ML040500317
| ML040500317 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/11/2004 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML040500317 (44) | |
Text
Feb. 11, 2004 Page 1
of 1
MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004-6578 USER NFORMATTON!
GE CH*
E M EMPL#:28401 CA#: 0363 Add CSA2 Krie#: 254 4
TRANSMITTAL INFORMATION:
TO:
02/11/2004 LOCATION;r"USNRC.7 i
PROM:
NUCLEAR RECORDS DOCUMENT CONTROL CENTER NUCSA-2)
'\\HE 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: 01/27/2004 ADD MANUAL TABLE OF CONTENTS DATE: 02/10/2004 CATEGORY: DOCUMENTS TYPE: TRM1 ID:
TEXT 3.2.1 REMOVE:
REV:1 ADD:
REV: 2 CATEGORY: DOCUMENTS TYPE: TRM1 ID:
TEXT LOES REMOVE:
REV:5 ADD:
REV: 6 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.
- K>
4ge\\
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 6 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
. Section Title Effective Date TABLE OF CONTENTS TOC 1.0 2.0 3.0 3.1 3.2 3.3 01/21/2004 USE AND APPLICATION Pages TRM /1.0-1 through TRM / 1.0-3 PLANT PROGRAMS Pages 2.0-1 through 2.0-2 Page TRM / 2.0-3 Page TRM / 2.0-4 Page TRM /2.0-5 Pages TRM / 2.0-6 and TRM I 2.0-7
/
Page TRM I 2.0-8 Page TRM /2.0-9 7
Pages TRM / 2.0-10 and TRM / 2.0-11
/.
Page TRM /2.0-12 Page TRM /2.0-13 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-2 Pages TRM / 3.0-3
.(!
Page TRM / 3.0-4 REACTIVITY CONTROL SYSTEMS; Pages 3.1-1 through 3.1i-6' Pages TRM / 3.1 -7'and TRM /3.1-8 Pages TRM /3.119 'and TRM / 3.1-9a Page TRM / 3.1-10',,
"V CORE OPERATING LIMITS REPORT Page TRM /3.2Ž1 "
Pages\\TRM 3.2-2 through TRM / 3.2-37 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 Page'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 and TRM / 3.3-14 Page 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 / 3.3-21 Page 3.3-22 10/04/2002 08/31/1998 08/01/2001 06/25/2002 04/02/1999 10/22/2003 03/29/2000 09/04/2002 04/02/1999 10/22/2003 06/16/2000 04/08/1999 03/15/2002 04/08/1999 08/31/1998 06/05/2002 02/18/1999 02/18/1999 07/07/1999 01/27/2004 07/16/1999 11/28/2000 08/31/1998.
12/17/1998 12/17/1998 03/30/2001 12/14/1998 10/22/2003 06/27/2001 06/14/2002 10/22/2003 08/31/1998 SUSQUEHANNA - UNIT
.TRM/LOES-1 EFFECTIVE DATE 01/27/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 6 LISTOFEFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title
-Effective Date Pages TRM / 3.3-23 through TRM / 3.3-25 Page TRM / 3.3-26 REACTOR COOLANT SYSTEM' Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-13 05/16/2003 10/22/2003 3.4 10/23/1998 08/31/1998 3.5 3.6 3.7 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 3.6-3 Page TRM / 3.6-4 Page 3.6-5 Pages TRM / 3.6-6 through TRM / 3.6-8 PLANT SYSTEMS Pages 3.7-1 through 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 Page TRM / 3.7-34 Page TRM / 3.7-34a Pages TRM / 3.7-35 through TRM / 3.7-37 Pages 3.7-38 through 3.7-40 Pages TRM / 3.7-41 and TRM / 3.7-41 a Pages 3.7-42 and 3.7-43 Pages 3.7-44 through 3.7-48 Page TRM / 3.7-49 Pages TRM / 3.7-50 and TRM / 3.7-51 Pages TRM / 3.7-52 and TRM / 3.7-53 Page TRM / 3.7-54 08/31/1998 04/17/2000 08/31/1998 08/31/1998 01/07/2002 08/31/1998 12/31/2002 08/31/1998 08/02/1999 12/29/1999 08/02/1999 11/16/2001 01/09/2004 11/16/2001 10/05/2002 02/01/1999 08/31/1998 08/11/2000 08/31/1998 10/13/1998 03/08/2003 03/09/2001 04/15/2003 07/29/1999 3.8 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 / 3.8-9
-Page TRM /3.8-10 Page TRM / 3.8-11 Page TRM / 3.8-11 a 04/02/2002 08/31/1998 12/31/2002 04/02/2002 08/31/1 998 07/19/2001 04/02/2002 04/02/2002 SUSQUEHANNA - UNIT 1
'TRM / LOES-2 SUEFFECTIVE DATE 01/27/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 6 LISTOFEFFECTIVESEC7ONS(TECHNICAL REQUIREMENTS MANUAL)
Section Title Pages 3.8-12 through 3.8-14 Pages TRM / 3.8-15 through TRM l 3.8-17 Page 3.8-18 Page TRM / 3.8-19 Page 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25.
