ML13137A092
| ML13137A092 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 05/08/2013 |
| From: | PPL Bell Bend |
| To: | Gerlach R Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PL-NF-13-003, Rev 0 | |
| Download: ML13137A092 (58) | |
Text
May. 08, 2013 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2013-21097 USER INFORMATION:
GERLACH*ROSE M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
TO: GERLACH*ROSE M 05/08/2013 LOCATION: USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL. WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE
- UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL. TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF ERRORS.
ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 04/30/2013 ADD MANUAL TABLE OF CONTENTS DATE: 05/07/2013 CATEGORY: DOCUMENTS TYPE: TRM2 Aubý o?--fL-
May. 08, 2013 Page 2 of 2 ID: TEXT 3.2.1 REPLACE: REV:10 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE. UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
Core Operating Limits Report (COLR)
PPL Rev. 10 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 not A.1 Perform action(s) Specified In referenced met. described in referenced Technical Technical Specification. Specifications.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY
-- NOTE --------------.--------------------- NIA No associated Surveillances. Surveillances are Implemented In the applicable Technical Specifications, SUSQUEHANNA - UNIT 2 TRM / 3.2-1 EFFECTIVE DATE 08/31/1998
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 1 of 55 Susquehanna SES Unit 2 Cycle 17 CORE OPERATING LIMITS REPORT Nuclear Fuels Engineering APRIL 2013 pp SUSQUEHANNA UNIT 2 TRMl/3.2- 2 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 2 of 55 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. Affected No. Sections Description/Purpose of Revision 0 ALL Initial issuance of this COLR is in support of Unit 2 Cycle 17 operation.
~.l.
FORM NFP-QA-008-2, Rev. I SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 3 of 55 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 17 CORE OPERATING LIMITS REPORT Table of Contents 1.0 INTRO DUCTIO N.................................................................................................... 4 2.0 DEFINITIO NS .................................................................................................... 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) ....................................................... 24 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQ UIREM ENTS .................................................................................................. 34 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION .................................... 36 9.0 POWER / FLOW MAP ........................................................................................... 51 10.0 OPRM SETPOINTS .............................................................................................. 53 11.0 REFERENC ES ..................................................................................................... 54 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 4 of 55
1.0 INTRODUCTION
This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 17 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, RBM setpoints, and OPRM setpoints 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 2 TPM/3.2-5 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 5 of 55 2.0 DEFINITIONS Terms used in (his 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 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.
2.2 The PELLET EXPOSURE shall be equal to the total energy produced per unit length of fuel rod at the specified height divided by the total initial weight of uranium per unit length of that rod at that height.
2.3 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.
2.4 LHGRFACf is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFAC, multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from core flows less than 108 Mlbm/hr.
2.5 LHGRFAC, is a multiplier applied to the LHGR limit when operating at less then RATED THERMAL POWER. The LHGRFACp multiplier protects against both fuel centerline melting and cladding strain during anticipated system transients initiated from partial power conditions.
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 OPRM is the Oscillation Power Range Monitor. The Oscillation Power Range Monitor (OPRM) will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR safety limit is not violated.
2.9 Np is the OPRM setpoint for the number of consecutive confirmations of oscillation half-cycles that will be considered evidence of a stability related power oscillation.
2.10 Sp is the OPRM trip setpoint for the peak to average OPRM signal.
2.11 Fp is the core flow, in Mlbm / hr, below which the OPRM RPS trip is activated.
SUSQUEHANNA UNIT 2 TRMI3.2- 6 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 6 of 55 3.0 SHUTDOWN MARGIN 3.1 Technical Specification Reference Technical Specification 3.1.1 3.2 Description The SHUTDOWN MARGIN shall be equal to or greater than:
a) 0.38% Ak/k with the highest worth rod analytically determined OR b) 0.28% Ak/k with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and poison burnup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R', is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of uR" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.
The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.
SUSQUEHANNA UNIT 2 TPM/3.2-7 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 7 of 55 4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 3.2.1 4.2 Description The APLHGRs for ATRIUMTm-10 fuel shall not exceed the limit shown in Figure 4.2-1.
