ML040420578
| ML040420578 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/05/2004 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 28401 PL-NF-03-001, Rev 2 | |
| Download: ML040420578 (38) | |
Text
Feb. 05, 2004 Page 1
of 1 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2004)-5891 USER INFORMATION:
LACH*ROSE EMPL#:28401 CA#: 0363 Addre A2 Phone#
2 TRANSMITTAL INFORMATION:
TO:
02/05/2 004 LOCATION:
'ROM:
NUCLEAR RECORDS DOCUMENT C NTROL CENTER UCSA-2)
HE FOLLOWING CHANGES HAVE OCCURR D TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO OU:
TRM2 -
TECHNICAL REQUIREMENTS MANAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 01/29/2004 ADD MANUAL TABLE OF CONTENTS DATE: 02/04/2004 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT 3.2.1 REPLACE:
REV:1 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES.
PLEASE 4AKE 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.
t-
-7 Core Operating Limits Report (COLR) 3.2.1 PPL Rev. 1 3.2 Core Operating Limits Report (COLIR) 3.2.1 Core Operating Limits Report (COLR)
TRO 3.2.1 APPLICABILITY:
The Core Operating Limits specified in the attached COLR shall be met.
Specified in the referenced Technical Specifications.
I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits not A.1 erform action(s)
Specified in referenced met.
iescribed in referenced Technical jTechnical Specification.
Specifications.
TECHNICAL REQUIREMENT SURVEILILANCE SURVEILLANCE FREQUENCY NOTE N/A No associated Surveillances. Surveillances are implemented in the applicable Technical SpecificationsJ SUSQUEHANNA - UNIT 2 3.2-1 EFFECTIVE DATE 8/31/1998
PPL Rev.
PL-NF-03-001 Rev. 2 Page 1 of36 I
Susquehanna SES Unit 2!Cycle 12 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering November 2003
.,~~
,S-us,+',
ppI, SUSQUEHANNA UNIT 2 TRM/3.2-2 EFFECTIVE DATE 11/01/2003
PPL R6v. 1 I
q PL-NF-03-001 Rev. 2 Page 2 of 36 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.,
Affected No.
Sections Description/Purpose of Revision 0
I 2
ALL 5.0 6.0 8.0 TOC 1.0 9.0 10.0 Issuance of this COLR is in support of Unit 2 Cycle 12 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 185 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 I Flow map is already included ir NDAP-QA-0338.
FORM NFP-QA-008-2, Rev. I SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-03-001 Rev. 2 Page 3 of36 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 12 CORE OPERATING LIMITS REPORT Table of Contents
1.0 INTRODUCTION
4......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 / FLOW MAP.33
10.0 REFERENCES
.35 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 11/01/2003
PPL Rv.
I.
PL-NF-03-001 Rev. 2 Page 4 of 36
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 12 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, A 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.
JEHANNA UNIT 2 TRM /3.2-5 EFFECTIVE DATE 11/01/2OOK I
SUSQL
PPL Rev. 1 PL-NF-03-001 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 2 TRM/3.2-6 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-03-001 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 rd 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 2 TRM/3.2-7 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-03-001 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 Description The APLHGRs for ATRIUMT'-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 2
-TRM/3. 2-8 EFFECTIVE DATE 11/01/2003
- 0.
CJ C ~'
m C
--i 16 14 E
-A3 i 010 q5 w
CUai m
01 SSES UNIT 2 CYCLE 12 a
a...
a.a.a.a.a.a.a.a.a.a.a.a.
a a
a a
a a
a a
a~ ~ ~~
a
....a...
a.a a
a a
a a
a a
a a
a~ ~ ~ ~
a a.a.a
.a.a..
a...
a a
a a
a a
a a
a
..a
- a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a......
(DI
-n1 m
C)--i 1-.4 m
'a C=.
00 4
10000 0
20000 30000 40000 50000 Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUmTMO1 FUEL FIGURE 4.241 60000 700
- CD Z
co " )71 CO) 0
- 0) 0
PPL Rev. i PL-NF-03-001 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 (ATRIUM'm-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 / 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 2 T.RM/3.2-10 EFFECTIVE DATE 11/01/2003
PPL Rev.
PL-NF-03-001 Rev. 2 Page 10 of 36 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3. 2-11 EFFECTIVE DATE 11/01/2003
i C
r, SSES UNIT 2 CYCLE 12 C.
c/)
__D 2.3 rn 2
2.2.2 2.1 2.0
,E 1.9
-I 01 1
mN
~-A CL 0\\
0 2-1.7 I
I I
I LEGEND I
- 4.