Effective Date 08/31/1998
-04/02/2002 08/31/1998 04/02/2002 08/31/1998 06/06/1999 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 Page TRM / 3.10-5 Page TRM / 3.10-6 Page TRM / 3.10-7 08/31/1998
- 03/08/2003 06/05/2002 04/07/2000 Corrected 04/17/2002 Page TRM / 3.10-8 3.11 RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-12 Pages 3.11-13 through 3.11-16 Pages 3.11-17 and 3.11-18 Page TRM / 3.11-19 Pages 3.11-20 and 3.11-21 Pages TRM / 3.11-22 through TRM / 3.11-24 Page 3.11-25 Pages TRM /3.11 -26 through TRM / 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 08/31/1998 09/01/1998 08/31/1998 01/21/2004 08/31/1998 04/02/2002 09/01/1998 01/21/2004 08/31/1998 3.12 4.0 02/05/1999 08/31/1998 SUSQUEHANNA - UNIT 1 TRM / LOES-3 EFFECTIVE DATE 01/27/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 6 LIST OFEFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section B 3.0 B 3.1 B 3.2 Title APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM / B 3.0-11 through TRM 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 CORE OPERATING LIMITS BASES Page B 3.2-1 Effective Date 08/31/1998 03/15/2002 07/13/1999 08/31/1998 07/13/1999 02/18/1999 08/31/1998 B 3.3 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 Pages TRM / B 3.3-4 through TRM / B 3.3-6 Pages TRM / B 3.3-7 through TRM / B 3.3-9 Pages B 3.3-10 through B 3.3-12 Page TRM/ B 3.3-13 Page TRM/ B 3.3-14 Page TRM / B 3.3-14a Page TRM / B 3.3-14b Pages TRM / B 3.3-15 and TRM I B 3.3-16 Page TRM / B 3.3-17 Pages TRM / B3.3-18 and TRM I B 3.3-19 Page TRM / B 3.3-20 Page TRM / B 3.3-21 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 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 CONTAINMENT BASES Page TRM I B 3.6-1 Page TRM I B 3.6-2 Page B 3.6-3 Page TRM / B 3.6-4' Page TRM / B 3.6-5 Pages TRM / B 3.6-6 through TRM / B 3.6-11 04/07/2000 08/31/1998 12/29/2000 03/21/2003 03/30/2001 08/31/1998 10/22/2003 06/25/2002
'06/14/2002.