The APLHGR limits in Figure 4.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable in Two Loop operation. The APLHGR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRMI3,2-8 EFFECTIVE DATE 4/25/2013
. mo Co a
Co C
SSES UNIT 2 CYCLE 17 a 16.0 rn II I II Il I I Il =i
- 1 I l I I I I I 1 1 1 a 1I I 1 I I v I I il I iI lI I iI I L II I I I I I II
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- II I I I I II I I I I I I I l I I I I I I I A I5 I I I I I I I lI lIlI Il* l rI l lII
- I iII I a IIiiiiiiii I £IIIIiIIII I I II I I V~IIII IIIIi i III i l ll l l III I I II I '- I I I I I I ,i ii iIu I I I I I II I II I II I I I II I I II I I I I 12.0 I I I I I I I I I I II I I I II I I 1I J I1 I I 1 1 1 1 1 1 1 tIlI lE II II II I I I I I .I: I I I I
- I
.I I IIII I II II I I I I I*
-4 a.c-I I I I I I I I I I I I I II III I I
_oI 00
,a 10.0 I II I I I ~ III~I II II I N,
'.0 I I I I III I c 8.0 lI l l* l l l I I4 I I I I I I I II I I III II II III I I II*
I I IIil
.I l I I . I mf (D
m 00 C-) 6.0 4.0 0 10000 20000 30000 40000 50000 60000 70000 N) Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION cnb0 w.I ATRiUMT'-10 FUEL FIGURE 4.2-i
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 9 of 55 5.0 MINIMUM CRITICAL POWER RATIO (MC.P 5.1 Technical Specification Reference Technical Specification 3.2.2, 3.3.4.1, 3.7.6, and 3.7.8 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 MOPR limits for all fuel types (ATRIUM TM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOO to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOO to EOC c) EOC-RPT Inoperable Figure 5.2-5: Flow-Dependent MCPR value determined from BOO to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOO to EOC d) Backup Pressure Regulator Inoperable Figure 5.2-7: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-8: Power Dependent MCPR value determined from BOO to EOC The MCPR limits in Figures 5.2-1 through 5.2-8 are valid for Two Loop operation.
The MCPR limits for Single Loop operation are provided in Section 8.0.
SUSQUEHANNA UNIT 2 TRMI3.2-10 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 10 of 55 5.3 Average Scram Time Fraction If the average measured scram times are greater than the Realistic Scram times listed in Table 5.3-1 then the MCPR operating limits corresponding to the Maximum Allowable Average Scram Insertion Time must be implemented.
Determining MCPR operating limits based on interpolation between scram insertion times is not permitted. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.
SUSQUEHANNA UNIT 2 TRM/3.2-11 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 11 of 55 Main Turbine Bypass / EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM/3.2-12 EFFECTIVE DATE 412512013
(A (A SSES UNIT 2 CYCLE 17 2.2 1 - I- I I LEGEND 2.1 - CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM
-4 INSERTION TIME
-I N) 2.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME
.. I . I -I I 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
_ _I I I 1.8 USED IN DETERMINING MFLCPR J"_ -0 t-
"* 1.7 0
- 0. M CA) I.
o 1.6 1.5 C-) 1.4 m
REFERENCE:
T.S. 3.2.2 1.3 m
1.2 03 CD 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) CD MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW c~n w MAIN TURBINE BYPASS i EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIG URE 5.2-1
CA SSES UNIT 2 CYCLE 17 C=
N)
-o
'U 1~
C-t ci) a)-
0 0~
CA)
C-)
C)
P1 0i m
20 30 40 50 60 70 80 90 100 Core Power (% RATED)
N)
MCPR OPERATING LIMIT VERSUS CORE POWER I-.
W.
MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-2
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 14 of 55 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRMI3.2-15 EFFECTIVE DATE 4/25/2013
(A (I:) SSES UNIT 2 CYCLE 17" 2.2 LEG END 2.1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REAUSTIC AVERAGE SCRAM INSERTION TIME Na 2.0 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 1.9 F30.-.7-1 SED INDETERMINN!G.MF'OPR 1.8 S
1.7 -0 (D
0) 0 1.6 1.5 30F1E79 31
-n 1.4 rn
REFERENCE:
_T.S. 3.7.6 and 3.2.2 _____
1.3 1.2 W~ CD I 30 40 50 60 70 80 910 100 110 N) Total Core Flow (MLB/HR) CD Z
-n NO MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE 031 0)
C." W TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-3
(A (A SSES UNIT 2 CYCLE 17 nfl 3.6
-H
'0
-4l CD 0.