+
CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 4
- 4.
I.
I 4.
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR n=___
-U 1.6 -(30,1.!.
Ju1-l J
-n
'-4 P1 ca 1-4 1
F-S
'-A
~-S r\\3 CA, (45.7,1.49) 1.5 1.4 1.3 a
- 4.
+
I 4.-
A _ __
v
_~~~
_ I-
-I-
'I.
1 4.
P B
~
(108,1.49)
(108,1.47)
I
REFERENCE:
T.S. 3.2.21 (60,1.47) 4 4.
I
- 4.
4 4
1
- 4.
4 I
- 4.
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
- X T o <"
N -nv O~
0 W
o a)
(ii C:
(
Vl)
N) 3.0 2.9 2.8 2.7 2.6 2.5
--I c,
-al
- 2.4 X 2.3 2.2 tu I-O 2.1 0
a: 2.0 1.9 SSES UNIT 2 CYCLE 12 LEGEND
._____ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (25,2.30)
.(30,2.253 USED IN DETERMINING MFLCPR (80,1.49)
REFERENCE:
T.S. 3.2.2 (72.9,1.47) 1.8
-4 t--4
-4
'-A C:)
1.7 1.6 1.5 1.4 1.3 (100,1.49)
(1 00,1.47) 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2
)(D r-co <
K) 6 o
W a) 0 a)
--L
PPL Rev.
PL-NF-03-001 Rev. 2 Page 13 of36 Main Turbine Bypass Inoperable / EOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3. 2 EFFECTIVE DATE 11/01/2003
c)
C*
SSES UNIT 2 CYCLE 12
,C.
C Jo 2.3 c
2.2
'-41 2.1 2.0 E1.9 0)
CA,)
8 L-, 1.8 o-1
~-
.C tn 0
ci,
& 1.7 1.6 I
I t-1,ur
'END RVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME WE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I I CUR I
I 1 1
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I
I I
I I
1 I
USED IN DETERMINING MFLCPR r
(30,1.79)
{ AA A
B
- I
~~~~(Iuu,
,1.79)
I.
-o
-u (D,
C-)
-I4
'--4 I.
t-aj r%)
Ci3 1.5 1.4.
REFERENCE:
T.S. 3.7.6 and 3.2.2 I
I 1.3 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 T ;e T m ( r-CD. Z o
-o 0
a) 0
- 0)
..L
(
C.
I Cj2 Lol c
'D r.
SSES UNIT 2 CYCLE 12 3.0 2.9 4
4 4.-
2.8 2.7 2.6 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
-(25,2.54)1 I
I I
II 2.5 2.4 g X2.3 tm.
= 2.2
. ;\\
1 c-2.1
- a. 2.0 1.9 1.8
\\i.i_
SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I
I I
I T
=
~~~~~~~~~~USED N DETERMINING MFLCPRr
~(40,2,022; B
_ _ _ _ _ _ _ _(
6 0.1,1.7 9 )
REFERENCE:
T.S. 3.7.6
.2.
u-u (D
5 (100,1.79) m r
C-)
--i
'--4 m
I=l m
-S C)
PO C=
C) cW 1.7 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 / EOC-RPT OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4
-u ;u -u nm (D r (O <
(D C
Z 0
o
° 0
o
-W 0
CY)
PPL Rev. 1 PL-NF-03-001 Rev. 2 Page 16 of 36 EOC-RPT Inoperable I Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-17 EFFECTIVE DATE 11/01/2003
(6 C.
C)
V*)
cLn
-i 23 SSES UNIT 2 CYCLE 12 2.3 2.2 2.1 T.
r I
t LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I I.
I 2.0 4..
CA)
(U 18 a.
o: t
,l.7 1.6 t
SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I
I
'I 1
I USED IN DETERMINING MFLCPR I
7 1
- 1.
1
-(30,1.
_^.
VF.I- ~
~
~
14-4 44,A l
B.
(108,1.56)
I
1 i.
m
'-I rn
-n m
'-4
--I 0-a r\\)
CD 1.5 1.4
REFERENCE:
T.S. 3.3.4.1 and 3.2.2l
_ I
_ I
_~~~~~~~~~~~~~~~
1.3 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
'U ;U T a
r (D 'Z
-4 0
o o
0 CA) 0
- 0)
CI C -
C',
C, r-m
'-~-4 SSES UNIT 2 CYCLE 12 3.0 2.9 2.8 2.7 2.6 I
I I
I I
I 4
4 I
4.