06/14/2002 10/22/2003 04/07/2000 05/16/2003 10/22/2003 05/16/2003 B 3.4 B 3.5 08/31/1998 10/15/1999 08/31/1998 08/31/1998 B 3.6 07/26/2001 02/01/1999 08/31/1998 09/23/1999 01/07/2002 12/31/2002 SUSQUEHANNA - UNIT
TRM / LOES-4 EFFECTIVE DATE 01/27/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 6 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUI REMENTS MANUAL)
Section Title
- ,.,1, -,
B 3.7 B 3.8 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 / B 3.7-10 Page TRM / B 3.7-1 Oa Pages TRM / B 3.7-11. and TRM I B 3.7-11 a Pages TRM I B 3.7-12 through TRM I B 3.7-14 Page TRM / B 3.7-14a Page TRM / B 3.7-14b Pages TRM / B 3.7-15 and TRM B 3.7-16 Pages B 3.7-17 through B 3.7-20 Page TRM/B 3.7-21 through TRM/B 3.7-21a Pages TRM/B 3.7-22 and TRMIB 3.7-23 Pages B 3.7-24 through B 3.7-30 Pages TRM I B 3.7-31 and TRM I B 3.7-32 Page TRM I B 3.7-33 Pages TRM I B 3.7-34 and TRM I B 3.7-35 ELECTRICAL POWER BASES Pages TRM I B 3.8-1 and TRM I B 3.8-2 Page TRM / B 3.8-2a Page TRM / B 3.8-3 Page TRM / B 3.8-3a Page TRM I B 3.8-4 Page TRM / B 3.8-4a Page TRM / B 3.8-5 Pages TRM / B 3.8-6 through TRM I B 3.8-17 Effective Date 08/31/1998 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 01/09/2004 02/01/1999 08/31/1998 05/11/2001 04/07/2000 08/31/1998 03/09/2001 04/15/2003 07/05/2000 04/02/2002 04/02/2002 04/02/2002 04/02/2002 04/02/2002 04/02/2002 08/31/1998 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 Page TRM / B 3.10 Pages TRM / B 3.10-4 and TRM / B 3.10-5 Pages TRM I B 3.10-6 and TRM I B 3.10-7 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 PageTRMIB3.11-10 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 08/31/1998 03/08/2003 08/23/1999 04/17/2002 08/30/1998 02/01/1999 04/07/2000 02/01/1999
- 11/01/1999 02/01/1999 08/30/1998 SUSQUEHANNA - UNIT TRM / LOES-5 EFFECTIVE DATE 01/27/2004
SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 6 LISTOFEFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)
Section Title Effective Date Page TRM B 3.11-20 Page TRM B 3.11-20a Page TRM B 3.11-21 Page TRM B 3.11-22 Page TRM / B 3.11-23 Page TRM / B 3.11 -23a Pages TRM B 3.11-24 and TRM /B 3.11-25 Pages B 3.11-26 through B 3.11-35 Page 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 09/26/2003 04/02/2002 04/02/2002 01/21/2004 08/30/1998 02/12/1999 02/05/1999 Adept TRM1 text LOES SUSQUEHANNA - UNIT 1
--- TRM / LOES-6 EFFECTIVE DATE 01/27/2004
Core Operating Limits Report (COLR)
PPL Rev. 2 3.2.1 3.2 Core Operating Limits Report (OLR) 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.'
A' 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 N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.
SUSQUEHANNA - UNIT
-TRM 32-1 EFFECTIVE DATE 7/07/1999
.-1 I
X PPL Rev. 2 -
PL-NF-02-001 I IIRev.3 Page 1 of 36
(,
)
Susquehanna SES Unit 1 Cycle 13 CORE OPERA-TING LIMITS REPORT Nuclear Fuels
- Engineering J
January 2004
%I
- I I~~,
-- TRM/3.2-2 SUSQUEHANNA UNIT 1 EFFECTIVE DATE 1/27/2004
PPL Rev. 2 PL-NF-02-001 Rev. 3 Page 2 of 36 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.
Affected No.
Sections Description/Purpose of Revision 0
1 2
'3 ALL 5.0 6.0 8.0 TOC 1.0 9.0 10.0 9.0 Issuance of this COLR is in support of Unit 1 Cycle 13 operation.
This revision adds a text box to all appropriate plots. This text box indicates that for all bypass operable cases, four bypass valves are assumed 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.
This revision adds the Power! Flow map to the COLR. Section 1.0 was revised to include the stability regions as part of the COLR. The Power /
Flow map was added as Section 9.0. The Reference section was renumbered as Section 10.0 and a stability reference added.
This revision is administrative in nature since the Power / Flow map is already included in NDAP-QA-0338.
This revision replaces the Power! Flow map contained in Section 9.0.
I I
- FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 JRM/3.2-3 EFFECTIVE DATE 1/27/2004
-,~~
PPL Rev. 2 PL-NF-02-001 Rev. 3 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 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 2 23 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.26 9.0 POWER / FLOW MAP...............
