5
REFERENCE:
T.S. 6 and 3.2.
H cW 1.4 1.3
._ _ _ _ __ _ _ _ I _ _ __ _ _ _ I__ _ __ _ _'d__
20 30 40 50 60 70 80 90 100 4:- Core Power (% RATED)
(01 MCPR OPERATING LIMIT VERSUS CORE POWER -h, 0 7 MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE C,, 0 TWO LOOP OPERATION (BOC to EOC) 0) -. %
FIGURE 5.2-4
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 16 of 36 EOC-RPT inoperable /
Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2 17 EFFECTIVE DATE 03/15/2004
C ( (
CAI SSES UNIT I CYCLE 14 CA 2.3 I I I D
rT.
P1 2.2 I 4 II.~4, ICURVF A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME I-
-4i 2.1 1 4 4.l B: REALISTIC AVERAGE SCRAM INSERTION TIME I.j I I I -. - - I 2.0 I 4. 4 4-SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-- E1.9- I I I
. USED IN DETERMINING MFLCPR F
co rN) 1.8-
-o
-Q I-4 6 4 4. I I
- o. 0. CD W,
g 1.7-1.6 - 4 4 I 4 4 1 I rn (30,1.52)
- I -1 (108,1.51) 1.5
-n (37,1.51) m
-4 Co 1.4 1.3
' ____I
REFERENCE:
T.S. 3.3.4.1 and 3.2.21 CIO i
01 30 40 50 60 70 80 90 100 110 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.
( K (
SSES UNIT 1 CYCLE 14 3.0 I I I I 2.9 2.8 I _ _ _ I _ _
l
_ I l
_ I _
1 II LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME u- 2.7 1* I-I.-.
CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.6 t I-2.5 'I 4 4-SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
- 4. 4 I- ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 E 2.4 1:' (25,2.30) a 2.3 I.
- 4. .4 1 -1 cm USED IN DETERMINING MFLCPR
.CA) 22 4- II . _ _ _ _ _ __ _ _ _ _ _ I .I__ I_
&2.2 N (30,2.13) k 4 4. 4 I* 4. 4 4. I
- a. 2.0 U
2 1.9 1.8 m 1.7 (40,1.78) __ __ __ _
rn m
C-,)
1.6 B
-q 1.5 -
REFERENCE:
T.S. 3.3.4.1 and 3.2.2 (100,1.51)
-4 1.4 1.3
_ _ _ _ I _ . _ _ 74,1.51 ) _ _)_
20 30 40 50 60 70 80 90 100 N) Core Power (% RATED)
(a <
OD O MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE o-,)
o 0 n hF 0 TWO LOOP OPERATION (BOC to EOC) c 0 FIGURE 5.2-6
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 19 of 36 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 SUSQUEHANNA UNIT 1 TRM/3 .2- 20 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 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 Operable The LHGR for ATRIUMTm-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.
Main Turbine BvDass Inoperable The LHGR for ATRIUMT'-10fuel 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 03/15/2004
16 SSES UNIT I CYCLE 14 gr16 .
m ~SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES AE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1400,13.4 : 15000,13.4 ... ... .....
REFERENCE:
T.S. 3.2.3
. ...... ......... SDI DETEMININGFDRX 12.
E CA) (D
.. . .. . . . . . . . ... . . .. .G 8 ........ a. a . . . . a a a a3........... . . .................... ....................... ......
- :. .... .: : : ~ : :: :67000,7.14
.... a ,
.. . .a. a a .. . . . . .. * . . ... ... ...... . . .. a.a.....a......a...
a . . . . . . . . . . ...
-- A I . . a a ... .
CDa a a a a a a a a a a a , a a a 1-.- 4 . . . . . . . a a..
0 10000 20000 30000 40000 50000 60000 70000 CpAverage Planar Exposure (MWDIMTU) Wcm r ci) (a (D
<' Z LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE 0 7 MAIN TURBINE BYPASS OPERABLE ATRIUMTm410 FUEL FIGURE 6.2-1
( I (
16 SSES UNIT 1 CYCLE 14 16 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS z ....... . VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 c 4 .............
z ', 14 ' ' a 'l .' a; a,
REFERENCE:
T.S. 3.2.3 and3.7.6
. . . a
.. @ @ @ ! I @ . ". :.. ... *... .. I @ @'.
e : ' : :: : : : : :: :: :USED IN DETERMINING FDLRX 0.0,12.0 : ' 15000,12.0
- a a a ' : : :,.
o12 -.........
i t C, ~~~~~~~.. @j..