END VE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME FE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I I
I 4.-
2.5 I
4 4-SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 2.4 -
i
- JE2.3 O -0 '2.2 I-a i o
F--j 2.1 1
0 U
)
1.9 1.8 (25,2.31)
I I
Ae__I_
I I
_#\\%#
4%
pul.La)
I USED IN DETERMINING MFLCPR I
A B
REFERENCE:
T.S. 3.3.4.1 and 3.2.2
-n
-n P1 C-,
--i p-4
- -4 F-.l INJ CA) c~
W 1.7 1.6 1.5 1.4
.1.3 (100,1.56) 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER
- EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6
- 0)
CD r, (0 <
0D 0
-0 C,
0
- 0)
PPL Rev. I PL-NF-03-001 Rev. 2 Page 19 of 36 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time MCPR Operating Limits Dependent 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 2 TRM./3.2-20 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-03-001 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 Bvpass Operable The LHGR for ATRIUM'-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.
Main Turbine Bypass Inoperable The LHGR for ATRIUM'-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.
SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 11/01/2003
16
~~~SSES UNIT 2 CYCLE 12 ri-I a1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 14- 0.0,13.4....."15000,13.4.:...
REFERENCE:
T.S. 3.2.3-
--4 a~~~~
~ ~ ~~~~
.... a a
a a
a a
aa a
a a
a a
- a.
a a
~
HUSEDIDETERMINING FDLRXL 12 C, 0-6 *aa........~~~......
~..
N)
~
~ ~ ~ ~ ~ a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
ri ia a
a a. a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a1 a
a a
a a.
a a
a
- a.
a a
a a
a a
a a
a a
a..a.a.a a
a a
a a
- a.
a a
rri
- 3 a
a.a a.aa.aa.a a.a
- a.
..a..
a
.a..a..a
.a
..a a..a
.a...
- a..
- a.
- a.
a.a.a
-ri 6700aa a
a0 a
a a
a a
a aaa a
a a
a a
a4 0
10000 20000 30000 40000 50000 60000
.70000 C=)
~~~~~~~~~~Average Planar Exposure (MWDIMTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS OPERABLE
_I C.0~~~~~~~~
ATRIUMM 0 FUEL 0)
FIGURE 6.241
.0L C-C GI c
rLn CD M
C.,
rN Tl CA) m F,
m CP)
--4 m
-n
-)
-Si CA)
SSES UNIT 2 CYCLE 12 16 14
- t 12 E.
1 a'
a c.01 (U
I.
6 4-6 SAFETYANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2
REFERENCE:
T.S. 3.2.3 and 3.7.6 U S E D IN DET E R MININGFDLR 0.0,1 1.9,
@, 1 5000,1 1.9 2
2 67000,6.36
.I r-
- U
- cI I.
4 0
101000 20000 30000 40000 50000 60(
Average Planar Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS INOPERABLE ATRIUMTM_10 FUEL FIGURE 6.2-2 000 70000 o
'?
.U3<
0 0a 0
O)
PPL Rev. 1 PL-NF-03-001 Rev. 2 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 2 TRM/3.2-24 EFFECTIVE DATE 11/01/2003
PPL Rev.
PL-NF-03-001 Rev. 2 Page 24 of 36 Table 7.2-1 APRM Setpoint for Two Loop Operation I
Trip Setpoint I
Allowable Value S S (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 5 (0.58W + 54%) T S*5 (0.58W + 57%) T' SRB < (0.58W + 45%) T SRB S (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 lirhit for APRM setpoints for ATRIUM'-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 2 TRM/3.2-25 r EFFECTIVE DATE 11/01/2003
(c-i C
II L,)
-4~
--4 CA, SSES UNIT 2 CYCLE 12 16 14 (U
WL 8
- ~..,.
REFERENCE:
T.S.3.
4: :
- ~ *,*, ~ ~
- J U S E D I N DUSEDM INNETERMI ING*FDLa a
a a a
a a
a a
a a
a a
a a
S S
a a
a a
- a a
a a..........a.
a a
a a
- a a a a a a a a
a a
a a
a a
'a a
a a
a a
a a
a a
a a
a a
a~~.
- a a
a
.a.a.a.a.*.
.a..a.a.a.a.a I
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a
a a0a a
a 3
a a
a a
a a
a a
a a
a a
JI a
a
.a.a...a..a.