33
10.0 REFERENCES
.35 SQ N
UE SUSQUEHANNA UNIT 1 TRM/3.2-4 EFFECTIVE DATE 1/27/2004-
PPL Rev. 2 PL-NF-02-001 Rev. 3 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 1/27/2004
- PPL Rev. 2 PL-NF-02-001 Rev. 3 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.
ISUSQUEHANNA UNIT 1 TRM/3.2-6 EFFECTIVE DATE 1/27/2004 fI
PPL Rev. 2 PL-NF-02-001 Rev.3 Page 6 of 36 3.0 SHUTDOWN MARGIN 3.1-Technical Specification Reference Technical Specification 3.1.1 3.2 DescriDtion 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, 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.
SUSQUEHANNA UNIT ITRM/3.2 EFFECTIVE DATE 1/27/2004
PPL Rev. 2 PL-Re%
NF-02-001
,.3 le 7 of 36 Pag
- 4.
VRG LNA R.
T RT 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 ATRIUTM-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 anid 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 1/27/2004
(9--
..I I I, '.
I SSES UNIT I CYCLE.13 V1)
C F-4 12 11
'-10 En f:A3 4-c:7'-
m~~
CD~~~C CD~~
- [REFER~ENCE T.S. 3.2.1 ~
USED IN DETERMINING MAPRAT55 r
-r
-1 sr or....
r r
r7.
S S
S I
S S
S.S.I.U.*.U.U.I.S.U.S.S.*.*.S.
r.
r r*
..S
.S..S.
S.
..5 S
S S
S S
S S
U S
S S
S S
- I
's S
S U
i I
U U
S U
Ila IV I
I r-m,
(D IQ I) 10000 20000 30000 40000 50000 Average Planar Exposure (MWD/MTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMTM.10 FUEL FIGURE 4.2-1 60000 70000 o
(O
- 0) 0
PPL Rev. 2 PL-NF-02-001 Rev. 3 Page 9 of 36 5.0 MINIMUM CRITICAL POWER RATIO (MCPRI 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 5.2-3: '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 I 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 1/27/2004
PPL Rev. 2 PL-NF-02-001 Rev. 3 Page 10 of 36 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2-11 EFFECTIVE DATE 1/27/2004
(2-qt I:
.... I
(-'
C P.'
Ln
'-I F-1 2.3 2.2 2.1 2.0 EA 1.9 IR 0
NJ I 0' 51.7 1.6 SSES UNIT I CYCLE 13 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE : REALISTIC AVERAGE SCRAM INSERTION TIME lSAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES,l
' l ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR (30,1.64)..
(98,1.54)
- A
.B (1
REFERENCE:
T.S. 3.2.21 (60,1.47)
(98,1.47)
CD r')5 mnI
-n C.)
--I I-i m
MI-h F-S S0.
1.5 1.4 1.3 108,1.53) 108,1.49) 30 40 50 60 70 80 90 100 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
.110 0.
Iu)0
- 0)
(9~Ol A -
fIt -.
(j JC SSES UNIT 1 CYCLE 13 3.0 1
F I
I I
2.9 I
I I
I I
1 14 2.8 -
2.7 2.6 1
I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1
t I
4 4
I I
I.
2.5 2.4 n 2.3 I\\.)
- - 2.1 c1.
O, 2.0 1.8 (25,2.41)
(30,2.41)
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR REF RE CE T'.'.,S
- _=_'_.-'_..__,.,
. (40,1.84)
(
~~~~~(40,1 82) ~
1
=2^^^
(810~~~~~~~~~~~~~~~~.7,1.53).
.E REN..-C A"_"
-U I -
(100,1.53)
(tO0,1.47) r
--i 1-4
-4 c
F_,
1 o-A 1.7 1.6 1.5 1.4 1.3 20 30 40 50 60 Core Power (% RATED) 70 80 gO 100 la m l 0 r to c
-*6 ta 0
a)
.o MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2
PPL Rev. 2 Mai Tubn Bypas inoperable:/.EOC-RPT~~~~~~~~~~
.ra l
PL-NF-02-001 Rev. 3-Page 13 of 36 TRM/3.2-14 EFFECTIVE DATE 1/27/2004 SUSQUERANNA UNIT
(9,rl (r,.