4 jjt 2,'2......j.@,'2,
,i . § § § @ @ @ s * -a CA) = . . ., .. ., ,..
. . . . . . . . T 10 0
. . .. * . . , , , a . . . . * * ,* * . a
........ ....... ....... . ................... , .......... .. .... . ................ CAa (U(
a
......... a . a.. ..
... ... .. a.. ... ... ... ... .... .. .a .. . .......
. I . . . . . . . . .I ...........
6z,. . . . .a . . .a. . X s l a l l
- l } w @ t @ b @ "e a , a ,. . . . . . * *. . .a a . . * .
o . a a ... * * **I II S....* ** . * ._ ...... , .
- .:67000,6.39 C* 4 .* *..._ . .
- 0 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU)
C=) z r'3 Q71 LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE K) 0 MAIN TURBINE BYPASS INOPERABLE
.ATRIU 10 FUEL . ..
FIGURE 6.2-2
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 23 of 36 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.
SUSQUEHANNA UNIT 1 TRM4/3.2-24 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 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' Sma < (0.58W + 50%) T SRR * (0.58W + 53%) T I
Table 7.2-2 APRM Setpoint for Single Loop Operation Trip Setpoint Allowable Value l IS< (0.58W + 54%) T S* (0.58W + 57%) T1 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 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 ATRIUM'T~-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/3.2-25 EFFECTIVE DATE 03/15/2004
( ! C' GU) SSES UNIT I CYCLE 14 16 Y-*
RFERENCE: T.S. 3.2.:4 14
. a. . .. . .a .... . .
.E
.:i? 1 2
--i
.... .a. . .. a. .a .. . . a S
i\) CL10 . . .. . . . . . . .: :67000.8.0.
I,1L
, C C C .......... C C .. ...... S P1
-n
-I . a a ~ ~ ~a ~ ~ ~~~~~~
a ~ *.
a a., a a a - a . * ., , . . . . . .
m 6 SC C S C ~~ .. ..... .... . .. . ...... .. ... . .
C-)
I-a- , . . . . I , . .a.a. . . .a. . . .a . . . .a. . . .a. . . . .. . . .
01-C) 4 0 10000 20000 30000 40000 50000 60000 70000 c"
Average Planar Exposure (MWD/MTU) 0u00 LINEAR HEAT GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE ATRIUM' -10 FUEL a~ 0 0
FIGURE 7.2-1 08 c
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 26 of 36 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 ATRIUM'-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 (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 I 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 I TRM/3.2-27 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 27 of 36 Averaae Power Ranae Monitor (APRM) Gain And Setpoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined in Section 7.0.
SUSQUEHANNA UNIT 1 TRM/3.2-28 EFFECTIVE DATE 03/15/2004
( (
cn, cn SSES UNIT I CYCLE 14 I16 XD
.... . . ...... .... . .. . . . .......... S *
- 14
- REFERENCE T.S. 3.4.1 and 3.2.1 1-H
-I.
. . . .... EDIN DETERMINING MAPRAT
................... S... .. .. . . . .
& 12 E .. . . . . ... .. .... S ... ~. . .. ...
- S
..... ... SSS*...........S r\3
~co . .. . .. . .
S.... . ... ... S ~ .... .. .. . . .. . . . . .. .. .
(U 0
=83K
- S . ... . .S . . S
. . ... S...S..* .. . . . . . .S .S S
& I..)
P 0 N)1 U!
S-m .. S.. .. S .. .... S ...... .. .. .. .. S ..S ..
- S C
- S .!67000,4.8S
-I,
-n C-)
-- I 6 P-1
-H CD 4
0 10000 20000 30000 40000 50000 60000 70000 N) Average Planar Exposure (MWDIMTU)
(O <
OD*
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE M07 SINGLE LOOP OPERATION UTM. co) 0 ATRIU 10 FUEL 0) -&
FIGURE 8.2-1
( (
ci C-,)
SSES UNIT 1 CYCLE 14 U1 2.6 .
I I I I --
D 2.5 I I I-ifh ICRVF A: MAXIMUM ALLOWABLE AVERAGE SCRAM I,
INSERTION TIME CD B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 I I I -T
'u 2.3 USED IN DETERMINING MFLCPR
.Z
-u CZ V 2.2 (30,2.19) 4.
