Text

Submittal of Cycle 19 Core Operating Limits Report
	ML14107A375
Person / Time
Site:	Susquehanna
Issue date:	04/17/2014
From:	Franke J; Susquehanna
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	PLA-7153
	Download: ML14107A375 (55)
	v • d • e

Jon A. Franke PPL Susquehanna, LLC Site Vice President 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 jfranke@pplweb.com U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION SUBMITTAL OF UNIT 1 CYCLE 19 CORE OPERATING LIMITS REPORT (COLR)

PLA-7153 Docket No. 50-387 Technical Specification Section 5.6.5 requires that the Core Operating Limits Report (COLR), including any mid-cycle supplements or revisions, be provided upon issuance to the NRC in accordance with 10 CFR 50.4. In compliance with this requirement, the Unit 1 Cycle 19 COLR is provided in the attachment to this letter.

If you should have any questions regarding this submittal, please contact Mr. John Tripoli at (570) 542-3100.

ry commitments identified in this letter.

Unit 1 Cycle 19 COLR Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PA DEP/BRP

Attachment to PLA-7153 Unit 1 Cycle 19 COLR

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 1 of 53 Susquehanna SES Unit 1 Cycle 19

-CORE OPERATING REPORT LIMITS Nuclear Fuels Engineering April2014

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SUSQUEHANNA UNIT 1 TRM/3.2-2 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 2 of 53 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev. Affected No. Sections Description/Purpose of Revision 0 ALL Issuance of this COLR is in support of Unit 1 Cycle 19 operation.

FORM NFP-QA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 3 of 53 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 19 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) ............................................................. 24 7.0 ROD BLOCK MONITOR (RBM) SETPOINTS AND OPERABILITY REQUIREMENTS ....................................................................................................... 32 8.0 RECIRCULATION LOOPS- SINGLE LOOP OPERATION ......................................... 34 9.0 POWER I FLOW MAP ................................................................................................ .49 10.0 OPRM SETPOINTS .................................................................................................... 51

11.0 REFERENCES

............................................................................................................ 52 SUSQUEHANNA UNIT 1 TRM/3.2-4 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 4 of 53

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 19 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, 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 1 TRM/3.2-5 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev.O Page 5 of 53 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 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 LHGRFAC 1 is a multiplier applied to the LHGR limit when operating at less than 108 Mlbm/hr core flow. The LHGRFAC 1 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 LHGRFACp is a multiplier applied to the LHGR limit when operating at less than 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 F P is the core flow, in Mlbm I hr, below which the OPRM RPS trip is activated.

SUSQUEHANNA UNIT 1 TRM/3.2-6 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 6 of 53 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% ~k/k with the highest worth rod analytically determined b) 0.28% ~klk 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 "R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOC measured value is required.

The SHUTDOWN MARGIN limits provided in 3.2a and 3.2b are applicable in MODES 1, 2, 3, 4, and 5. This includes core shuffling.

SUSQUEHANNA UNIT 1 TRM/3.2-7 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 7 of 53 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 ATRIUM'-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 1 TRM/3.2-8 EFFECTIVE DATE 4/17/2014

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PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 9 of 53 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 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 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) Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator 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 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 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 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 BOC 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 1 TRM/3.2-10 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev.O Page 10 of 53 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 1 TRM/3.2-11 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 11 of 53 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-12 EFFECTIVE DATE 4/17/2014

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PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 14 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-15 EFFECTIVE DATE 4/17/2014

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PPL Rev. 14 PL-NF-14-001 Rev.O Page 17 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-18 EFFECTIVE DATE 4/17/2014

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e..