W m
C-I m
-0.
i)CD I;-
20 30 40 50 60 70 80 90 100 CD Z Core Power (% RATED)
- 0) --%
.0 MCPR OPERATING UMIT VERSUS CORE POWER h C)
MAIN TURBINE BYPASS INOPERABLE cn CA)
TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-4
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 17 of 55 0
EOC-RPT Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-18 EFFECTIVE DATE 4/25/2013
(A SSES UNIT 2 CYCLE 17 2.2 C=
2.1 ND3 2.0 1.9 E
1.8 0,.
-o (D
CD 1.7 0
0 ILI a.
C., 1.6 1.5 rn CD m 1.4 00 m 1.3 m
1.2 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) 0UJ-S C),I MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-5
C/)
SSES UNIT 2 CYCLE 17 CA 2d
-H CAo 02 CD m
C-)
20 30 40 50 60 70 80 90 100
-A0 Il Core Power (% RATED) CDZ N)
CD1 (0 SO N,- MCPR OPERATING LIMIT VERSUS CORE POWER W. EOC-RPT INOPERABLE h~ 0 CA CA)
TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-6
PPL Rev. 10 PL-NF-1 3-003 Rev. 0 Page 20 of 55 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 4/25/2013
V)
C= SSES UNIT 2 CYCLE 17 m 2.2 1 I I .....
LEGEND 2.1 'CURVE A- MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME 2.0 _ -CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 1.9 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 E
1.8 USED IN DETERMINING MFLCPRJ r-"
C., 1.7 (D 0 0) 1.6 1.5 1.4
-n
IREFERENCE:
T.S. 3.7-8 and 3.2.21 1.3 108,1.21 rn 1.2 mn W) CD i;-
30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR) CD Z1 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW -0 BACKUP PRESSURE REGULATOR INOPERABLE cn cý TWO LOOP OPERATION (BOC TO EOC)
FIGURE 5.2-7
Z/)
(A SSES UNIT 2 CYCLE 17 3.6 E
-I C~3 CL 0
m,
- 0-0 m
Phl 71, 20 30 40 50 60 70 80 90 100 Core Power (% RATED)
- ". z 4I.
o -n MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE 0~C)
TWO LOOP OPERATION (BOC to EOC)
FIGURE 5.2-8
PPL Rev. 10 PL-NF-1 3-003 Rev. 0 Page 23 of 55 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 0.520 39 0.630 0.860 25 1.500 1.910 5 2.700 3.440 Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TPM/3.2-24 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 24 of 55 6.0 LINEAR HEAT GENERATION RATE (LHGRI 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The maximum LHGR for ATRIUMTM-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1. The LHGR limit in Figure 6.2-1 is valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.
To protect against both fuel centerline melting and cladding strain during anticipated system transients initiated from reduced power and flow conditions, power and flow dependent LHGR limit multipliers are provided.
The flow dependent LHGR limit multiplier figures are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable:
a) Flow Dependent Main Turbine Bypass.Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier b) Flow Dependent Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier The power dependent LHGR limit multiplier figures are applicable to:
a) Power Dependent Main Turbine Bypass and EOC-RPT, and Backup Pressure Regulator Operable Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Power Dependent Main Turbine Bypass or EOC-RPT or Backup Pressure Regulator Inoperable Figure 6.2-5: Power-Dependent LHGR Limit Multiplier The LGHR limit and LHGR limit multipliers in Figures 6.2-1 through 6.2-5 are valid for both Two Loop and Single Loop operation.
SUSQUEHANNA UNIT 2 TRM/3.2-25 EFFECTIVE DATE 4/25/2013
- Vn SSES UNIT 2 CYCLE 17 16.0
ll'11111 a liiill 1:113l.
N) = = ', , * , "' " ", ". . . . w 14.0 4-4. 18900, 1&3A -[ 4 II
REFERENCE:
T.S. 3.2.3
-i l l lll4It 4l4 I I.4 '
A, I
1=1USED I
IN DETERMINING FDLRX 3gll 3 i I
12.0 i l l I l +l l - I I -I I I I t I II
-a l1311 3l i$ 1 i l aI l I , 1l 1l i. l ~ l l l 0 1... 11 111 0 -D C
I I I I I
.II I I I I . I Il I l. . I lI l. l---ll l --
-o 0 L I I I I I IlIlIl ll l 0 10.0 CD 0 5 C -3.