(
- 9 SSES UNIT I CYCLE 13 Ln r'-
'D 2-0-
2.3 2.2 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.1 N)'
N, C,
' 1' r11 rri 2.0
.E
.E 1.9 C
01
- , fa
.. D 1.7 I
1.6 1.5 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS.
. VALVES ARE NOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I
I I
I 4
4 4-(30,1.78)
(37 I)_
IL USED IN DETERMINING MFLCPR I
4
'B 1 >1 1.4 ]
REFERENCE:
T.S. 3.2.21 -I.
I I
I I
4.
i 11 _
- 1
- 4.
I I
I I
I 30 40 50 60 70 80.
90 100 110
-. 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)
FIGURE 5.2-3 l
m m m 0
-9b c
a) 7T1 0
00
Il ilT!'Il.
C,'j.:
SSES UNIT I CYCLE 13 FH
.1
,r
-n
.S r\\3 3.0 2.9 2.8 2.7 2.6 2.5
_ 2.4
_= 2.2 L.
- EL 2.1 0,.
. 2.0 C.
1.9 1.8 1.7
=
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM (25,2.64)
INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS
.\\:
~~~~~~~~~VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2._
^ \\
i
~~~~~~~~~USED IN DETERMINING MFLCPRr (40,2. 4)
A
^~
~
~~
~
~
~
~~~B l
(68.2,1.75)
REFERENC,E: T.S. 3.7.6 and 3.2.2
,. _ ---u I
. m i.:
H.
(100,1.75) 1.6 1.5 1.4 1.3 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE i EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4 ci :CD m
(n o
- o..
0 W.
0
- 0)
PPL Rev. 2 PL-NF-02-001 Rev.3 Page 16 of36 EOC-RPT Inoperable /
Main Turbine Bypass Operable e
TRM/3.2-17 SUSQUEHANNA UNIT I EFFECTIVE DATE 1/27/2004
(K)1 (p
SSES UNIT I CYCLE 13 C
cn
'-A 2.3 2.2 2.1 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
.TYARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 2.0 I.
__A E 1.9
- v 2 1.8 0*
. I,-
I 0
X en 1.7 2
I..
1.6 (30,1.64)
-?
1 1
1 A
I 9
F I
(108,1.64)
-n H
'-4 1
N, 1.5 1.4 1.3
REFERENCE:
T.S. 3.2.21 30.
40 50 60 70 80 90 100 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5 110 t 0 r
to v.
o
-4.
01 X-2 a
0
.0)
C-(5 (17l-..
C Z-D-
SSES UNIT 1 CYCLE 13 3.0 1
I T
V I
I I
I 2.9 2.8 I _
-I I
I I
LEGEND.
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.7 2.6 I
I 4.
4 2.5 -
I I
I I
I I
I i
I (25,2.41)
(30,2.41)
.0 1
-n
-n
'-4
~-A N3)
-rS O 2.4 0) 2.2
'a.
2.1
- 2.0 2 1.9 1.8 1.7 1.6 1.5 1.4 1.3 A
i I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 F
=
~~~~~~~~~~~~USED IN DETERMINING MFLCPAR (40,1.90 l
REFERENCE:
T.S. 3.3.4.1 and 74,.64)
-u
- (D (100,1.64) 20 30 40 50 60 70 80 90 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6 100 la m la
-D Z
t 0
o 0o 0-
PPL Rev. 2
- PL-NF-02-001 Rev. 3 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 TRM/3.2-20 SUSQUEHANNA UNIT 1 EFFECTIVE DATE 1/27/2004
PPL Rev. 2 PL-NF-02-001 Rev. 3 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 ATRIUM'-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.
Main Turbine Bypass noberable The LHGR for ATRlUMThT-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.
s SUSQUEHANNA UNIT
TRM/3.2-21 EFFECTIVE DATE 1/27/2004
6 C,,
16 I,,
14
-1
*
12 CD (U
0
- -
1O w
C U)
- 1.
04-(U I-(U U)
C m
6 r1 I',
-H 4
-H
- N)
-sJ
-S N)
.1 In.,
K-SSES UNIT CYCLE 13
.a
.a I
I I
I I
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
- i'
a-a
-a--
-a-.ra ARE OPERABLE 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
-L.
~
7 USDINGTEMNIGLDRX a
a a
a a
I.