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 I

-1 :J 1.8 USED IN DETERMINING MFLCPR

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TWO LOOP OPERATION (BOC TO EOC) OCDf" FIGURE 5.2-5 -

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e

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=

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(Q rI MCPR OPERATING LIMIT VERSUS CORE POWER CD z "Tl EOC-RPT INOPERABLE -" I

<D:;:o-"

TWO LOOP OPERATION (BOC to EOC) oCDf" FIGURE 5.2-6 -<0 c.n* 0 VJ 0 -"

PPL Rev. 14 PL-NF-14-001 Rev.O Page 20 of 53 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-21 EFFECTIVE DATE 4/17/2014

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(0 rI MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD z BACKUP PRESSURE REGULATOR INOPERABLE N 71 TWO LOOP OPERATION (BOC TO EOC) """"::::o""""

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\

.... -c- ~ 26, 2.811

e

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o C) 3

s: :: ARE OPERABLE PERSR3.7.6.1 AND 3.7.6.2

--...... *- 26.01' 2.41

~ ~ '"'0

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= ..........

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'-J N

=

I--'

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(Q r I MCPR OPERATING LIMIT VERSUS CORE POWER CD z BACKUP PRESSURE REGULATOR INOPERABLE N N:;:u_,

"Jl TWO LOOP OPERATION (BOC to EOC) oCDf" FIGURE 5.2-8 -

(J1.

<00 VJ 0 ....>.

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 23 of 53 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 1 TRM/3.2-24 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 24 of 53 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3, 3.3.4.1, 3.7.6, and 3.7.8 6.2 Description The maximum LHGR for ATRIUM'-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 following figures are applicable to EOC-RPT Operable and Inoperable and Backup Pressure Regulator Operable and Inoperable:

a) Main Turbine Bypass Operable Figure 6.2-2: Flow-Dependent LHGR Limit Multiplier Figure 6.2-3: Power-Dependent LHGR Limit Multiplier b) Main Turbine Bypass Inoperable Figure 6.2-4: Flow-Dependent LHGR Limit Multiplier 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 1 TRM/3.2-25 EFFECTIVE DATE 4/17/2014

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PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 26 of 53 Main Turbine Bypass Operable SUSQUEHANNA UNIT 1 TRM/3.2-27 EFFECTIVE DATE 4/17/2014

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PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 29 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-30 EFFECTIVE DATE 4/17/2014

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PPL Rev. 14 PL-NF-14-001 Rev.O Page 32 of 53 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, d) Low Power Range - Upscale, e) Intermediate Power Range- Upscale, and f) 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 1 TRM/3.2-33 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 33 of 53 Table 7.2-1 RBM Setpoints Allowable Nominal Trip Function Value< 1> 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 (1)

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 < 1.70 (2)

Applicable to Main Turbine Bypass Operable and Inoperable, EOC-RPT Operable and Inoperable, and Backup Pressure Regulator Operable and Inoperable.

(3)

Applicable to both Two Loop and Single Loop Operation.

SUSQUEHANNA UNIT 1 TRM/3.2-34 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 34 of 53 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 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, 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 (ATRIUM'-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 I EOC-RPT I 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 BOC to EOC Figure 8.2-5: Power-Dependent MCPR value determined from BOC to EOC c) EOC-RPT Inoperable Figure 8.2-6: Flow-Dependent MCPR value determined from BOC to EOC Figure 8.2-7: Power-Dependent MCPR value determined from BOC 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 1 TRM/3.2-35 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev.O Page 35 of 53 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 1 TRM/3.2-36 EFFECTIVE DATE 4/17/2014

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PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 37 of 53 Main Turbine Bypass I EOC-RPT I Backup Pressure Regulator Operable SUSQUEHANNA UNIT 1 TRM/3.2-38 EFFECTIVE DATE 4/17/2014

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2: 2.6 rrl I 26.01, 2.40 I

'l 2.4

'l rrl

()

-I 2.2

............... 140,2.081 f--i

< ............... 8 rrl A 60, 1.921 1100, 1.921 CJ 2.0

)>

-I rrl 1.8 0

_J::,.