0 0 013 C,
-p Cu 0
S II I3 III 3 31 3 I I I l I-0 8.0 0
C
-J rn
-n m
rn C-,
-I 6.0 C
m C 9-t 1 11 I .
-H I 1 I 3 31 : 1 s m 4.0 S- - -. t . I . . . . .
0 10000 20000 30000 40000 50000 60000 70000 80000 oD r N) Pellet Exposure (MWDIMTU)
(a, 0*
N) 0 LINEAR HEAT GENERATION RATE LIMIT VERSUS PELLET EXPOSURE h C)
I.
'-3, ATRJUMTr-10 FUEL cy 0 (n wj FIGURE 6.2-1
PPL Rev. 10 PL-NF-1 3-003 Rev. 0 Page 26 of 55 Flow Dependent Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-27 EFFECTIVE DATE 4/25/2013
c-fl a
c-fl C
SSES UNIT 2 CYCLE 17 a
rn 1.10 I I I i I I 3 I I i S I I I i I I I I I I I I I I I I I I i i i I i Ii i i iI I
- I I I I i l I i I I I I I I =I IkII I I I
I 181),1.00' W I a I i a 1.00 l I b*. r Losi 2I221
-4 T if 4 1l - ii r
,I ,4 . , .. $
0.90 I
- IL I I I I S I n
- I I 1 *
- I I , I I I - v J . w
- , I I I I , SAETI ANLYE I ASUM I , THA *.. FOU , BYAS IVALVES-l. I 0.80 I l
I I
I I
I I
I I
I I
i i
I I I l I I I
- I I
I I
I I I+ I l I I I l I I I u "0
CD S
i i _ _ _ _ _ i I_ J I "-"
- 0.70 +--'-
-- - -- --. '-------'-L+--t' .. -- + . .
..3 i 4 i i 4 1 i i i S0.60 i i-i- t i i i i i 0.50
REFERENCE:
T..3.2.3 ad3.7.6 cm m ( 0 C-)
USED IN DETERMUINING FDLRX 0.40 cm C)
P1 cc 0.30 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/hr)
N) 01 FLOW DEPENDENT LHGR LIMIT MULTIPLIER wO MAIN TURBINE BYPASS OPERABLE Z CD ATRIUMTM-10 FUEL FIGURE 6.2-2
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 28 of 55 Flow Dependent Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-29 EFFECTIVE DATE 4/25/2013
SSES UNIT 2 CYCLE 17 1.10 C=
1.00 N) 0.90 s-0.80
--q (-
(D V 0.70 06 0 03
- a. 0.60 7-0 Nz) 0.50 m 0.40
-n
-C= *0.30 0
- )
30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) CO --
FLOW DEPENDENT LHGR LIMIT MULTIPUER MAIN TURBINE BYPASS INOPERABLE 01 0*
ATR[UMTm-10 FUEL FIGURE 6.2-4
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 30 of 55 Power Dependent Main Turbine Bypass and EOC-RPT and Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TRM/3.2-31 EFFECTIVE DATE 4/2512013
SSES UNIT 2 CYCLE 17 1.10 C=
-0
-J N) 0 0
0 m I-
-n
-n 0
-r-%
N) 20 30 40 50 60 70 80 90 100 I-- Core Power (% RATED)
P1 (0
POWER DEPENDENT LHGR LIMIT MULTIPLIER CD Z MAIN TURBINE BYPASS AND EOC-RPT AND BACKUP PRESSURE REGULATOR OPERABLE ATRIUMu-10 FUEL FIGURE 6.2-3
PPL Rev. 10 PL-NF-1 3-003 Rev. 0 Page 32 of 55 Power Dependent Main Turbine Bypass or EOC-RPT or Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-33 EFFECTIVE DATE 4/25/2013
Cn m,
SSES UNIT 2 CYCLE 17 1.10 C=
[I
-D CL N) 03 Q 0 IL m~
m rni Lrn -0 20 30 40 50 60 70 80 90 100 CD W Core Power (% RATED)
C;)
POWER DEPENDENT LHGR LIMIT MULTIPLIER 07 CA MAIN TURBINE BYPASS OR EOC-RPT OR (J1 BACKUP PRESSURE REGULATOR INOPERABLE ATRIUMIM-L.10 FUEL FIGURE 6.2-5
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 34 of 55 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS 7.1 Technical Specification Reference Technical Specification 3.3.2.1 7.2 Description The RBM Allowable Value and Trip Setpoints for; a) Low Power Range Setpoint, b) Intermediate Power Range Setpoint, c) High Power Range Setpoint, e) Low Power Range - Upscale, f) Intermediate Power Range - Upscale, and g) High Power Range - Upscale shall be established as specified in Table 7.2-1. The RBM setpoints are valid for Two Loop and Single Loop Operation, Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.