.a.a.a....
.a.a.a
.*..a.a...a.a
- t..b.S.,...4.b.A.L.I.
...b.
a a
a a
a CDIr'
-n C-)
F-4
-4 t-S.
f-A C) 6 4
0 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWD/MTU)
LINEAR HEAT GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE ATRIUMM 10 FUEL FIGURE 7.2-1 70000 Dl) CD r-ul 0
o 9-6 0 wA 0
- 0)
-L
PPL Rev. I PL-NF-03-001 Rev. 2 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 (ATRIUMT M-1O) 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 8.24: Main Turbine Bypass Inoperable / EOC-RPT Operable from BOC to EOC Figure 8.2-5: EOC-RPT Inoperable / Main Turbine Bypass Operable from BOC to EOC The MCPR limits in Figures 8.2-2 through 8.2-5 are valid only for Single Loop operation.
Linear Heat Generation Rate Limit The LHGR limits for Single Loop Operation are defined in Section 6.0.
SUSQUEHANNA UNIT 2 TRM/3.2-27 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-03-001 Rev. 2 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 2 TRM/3.2-28 EFFECTIVE DATE 11/01/2003
(J-CI (2
JC a-
--I Na SSES UNIT 2 CYCLE 12 16 14
=
12 E
=8 m.
2 a'
c
- a a
a a
- a a
a a
a a
a a
a a
a a
a a
a a~~~~~~~~~
a a
a.
a a.
a a
a a
a a
a a
a a
a a
a a
a a
- a.
a aNaCE a
a nd 3.2.
a1 a
a a
a a
a a
a a
a a
a a
USa D IN DETERMINIa MAPRATa a
a a...
..a a
a a
a aa.
a a
a a
a a
a a
a a.*.a.*...a...
- a.
.FE EN
. 3..a d.
....a.....
- a...
- a.
..a.a..
a.a a.a.a
. a..a
..a.
.a. a..a..a
.a
..a a
..a
..a. a..a a
a a
.a....
U...
N.. M...
a a
a a
a a
- a.
a a
a a
a a
a..
a a.a.
a.a.a.a..
a..a a.a.a
- a.
.a.a a.a.a a
a a70a00a a
a a
a a
a a
a a
a a...a a
a.a
- a.
.a..a.a a.
m C-)
--I m
Ia) s-sA I-a
-a CD) 4 0
10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION IUTM1 ATRIU
-0 FUEL FIGURE 8.2-1 70000 0)CD f
(D Z
OD 0
-~
0 (A) o
- 0)
(a2 C
c i CA c-JC m
-i23 SSES UNIT 2 CYCLE 12 2.6 I
I I
2.5 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.4 1
6-I I
I I
a 2.3 6& 2.2 WA 0.
co 0
- a.
2.1 r
2.0 1.
rn C-)
'-4 m
~1.9 F-IA
~-&
1.8
-C=
ro I
- 4.
1 I
I USED IN DETERMINING MFLCPR I
(30,2.20) 1 4-
-A
~ B
-(108,2.20) 1
.9 I
'9
__ I
___ I
.H-
REFERENCE:
T.S. 3.4.1 and 3.2.2
-1 r
i 4
I 4
I I
4.
30
. 40 so 60 70 80 90 100 110 Total Core Flow (MLB/HR)
MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2 m
D r
(
(D Z
0 0
-4 0
- 0)
_x
(2 C'
UNIT 2 CYCLE 12 C'-
SSES Vm C
'-4 c-4
.3 3.5 3.4 3.3 3.2 3.1 3.0 I.
1,
' CA)
E9 2.9
-j oi 2.8 (n
- 2.7
° 2.6 02 m 2.5
~~~~~~~~I I
I I
LEGEND
.________ l_______
L CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
__(25,2.75)
=
USED IN DETERMINING MFLCPR (30,2.69)
(39.4,2.20)
RCEERENCE: T.S. 3.4.1 and 3.2.
-u CD-2.4 2.3 m-n m
C*)
-i
'-4 m
'-aj t-S "A3 2.2 2.1 2.0 1.9 (100,2.20) 20 30 40 50
. 60 70 80 90 100 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 X -u
()
- Z o
0 o
a) 0
&)
0
- 0)
Cl C
(/~
C,,
--I 3.5 3.4 3.3 3.2 3.1 3.0
- E 2.9
--I E
can 2.8 a! 2.7 2.6 u2 2.5 2.4 SSES UNIT 2 CYCLE 12 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME (25,3.03)-
L
_ SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 USED IN DETERMINING MFLCPR
~~~(40,2.4.