1 --'

---._J N

0 1.6 1.4 Q

REFERENCE:

T.S. 3.4.1 and 3.2.21 I I 1--'

_J::,. 20 30 40 50 60 70 80 90 100 Core Power(% RATED)

"'0 "'0 m

(0 rI MCPR OPERATING LIMIT VERSUS CORE POWER CD z MAIN TURBINE BYPASS I EOC-RPT I BACKUP PRESSURE REGULATOR OPERABLE (;,) 71 SINGLE LOOP OPERATION (BOC to EOC) C.O;::o-"

oCDf" FIGURE 8.2-3 - <0

(]1* 0

(;,) 0--"

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 40 of 53 Main Turbine Bypass Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-41 EFFECTIVE DATE 4/17/2014

(/)

SSES UNIT 1 CYCLE 19 c

(/) 4.2 D I I I c

rr1 LEGEND I

)> 4.0 -

z::

z:: CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM

)>

3.8 INSERTION TIME 1---

c

z::

f---4

---1 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.6 r--

I-'

3.4

.... 3.2 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS -

e VALVES ARE INOPERABLE PERSR3.7.6.1 OR3.7.6.2

---1 :.::i

a

s: Cl 3.0 s::

w :;::; "'0 N

CIS Q) 2.8 I USED IN DETERMINING MFLCPR "'0 r

I

-I'>

c. :::0 N 0 CD 0:::: 2.6 <

0.. ....>.

(..) .j:>..

2 2.4 rr1

'l 130, 2.181

'l rr1 n 2.2

---1 f---4

< A rr1 2.0 8 CJ

~

rr1 1.8 H

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.2 J 1108, 1.65

=

-I'>

I -'

'--._J 1.6 I I I -

N

=

I-'

-I'>

1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR)

"'0 "'0 m

(Q r I MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD z MAIN TURBINE BYPASS INOPERABLE .j:>.. 71

__,:::0-->.

SINGLE LOOP OPERATION (BOC to EOC) oro~

FIGURE 8.2-4 -<0

01. 0 VJO....>.

(/)

SSES UNIT 1 CYCLE 19 c j23,4.14l

(/) 4.2 D

c \ LEGEND fTl I

)>

z 4.0 \ ~

z

)>

\ CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME f---

c z

1---<

--1 1---'

3.8 123, 3.61

' _126, 3.811 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME r--

r--

3.6 CURVE C: CORE POWER~ 26% AND CORE FLOW~ 50 MLBM/HR -

\ -

3.4 -C~ M26, 3.381 I I I I E SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS

--1 ::i

a 3

: C) 3.2 VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 -

c w :;:::; ""'0

~

c N

""'0 Q) 3.0 r I

_p,. c.. USED IN DETERMINING MFLCPR :::0 w 0 CD 0::: <

a.. 2.8 ....>.

(.)

.j:::.

2:

fTl

'l 2.6

'l 126.01' 2.451 fTl n

--1 2.4 1---< .......

fTl .......... ~140,2.131 CJ

)> 2.2

--1 ............. 1---.

fTl A-s

=

_p,.

1---'

--...J N

2.0

REFERENCE:

T.S. 3.4.1, 3.7.6, and 3.2.21

---t::----_ t60, 1.98t I

100, 1.981 I

=

1---'

_p,.

1.8 20 30 40 50 60 70 80 90 100 Core Power(% RATED)

""'0 ""'0 w

(0 rI MCPR OPERATING LIMIT VERSUS CORE POWER CD z MAIN TURBINE BYPASS INOPERABLE .j:::. 71 SINGLE LOOP OPERATION (BOC to EOC) I'V;:o-"

oCDf" FIGURE 8.2-5 -<0

(]1. 0 VJ 0 ....>.

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 43 of 53 EOC-RPT Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-44 EFFECTIVE DATE 4/17/2014

(/)

SSES UNIT 1 CYCLE 19 c

(/) 4.0 D

c ITl

c LEGEND

)> 3.8 -

z z CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM

)>

c 3.6 INSERTION TIME -

z

-l CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f--' 3.4 r-3.2 1 L

......E 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3. 7 .6.1 AND 3. 7 .6.2 -

-l :::i

0

s C) s::::

w

:;::; 2.8 USED IN DETERMINING MFLCPR \J N E Q)

I I \J r

I

+:> a. ;a (Jl 0 2.6 CD 0::: <

a.. ....>.