The RBM system design objective is to block erroneous control rod withdrawal initiated by the operator before fuel design limits are violated. If the full withdrawal of any control rod would not violate a fuel design limit, then the RBM system is not required to be operable. Table 7.2-2 provides RBM system operability requirements to ensure that fuel design limits are not violated.
SUSQUEHANNA UNIT 2 TPM/3.2-35 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 35 of 55 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value~') Setpoint Low Power Range Setpoint 28.0 24.9 Intermediate Power Range Setpoint 63.0 61.0 High Power Range Setpoint 83.0 81.0 Low Power Range - Upscale 123.4 123.0 Intermediate Power Range - Upscale 117.4 117.0 High Power Range - Upscale 107.6 107.2
( Power setpoint function (Low, Intermediate, and High Power Range Setpoints) determined in percent of rated thermal power. Upscale trip setpoint function (Low, Intermediate, and High Power Range - Upscale) determined in percent of reference level.
Table 7.2-2 RBM System Operability Requirements Thermal Power MCPR (2,3)
(% of Rated)
> 28 and < 90 < 1.76
>90 and < 95 < 1.47
> 95 < 1.68 (2) Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.
) Applicable to both Two Loop and Single Loop Operation.
SUSQUEHANNA UNIT 2 TRM/3.2-36 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 36 of 55 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, 3.7.6, and 3.7.8 8.2 Description APLHGR The APLHGR limit for ATRIUMTM-10 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.
The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator 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 limits for all fuel types (ATRIUMTM-10) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.
a) Main Turbine Bypass / EOC-RPT / Backup Pressure Regulator Operable Figure 8.2-2: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-3: Power-Dependent MCPR value determined from BOC to EOC b) Main Turbine Bypass Inoperable Figure 8.2-4: Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOG to EOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOG to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOG to EOC d) Backup Pressure Regulator Inoperable Figure 8.2-8: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-9: Power-Dependent MCPR value determined from-BOC to EOC SUSQUEHANNA UNIT 2 TRM/3.2- 37 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-1 3-003 Rev. 0 Page 37 of 55 The MCPR limits in Figures 8.2-2 through 8.2-9 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.
RBM Setpoints and Operability Requirements The RBM setpoints and operability requirements for Single Loop Operation are defined in Section 7.0.
SUSQUEHANNA UNIT 2 TRr4/3.2-38 EFFECTIVE DATE 4/25/2013
GO a
CA C
SSES UNIT 2 CYCLE 17 a 16.0 rn
= & I I I IIII II I l I I I 1I 1 I a 1I5I I I I I I I I I I a a a a I a a1 I I I I a I I Il a al Il a I I ClI ,lC 1 1 1 C I C I C I J C I 1C I tl al a I I I I I l IC lI II I l C I I C I I I I I II I IlI"I I I I I I I II II I II CI a I II a C CI C I C II, C I IIREFRENCE T.S. 3.4.1 and 3.2.1 I
-4 14.0 N)
- t itt l& I i Jf I I l t l S
USED IN DETERMINING MAPRAT
- ii 1+ l1 t t1l11 C. C I 12.0 CII II IIIN I I I Ii --- ~
P4 ~ l l 41i lF-a--.r.f--- I * +/- 1 I. -I " 1
-4 C I I l I I. a I a a l l I I I I I I
- l 0010 1110Soo *. I CA, M=10.0 (D N) I $ I I l lIl l l l , l l l l l I I I CA) 0 I II 1.3 I I
- 8.0 co SJ m
C-) 6.0
-4q I lI , I
--- 67000, 5.I rn 4.0 0 ;0 r0 0.0 10000.0 20000.0 30000.0 40000.0 50000.0 60000.0 70000.0 Average Planar Exposure (MWDIMTU)
AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS co 9.