I I' I -a
- 0. 9 A B (1'108,2.19) I-
- t.~
0 1(
O ,,
2 2.1 m 2.0 iN) 21 C!O
-i Cr) 1.9 REEECE: T.S. 3.4.1 and 3.2.2 rm
-I-T-n 1.8 30 40
_ _ _ _ I 50
_ _I__
60 70 80
_ I__
90 I
100 I 110 Total Core Flow (MLB/HR)
C (D
Z Z0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW to o SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2 _ 0
( C C CZ, U-)
SSES UNIT I CYCLE 14 Ln 3.5 I *I*
I I I I LEGEND 3.4 1 4 4 I- CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.3 INSERTION TIME I-.
3.2 I 4 4 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.1 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES am2.8 I I _. I _
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
_(25,2.76) USED IN DETERMINING MFLCPR ZF 0 2.8 -* 4. 4
._ -u I'
Co
,. c._
O .:
m 2.5 2.4 P1 2.3 n
-I, C, 2.2 \t l - A- B- (100,2.19)
A_
(38.9,2.19) . '. ,_._.
<r 2.1 Ri 2.0 NCE: T.S. 3.4.1 and 3.2.2 rC1
° 1.9 I-.
(' 20 30 40 50 60 70 80 90 100 Core Power (% RATED) N) 01 N) (0 $ 7 (D- Z o,nO7 MCPR OPERATING LIMIT VERSUS CORE POWER o o EOC-RPT AND MAIN TURBINE BYPASS OPERABLE o -0 SINGLE LOOP OPERATION (BOC to EOC) W, 0
- 0) -L FIGURE 8.2-3
( (
CI c_- SSES UNIT I CYCLE 14 Ur 3.5 LEGEND 3.4 2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3, 3.3 INSERTION TIME c_-
3.2 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.1 3.0 (25,2.99) ._. SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
- 2.9
._ _ _ uUSED IN DETERMINING MFLCPR 3 1 2.7
__ _ _ I_ I_ _ _ _ __ _ _ _ __ _ ___I_ I _ ___
-,0
,0 CA) (0,21 ,
is 2.6 0.
< 2.5 2.4 rn 2.3 (40,2.33)
C--) 2.2 (100,2.19)
-1i .-- A B --
'-4l
. (52,8,2.19) .
2.1 m 2.0 REFE ICE- T.S. 3.4. 1, 33.7.6, and 3 1.9 .I I I' . I.
CA) 20 30 40 50 60 70 80 90 100 C03
- Core Power (% RATED) 4:4
.00r MCPR OPERATING LIMIT VERSUS CORE POWER (0 0
?
1 C,
MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE SINGLE LOOP OPERATION (BOC to EOC) C.) 0
- 0) -
FIGURE 8.2-4
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 33 of 36 9.0 POWER I FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.4.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER I core flow outside of Stability Regions I and 11of the PowerI Flow map, Figure 9.1.
SUSQUEHANNA UNIT 1 TRM/3 .2- 34 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 34 of 36 120 120 110 110 100 100 90 90 go 80 70 70 0
0 60 60
- 0. T 50 5O I.-
40 - 40 30 30 T
20 20 l
10 10 0 0 0 10 20 30 40 - 50 60 70 80 . 90 100 110 Total Core Flow (Mlbm/hr)
Figure 9.1 Power I Flow Map SUSQUEHANNA UNIT 1 TRM/3.2-35 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 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. 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 AnaJysis," 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-80-19(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-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Light Company, December 1992 and NRC SER (November 30, 1993).
SUSQUEHANNA UNIT,1 TRM/3.2-36 EFFECTIVE DATE 03/15/2004
PPL Rev. 3 PL-NF-04-001 Rev. 0 Page 36 of 36
- 12. ANF-89-98(P)(A) Revision 1 and Revision I 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-1997(P)(A). Supplement 1 Revision 0, "ANFB-10 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 LEFM'Tm System," Engineering Report - 80P, March 1997.
- 17. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFMI'Tm or LEFM CheckPlusTm System," Revision 0, Engineering Report ER-160P, 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/Microbum-B2," Siemens Power Corporation, October 1999.
- 20. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2," November 1999.
SUSQUEHANNA UNIT 1 TRM/3.2-37 EFFECTIVE DATE 03/15/2004