A B -
(100,2.20)
(55.7,2.20) 4a REFRCE: T.S. 3.4, 1, 3.7.6, and m
--i m
I--&
I-A C,.)
2.3 2.2 2.1 2.0 1.9 20 30 40 50 60 70 80 90 100 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 u
an m r co <
CD.
Z
&,3 "71
-0 0
co 0
0)
0I (I--
(1f LnC JC TC c-4 r%3 N2 SSES UNIT 2 CYCLE 12 3.5 3.4 3.3 3.2 3.1 I
I
- 1I I
- 1. Ii LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I
I 3.0 E 2.9
-4 C.._
C) 0.
CA3
) i c 2.6 EL 0
° 2.6 2.4 I
I I
. SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-(252
-I~~~~~~~~~~~~~~~~~~
I USED IN DETERMINING MFLCPR (30,2.69)
I 4
I 4
1 I
-A B
(39.4,2.20)
I I
I I
I~~ _________________________
m
'-I m
C-)
-4i 0-4
-4 P1 I-.
I-.
CA) 2.3 2.2
-2.1 2.0 1.9 I
-1~
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2'.21 4
1.
I I
I I
(100,2.20) 00 i
I 4
4.
20 30 40 50 60 70 80 90 Core Power (% RATED)
MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-5 Xu ;u 11 n) CD r aO z
(D co r*)
0 o
-h 0
CA) 0
- 0)
-A
PPL Rev. 1 PL-NF-03-001 Rev. 2 Page 33 of 36 9.0 POWER / FLOW A MAP I
9.1 Technical Specification A Reference Technical Specification 3.4. 1 9.2 A Description Monitor reactor conditions to maintain THERMAL POWER / core flow outside A of Stability Regions I and 11 of the Power/ Flow map, Figure 9.A 1.
SUSQUEHANNA UNIT 2 TRM/3.2-34 EFFECTIVE DATE 11/01/2003 I
I I
I
PPL Rev. 1
- PL-NF-03-001 Rev. 2 Page 34 of 36 120 120 110 ~
Purpose.
I Initial I Date:
.... I @ *.
- 1 I.
100 +
STABItTY REGION I IMMEDIATE SCRAM REQUIRED U
tAW ON-278402 STABILTlY REGION 11 IMMEDIATELY EXIT REGION tAW ON278402 90 80 W
70 l1 W
60 0
0 o
50 s-RESTRICTED REGION (As defined In Aftachment G to
... i.:
! :. T, 4-4-1.... :.:.T.
40 -
30 20 10
.,.Natur alCiwainrS-Ci rcultn Une (Imnediate Scram Required)
....,...~.
... ~~~...
.4...,..,
.One Pump.,
...r3t0% Speedt....:.
Appt ox -------
.sTwo Pump..
.:30% Speedt J
7Appmx I...u.r Ju..
u....
One Pump 1
Zit 3 r EOSpeed.
K 60 1 % 70 L.80 !-.- 9 100 E'
,,....,.ICTE R11I I'
...._..,O ------ ? LX'.I
.I.-. - -,
........'00.00.0F
- 1.
.1.....
0 0
- I
- t::
1:::
- I... I 0
10 20 30 40
. 50 60 70 80 90 100 110 Total Core Flow (Mlbm/hr)
Figure 9.1 Power / Flow Map SUSQUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE DATE 11/01/2003
PPL Rev.
PL-NF-03-001 Rev. 2 Page 35 of 36 A
10.0 REFERENCES
A 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 Analysis,"
Exxon Nuclear Company, Inc.
- 6. XN-NF-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," September 1982.
- 7. XN-NF-80-19(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).
SUSQUEHA.NNA UNIT 2 TRM/3.2-36 EFFECTIVE DATE 11/01/2003
PPL Rev. 1 PL-NF-03-001 Rev. 2 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., 'S~uplement 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.
- 18. EMF-85-74(P)(A), RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements 1 and 2, February 1998.
- 19. EMF-2158(P)(A), Revision 0, Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microburn-B2," Siemens Power Corporation, October 1999.
- 20. EMF-CC-074(P)(A), Volume 4, Revision O, A BWR Stability Analysis:
Assessment A of STAIF with Input from MICROBURN-B2," November 1999.A SUSQUEHANNA UNIT 2 TRM/3. 2-37 EFFECTIVE DATE 11/01/2003