()

.f:>.

2: 2.4 ITl

'l

'l 2.2 ITl

()

-l

< 2.0 ~30, 1.921 ITl CJ

)> A

-l 1.8 8 ITl

=

+:>

1.6

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.21 108, 1.49 f--'

'-.J N

=

f--'

1.4

+:> 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) \J \J w

(0 rI MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD z EOC-RPT INOPERABLE .f:>.

.f:>.;o_,

71 SINGLE LOOP OPERATION (BOC to EOC) oCDf" FIGURE 8.2-6 -

()1.

<0 0 c..v 0 ...>.

(/)

SSES UNIT 1 CYCLE 19 c:

(/) 4.6 D

c:

[T1 I 4.4 LEGEND -

)>

z z

)> 4.2 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM -

c: INSERTION TIME -

z

-I 4.0 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f--

f---'

3.8 U23, 3.721

.. CURVE C: CORE POWER::; 26% AND CORE FLOW::; 50 MLBM/HR f--

r-

e

~f\

123, 3.61 I\\.

3.4 126,3.561 I--

r-

-I

Q

J - c - ~26, 3.38 1 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES 1--

3: C) s::: 3.2 - ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1--

w :;:::;

....ca 1-- '1J

'1J N Q) 3.0 r I

a.

..j:::>

0> 0 a:::

a.

()

2.8 USED IN DETERMINING MFLCPR t= ::0 CD

.j:>.

2 2.6

[T1 26.01, 2.40

'l

'l 2.4

[T1 ...............

()

-I 2.2

............... 140,2.08

[T1 1100,1.921 2.0 16o, 1.921 A 8 CJ

~

[T1 1.8

=..j:::> -i

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.21 f---' 1.6

-...__j N

= 1_.4 f--'

..j:::> 20 30 40 50 60 70 80 90 100 Core Power(% RATED)

'1J '1J ru r (Q I MCPR OPERATING LIMIT VERSUS CORE POWER CD z EOC-RPT INOPERABLE .j:>. 71 SINGLE LOOP OPERATION (BOC to EOC) CJ1;:o"""

oCDf" FIGURE 8.2-7 -

(J1.

<00 VJ 0"""

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 46 of 53 Backup Pressure Regulator Inoperable SUSQUEHANNA UNIT 1 TRM/3.2-47 EFFECTIVE DATE 4/17/2014

(/)

SSES UNIT 1 CYCLE 19 c::

(/) 4.0 D

c::

fTl

r:: LEGEND

)> 3.8 1--

z z

)> CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM c::

z 3.6 INSERTION TIME -

I-<

-1 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f----' 3.4 f--

I I I 3.2 i-

-1

o

e

.::i 3.0 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 1---

s: C'l USED IN DETERMINING MFLCPR s:::

w :;::;

Ill

....Q) 2.8 ""0

""0 N r I

+::> c. :::0 CD 0 2.6 CD c::: :<

a.. ....>.

(.) .j::>.

2: 2.4 fTl

'l

'l 2.2 fTl n

-1 I-<

< 2.0 J30, 1.921 fTl 1--.

0

~ 1.8 A fTl 8

=

+::>

1.6 j

REFERENCE:

T.S. 3.4.1, 3.7.8, and 3.2.21 1108, 1.491 f----'

---..J N

=

f----'

+::>

1.4 30 40 50 60 70 80 90 100 110 Total Core Flow (MLB/HR) ""0 ""0 m

(Q rI MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW CD z

.j::>. 71 BACKUP PRESSURE REGULATOR INOPERABLE -...J:;o-"

SINGLE LOOP OPERATION (BOC to EOC) oCDf"

()1.

<00 FIGURE 8.2-8 (,.,) 0 ....>.