.a.
a a
a a
a S~~~l I
s It el I
I I
I a
I I
I aI
- 59400.0,8.0 tt-----*--r-----t
@*..d.*..b_-...
d.,.*.....
I....
w~bb...*J^..*..*b..............".z..............b....*....b..........
- l a
a a@
a a
a a '
- a
- a a
a S
- ~
a a
a a
a a
a a
a a*
Fe-b-b-@-@4--e-
@@...J...............*
g..w@9..*.......r..
ar S§ I@
Il al a
a a
a g
- Wb l
@@e@@*@@
r.......4
- w lZZZ@
g gX g
a a9 a
a w
a l
l l
e
- I
_-l
§ II CD ID(
10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS OPERABLE ATRIUM
-10 FUEL FIGURE 6.2-1 70000 w :n r
. c 0 o.
Ca 0
- 0)
U
- 1'~'
(_,T-P1
-4 SSES UNIT 1 CYCLE 13 16 14
-I
12 a)
10 CA, a)
NJ a)
N
0 CA) 4(U I..(U a)
- I ~~SAFTYAALYS ES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
- S S
S S
- S S
S C
S S
S S
S S
S S
S R FERENCE: T.S. 3.2.3 and 3.7.6 0.
- g.
.. 1.
U SE.
..I N.D E T E R M IN.
N.G 0.0,12.3:
15000.0,12.3 :
S S
C S
S.
S s'
S S.
IL 5
S
.5~~~~~~~~~~~.
5.~
~ ~
~
~
~
~~~9 S
S S
S S
S
....S.S S
65-C 5
5 5.
.. I.
.J.. j.
. I..~~~~~~~~~.
~
~
~
~.
j..J..A..&
..q.~~~~~1 J
j 00
)i M 3C)7 co5
-HI
--I P1-I-
NJ NJ 4
0 10000 20000 30000 40000 50000 Average Planar Exposure (MWDIMTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS INOPERABLE' ATRtUMT 0FUEL FIGURE 6.2-2
- oooo 700 C
aC I
PPL Rev. 2 7.0 AVERAGE POWER RANGE MONITOR APRM)
PL-NF-02-001 Rev. 3 Page 23 of 36 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.
SUSQUERANNA UNIT I
- T-RM/3.2-24 EFFECTIVE DATE 1/27/2004
PPL Rev. 2 PL-NF-02-001 Rev. 3 Page 24 of 36 t : '.
- Table 7.2-1 APRM Setpoint for
-" Two Loop Operation Trip Setpoint Allowable Value S5< (0.58W + 59%) T S 5 (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 S
(0.58W + 57%) T' SRB * (0.58W + 45%) T-SRB < (0.58W + 48%) T where: S and SsB-are in percent of RATED THERMAL POWER W =
Lo6p 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 ATRUM'-1 0 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 TRM/3.2 25 EFFECTIVE DATE 1/27/2004
. n r
. I
0
\\4 J
01-~
I-,)C JC P1 R
18 16
'-4 ~
~
1
~14
-4 o
8
-n
'-4
-I C)
SSES UNIT 1 CYCLE 13
.1.
- 1.
I. r.
1.USED IN DETERMINING FDLRC
.J.I i.L.
J...
J..
~~~
d..b...S....*..b..S.~.
- I...
S S
S S
S U
I U
S U
U S
S S
S S
I S
S I
I S~~~~~~~~~~1 S I S
S S
S S~ ~ ~
U
-U.
I -
- I CD lD 10000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT FOR APRM SETPOINTS VER8US AVERAGE PLANAR EXPOSURE z
ATRIUM'-10 FUEL FIGURE 7.2-1 XD 0o
PPL Rev. 2 PL-NF-02-001 Rev. 3 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, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUMW-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 (ATRIUMTM-1 0) shall be the greater of:
(I~)
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.UNIT3I TRM/3.2-27 EFFECTIVE DATE 1/27/2004 SUQEANAUI
. TI.-2 EFETV AT
/720
PPL Rev. 2 PL-NF-02001 Rev. 3 Page 27 of 36 Average 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.
SUSQUEHANNA UNIT 1 TRM/3.2-28 EFFECTIVE DATE 1/27/2004
(a~~~~~~~~~"
V)
~~~~~SSES UNIT 1-CYCLE 13 C=
12
~ ~
~
.d..b.9....d..b....9...