CA)
AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION CA (n
ATRIUMTM-10 FUEL FIGURE 8.2-1 e
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 39 of 55 Main Turbine Bypass / EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 2 TIM/3.2-40 EFFECTIVE DATE 4/25/2013
(Ai SSES UNIT 2 CYCLE 17 3.6 3.4 3.2 3.0 2.8
" 2.6 CD O 2.4 2.
E2.2 2.0 1.8 07 rn
-4 1.6 1.4 r-0 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) (0 NO MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS / EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE CAt SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-2
SSES UNIT 2 CYCLE 17 4.6
_LEGEND 4.4
_-I CURVE A. MAXIMUM ALLOWABLE AVERAGE SCRAM 4.2 INSERTION TIME 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.8 CURVE C: CORE POWER <26% AND CORE FLOW 50 MLBMIHR 123. 3. ST 23,3.41 3.4 C 26, 3 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 26, 3.33ARE 26D*,3.33,I OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 3.2 I-0= CD 3.0 _USED IN DETERMINING MFLCPR
- 0. 0b NO) o-0= 2.8 2.6 2.4 126.01, 2.32M 2.2 + ~- 4 .I-;.~
2.02
-vi *1 i - I.
-vi vii 2.0
__B 601.90r I I t i10-0, 9. 1 C-.,
-I I 4 4 4 1.8 1.6
REFERENCE:
T.S. 3.4.1 and 3.2.2_
-I ni 1.4 WDCD I;-
20 30 40 50 60 70 80 90 100 to <
IN) Core Power (%RATED) CD -Z U, cý71 IN) MCPR OPERATING LIMIT VERSUS CORE POWER 0~
MAIN TURBINE BYPASS / EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE 0 SINGLE LOOP OPERATION (BOC to EOC) cai FIG URE 8.2-3
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 42 of 55 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 2 TRMI3.2- 43 EFFECTIVE DATE 4/25/2013
SSES UNIT 2 CYCLE 17 71 4.2 LEGEND m 4.0 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.8 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.6 3.4 3.2 -SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 t!
3.0 -0
.-4 r-USED IN DETERMINING MFLCPR C0 rGj 2.8 0
0 2.6 2.4 2.2 2.0 m
1.8 R'lEFERENCE
T.S. 3.4.1, 3.7.6, ,an3.2.2 --- ___
II 1.6 1.4 30 40 50 60 70 80 90 100 110 0 CD I Total Core Flow (MLBIHR)
CA MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-4
0 SSES UNIT 2 CYCLE 17 m
N)
E G')
.-L X-CD 0
Ila, It m
03<
20 30 40 50 60 70 80 90 100 Core Power (%RATED) CD Z 4511 N)
MCPR OPERATING LIMIT VERSUS CORE POWER h~ -
MAIN TURBINE BYPASS INOPERABLE C.0 SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-5
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 45 of 55 EOC-RPT Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-46 EFFECTIVE DATE 4/25/2013
ýC, SSES UNIT 2 CYCLE 17 I" 4.0 LEGEND 3.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 3.6 INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.4 3.2 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES E 3.0 ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2
-4 z 2.8 USED IN DETERMINING MFLCPR C.,
N, 0.
2.6
-4 2.4 2.2 2.0
-n 1.8 PA--
m 1.6
REFERENCE:
T.S. 3.4.1, 3.3.4.1, and 3.2. ____ 0,14
-4 1 .. --. I 1.4 I .
I______________ 1 1 30 40 50 60 70 80 9I0 100 110 Total Core Flow (MLBJHR) CD z MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-6
V)
(Ai SSES UNIT 2 CYCLE 17 4.6 E
3!
-4 C.,
0 0
I-C, I-6 0 i rm ft 0 m
20 30 40 060 (% RATED) 70 Core Power 80 90 100 0,ý CA0 C., MCPR OPERATING LIMIT VERSUS CORE POWER (0 CA)
EOC-RPT INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-7
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 48 of 55 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 2 TRM/3.2-49 EFFECTIVE DATE 4/25/2013
(A (A SSES UNIT 2 CYCLE 17 m 4.0 3.8 cz I. 3.6 3.4 3.2 3.0
.2 ~0
-D 2.8 I-CA)
- 0 a- 0 0L 2.6 (A 0 2.4 2.2 m 2.0 1.8 1.6 m
1.4 ;0 r--
30 40 50 60 70 80 90 100 110 CD 5 z,n iN) Total Core Flow (MLBIHR) 0 MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW 0o CA) cA 0ý BACKUP PRESSURE REGULATOR INOPERABLE cm WJ SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-8
L/I C=
SSES UNIT 2 CYCLE 17 r'3 E
.j 0.