(/)

SSES UNIT 1 CYCLE 19 c:

(/) 4.6 D

c:

Ill I

)>

4.4 ~------~------~~~LEGEND

z:

)> 4.2 1 - - - - - - - + - - - - - + - - 1 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM c:

INSERTION TIME

z:

---1 4.0 h23,3.72 I I I ICURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME f--'

38

~

l;; ~

! I I CURVE C: CORE POWER< 26% AND CORE FLOW< 50 MLBMIHR

---1

o

':t Ec ?11 j23, 3.611 3.4 126,3.561 26, 3.38 I I II I I I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES I d

3.2

---..._ ARE OPERABLE PER SR 3. 7 .6.1 AND 3. 7 .6.2 w ""'0 126.01, 2.9ol ""'0 N

I

!::::: 3.0 r E

+:>

<..0 ::i Cl s::

2.8

""' ~

140,2.611 USED IN DETERMINING MFLCPR c= ::::0 CD

.j

: >.

IV Q) 2.6 a.

I I I Ill

'l 0 2.4

'l Ill n

0:::

a.. I100, 2.18l

---1 () ~

>-----< :2: 2.2 Ill CJ 2.0

)>

rri 1.8 RREFERENC~: T.S. 3.4.1, ~.7.8, and 3.2 ..2 ~

=

+:>

f--' 1.6

.)

N

=

f--'

1.4

+:> 20 30 40 50 60 70 80 90 100 Core Power(% RATED)

""'0 ""'0 s:u (Q

rI MCPR OPERATING LIMIT VERSUS CORE POWER CD z BACKUP PRESSURE REGULATOR INOPERABLE .j::>. 71 C:O;::o-"

SINGLE LOOP OPERATION (BOC to EOC) oCDf" FIGURE 8.2-9 -

c.n. 0

<0 C..VO-"

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 49 of 53 9.0 POWER I 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 I Flow map, Figure 9.1.

If the OPRM Instrumentation is OPERABLE per TS 3.3.1.1, Region I of the Power I 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 I Flow map is considered an immediate exit region regardless of the operability of the OPRM Instrumentation.

SUSQUEHANNA UNIT 1 TRM/3.2-50 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 50 of 53 120~~::;cii~=ccc~~=ccc~~=ccc1J~J:~rJ~~====iJ.~r1~====1J120

+Purpose: UNIT 1 110 110 Initial/ Date:

100 80 80 0

w 70 70

~

';/!.

.... 60

~

60 0..

iii E

q) 50 50

.s::.

1-40 40 0 ~~~~~~++~~~~~++44~~~++++44~~~++++~~~++~~0 0 10 20 30 40 50 60 70 80 90 100 110 Total Core Flow (Mibm/hr)

(for SLO <75% Pump Speed Use Form G0-1 00-009-2)

Figure 9.1 SSES Unit 1 Cycle 19 Power I Flow Map SUSQUEHANNA UNIT 1 TRM/3.2-51 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 51 of 53 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:

= 1.11

= 15

= 60 Mlbm I hr SUSQUEHANNA UNIT 1 TRM/3.2-52 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 52 of 53

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, "RODEX2 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'-10: Appendix K Spray Heat Transfer Coefficients," Siemens Power Corporation, September 2000.

4. XN-NF-84-105(P)(A), Volume 1 and Volume 1 Supplements 1 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 1 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-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, 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 1 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 1 TRM/3.2-53 EFFECTIVE DATE 4/17/2014

PPL Rev. 14 PL-NF-14-001 Rev. 0 Page 53 of 53

13. EMF-2209(P)(A), Revision 3, "SPCB Critical Power Correlation," AREVA NP, September 2009.

14. EMF-85-74(P)(A), Revision 0, Supplement 1(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 CASM0-4/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. NED0-32465-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 1 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 1 TRM/3.2-54 EFFECTIVE DATE 4/17/2014

PLA-7153, Submittal of Cycle 19 Core Operating Limits Report

Contents

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1.0 INTRODUCTION

11.0 REFERENCES

1.0 INTRODUCTION

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PLA-7153, Submittal of Cycle 19 Core Operating Limits Report

Text

1.0 INTRODUCTION

11.0 REFERENCES

1.0 INTRODUCTION

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