11 -
~~.
~
~.
J..aJ.L..-.
9 9 9 9 9
9 9
9 9
9 9
9 9
9.9 USED IN DETER ININ MAPRAT 9
- 4.
'r 4-
- 4' -
'r -
- 4. -9 9
9 9
9 23 J
M~~~~~~~~~~~~9999 0.0,9.2
' 15000,9.2...~~~~~.
ia) co 7J 0JJ.J..A..L
~~~~~~~~~~~~~
0 9.........
.I
-n a
~~
7
.. ~~~~~4 J
I.....4-
.L 900,5. -
9 0
.10000 20000 30000 40000 50000 60000
.70000 rn Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE C
c:)
~~~~~~~~~~SINGLE LOOP OPERATION TMR.1 FUEL FIGURE 8.2-1
0 W"In;,
1 VA C
I VH D
l C)
SC
-4S N).
SSES UNIT 1 CYCLE 13 2.6 2.5 2.4 I
I I
I 4
I 4.-
END VE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
- INSERTION TIME VE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1
I.
91 n
I I
I I
2.3
,c C
2.2
.0 a.
.02 2.1 2.0 1.9 1.8 I
- 4.
I 4.
USED IN DETERMINING MFLCPR (30,2.20)
(108,2.2C 4.
-AII I
- ~~ I Rs
- 4.
- 4.
I D
-u
.. -.'U (D
5
.-..q h)
REFERENCE:
T.S. 3.4.1 and 3.2.2 30 40 50 60 70 80 90 Total Core Flow (Mlbm/hr)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2
. 100 110 0 w V.
.o iu.
t3 0'
o 0cJ 0
co~
0
- 0)
I
'0--
1,511%
(12_,,.
Cl CA C
m I-A Cr CD rri
-4 N3o o-
-5 SSES UNIT 1 CYCLE 13 3.5 3.4 3.3 3.2 3.1 3.0
- "2.9 om 2.8 2.7 w
0 '
° 2.6 0.
m 2.5 2.4 2.3 2.2 2.1 2.0 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES
(25,2.81)
(30281)
ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR
\\38 5,-A
_B (38.52.20)_
(100,2.20) 00 I
-a
.1
-1
REFERENCE:
T.S. 3.4.1 and n I
- 0. r..
1 4
II I
T I
1 1
1 I
I I
11 1
4 I
I V
20 30 40 50 60 70 80
.90 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-3 Ca S
o o
o a 0
0
- 0)
-A r
0
(-I Vl)
Ca m
-H SSES UNIT 1 CYCLE 13 3.5 -.7-1
'7
'7 3.4 I.
I I
I I
L I
3.3 3.2 3.1 I
I I
LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME C
5 ii-
_(25,3.07).
I I
I I
3.0
\\lI I
I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPAS' VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 -
_~~~
1 (1 0.20 CA N,
m rr
-n 5-4
-1 m
IoI N,
- g 2.9 I m 2.8 2.7 oI 2.6 m 2.5 2.4 2.3 2.2 2.1 2.0 1.9 N
I
_I 4
4 USED IN DETERMINING MFLCPR
_1 \\
(40,2.
A 1
B)
_ _ _ _ (54.6,2.20)
- -g
-1
REFERENCE:
T.S. 3.4.1, 3.7.6, and 3.2.21-______
I 4*
4 I.
I I
5 4
4 4
20 30 40 50 60 70 80 go Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE / EOC-RPT OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4 100 N :n -
to 7
o.
o o
W o a)
(ji 0_
-1'r.
SSES UNIT 1 CYCLE 13 d-C m
t
'-4
--I 3.5 3.4 3.3 I
Y I
I I
I 4
-4 m
4 4
4~~~~~~~~~~~~~~~~~~~~~J%~~~~~~~~~~~UI1~ ~~~~~~~~
END VE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME VE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.2 3.1 ___ II._1 I
I I
I I
-4A
.W I-r,
cA 3.0
- E 2.9 3
m 2.8 a
1! 2.7 0.
0M 2.6 a.6 L
2 2.5
- 4.
4 4
(2 5,2.81 (30,2.81)
I 4.