C,-
CD m
-ri 20 30 40 50 6o 70 80 90 100 Core Power (% RATED) CA W
MCPR OPERATING LIMIT VERSUS CORE POWER BACKUP PRESSURE REGULATOR INOPERABLE SINGLE LOOP OPERATION (BOC to EOC)
FIGURE 8.2-9
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 51 of 55 9.0 POWER / FLOW MAP 9.1 Technical Specification Reference Technical Specification 3.3.1.1 9.2 Description Monitor reactor conditions to maintain THERMAL POWER I core flow outside of Stability Regions I and II of the Power! Flow map, Figure 9.1.
if the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power / Flow map is considered an immediate exit region.
If the OPRM Instrumentation is inoperable per TS 3.3.1.1, Region I of the Power I Flow map is considered an immediate scram region.
Region II of the Power / Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.
SUSQUEHANNA UNIT 2 TRM/3.2-52 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-1 3-003 Rev. 0 Page 52 of 55
... .. ... .. I I ý ý . . 1 . I .
,======,i- 120 120 UNIT 2 120 POWER I FLOW MAP APRM Scram 110 TFIpSetpoint 110 T- Up 8Rod Block l
--- tpoint Int 100 MELLLA 100
- - - - Boundary 7-1 90 80 80 I
70 70 10 L_
60 60 41) 50 50 40 40 30 30 20 20 10 0 4- 0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mlbmlhr)
(for SLO <75% Pump Speed Use Form GO-200-009-2)
Figure 9.1 SSES Unit 2 Cycle 17 Power / Flow Map SUSQUI -HANNA UNIT 2 TRM/3.2-53 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 53 of 55 10.0 OPRM SETPOINTS 10.1 Technical Specification Reference Technical Specification 3.3.1.1 10.2 Description Setpoints for the OPRM Instrumentation are established that will reliably detect and suppress anticipated stability related power oscillations while providing a high degree of confidence that the MCPR Safety limit is not violated. The setpoints are described in Section 2.0 and are listed below:
Sp - 1.12
= 16 Fp 6MIbm /hr 60 SUSQUEHANNA UNIT 2 TRMf/3.2-54 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 54 of 55
11.0 REFERENCES
11.1 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. XN-NF-81-58(P)(A), Revision 2 and Supplements 1 and 2, URODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model," Exxon Nuclear Company, March 1984.
- 2. EMF-2361(P)(A), Revision 0, "EXEM BWR-2000 ECCS Evaluation Model,"
Framatome ANP, May 2001.
- 3. EMF-2292(P)(A), Revision 0, "ATRIUM TM-1 0: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.
- 4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements I and 2, "XCOBRA-T: A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis," Exxon Nuclear Company, February 1987.
- 5. XN-NF-80-19(P)(A), Volume I and Supplements 1 and 2, "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, March 1983.
- 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," Exxon Nuclear Company, 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," Exxon Nuclear Company, January 1987.
- 8. XN-NF-80-1 9(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, 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 Supplements I and 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 2 TRM/3.2-55 EFFECTIVE DATE 4/25/2013
PPL Rev. 10 PL-NF-13-003 Rev. 0 Page 55 of 55
- 12. ANF-89-98(P)(A) Revision 1 and Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.
- 13. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.
- 14. EMF-85-74(P)(A), Revision 0, Supplement I(P)(A) and Supplement 2(P)(A),
"RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model,"
Siemens Power Corporation, February 1998.
- 15. 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.
- 16. EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis -
Assessment of STAIF with Input from MICROBURN-B2," Siemens Power Corporation, August 2000.
- 17. NEDO-32465-A, "BWROG Reactor Core Stability Detect and Suppress Solutions Licensing Basis Methodology for Reload Applications," August 1996.
- 18. ANF-913(P)(A), Volume 1 Revision I and Volume 1 Supplements 2, 3, and 4, "COTRANSA2: A Computer Program for Boiling Water Reactor Transient Analyses," Advanced Nuclear Fuels Corporation, August 1990.
- 19. ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," Framatome ANP, September 2005.
SUSQUEHANNA UNIT 2 TRM/3.2-56 EFFECTIVE DATE 4/25/2013