I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED I I
I
~USED IN DETERMINING MFLCPR lr I
4.4 2.4
\\.
,A-B.
(41.3,2.20)
-o1 (100,2.20)
C,)
-4i
'-_4 m
-4 I,
N3 2.3 2.2 2.1 2.0 1
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2.2
- 4.
I I
1 I
1 1.Q
.4 4
4 4
4 20 30 40 50
.60
- t 70 Core Power (% RATED) 80 90 100 MCPR OPERATING LIMIT VERSUS CORE POWER
- EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-5 to
° o
(.t 0
- 0)
O
.0 C)
PPL Rev. 2 PL-NF-02-001 Rev. 3 Page 33 of 36 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.4.1 9.2 DescriDtion Monitor reactor conditions to maintain THERMAL POWER / core flow outside of Stability Regions I and II of the Power/ Flow map, Figure 9.1.
SUSQUEHANNA UNIT. 1
-TRM/3.2-34 EFFECTIVE DATE 1/27/2004
I -,, --9
..- 4.:
- PPL Rev. 2 PL-NF-02-001 Rev. 3 Page 340of36 120 110*
100*
90 T=
. 120 urpose i- -i
-L I
Ill 1
I UN I
I I I I
t POWER /
T 1r 1 1r.
J.
11 I 100 Io In I 1IT I It:
I1 Initial / Date:
110 STABILITY REGION IMUEDIATE SCRAM REQUnRED IAW ON-178402 100 UATBILITY REGION l IMUEDIATELY EXrr REGION LAW ON-1754 90 RESTRICTED REGION (As defined In Aftachment G to NDAP-QA338) w I-0 0
[L E
a) 80 70 60 50 40-30 20 l 4 lt-: 1 1 -- I 1
-I-a.,
It_
I 1 1-I
'i I-
.1 ITI
.ii I I. 1 _I_ I-I
...- 1 I
l I'll 4.
li lii
._ L
__ L.
I I 80 I
1 I
..?-
! -. I l
I I
I l l
- 1
,J.:..
Ill
,6..66-4.
- iii, 70 I,
I I I. I. I liii_ :
1 -
I I.
I I I I
.6, 5.4.
Speed l
ll I I
.~ ~ ~~~I eur I*
tt 84'
'_*_!2_R,!!!
i<'!
l
-srt
-r,
.'4,-e,~Ii- -
r-I I
4 Rodne
.5 J..L I.~~~~~~~~~~j I
i 0
I_
liii O~RITED REIg rs ^$g l
A pox lsl^
l*bl^
I RESTCEEGO
.. s 40 30 20 10 10
- I 0
10 I~~~..
I, qIiWWIi
.. I.,I u
20 30 40 0
- - O 60 70 80 90 100 110
-Total Core Flow (Mlbmlhr)
N
- -Figure 9.1 Power/ Flow Map TRM/3.2-35 SUSQUEHANNA UNIT 1 EFFECTIVE DATE 1/27/2004
, \\ i, ~*
- r,*,
PPL Rev. 2 PL-NF-02-001 Rev. 3 Page 35 of 36
-J 10.0 REFEI 10.1 RENCES CZQ>
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 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.
- 5. ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"
November'1 990.
- 6. ANF-1 125(P)(A) and ANF-1 125(P)(A), Supplement 1, ANFB Critical Power Correlation," April 1990.
- 7. NEDC-32071 P. RSAFER/GESTR-LOCA Loss of Coolant Accident Analysis,"
GE Nuclear Energy, May 1992.
- 8. 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).
- 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 TRM/3.2 EFFECTIVE DATE 1/27/2004
PPL Rev. 2 PL-NF-02-001 Rev. 3 w
~~~~~Page 36 of 36 AIJ-
- 12. 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-NF80-19(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 Thermdx: 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., Sgpplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM' or LEFM CheckPlus System," Revision 0, Engineering Report ER-1 60P, May 2000.
- 21. EMF-85-74(P), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation -
Model," Revision 0, Supplements 1 and 2, February 1998.
- 22. EMF-CC-074(P)(A), Volume 4, Revision 0, BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2," November 1999.
SUSQUEHANNA UNIT TRM/3.2-37, EFFECTIVE DATE 1/27/2004 i
.