ML033280181

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ML033280181
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Site: Susquehanna Talen Energy icon.png
Issue date: 11/14/2003
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Nov. 14, 2003 Page 1

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Pho

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TO:

D

-.wm" ix"0A" 11/14/2003 LOCATION:

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NUCSA-2)

HE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:

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TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 10/24/2003 ADD MANUAL TABLE OF CONTENTS DATE: 11/13/2003 CATEGORY: DOCUMENTS TYPE: TRMI ID:

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SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 3 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)-

Section Title Effective Date

.102..2..0 10/22/2003 TOC TABLE OF CONTENTS 1.0 2.0 3.0 3.1 3.2 3.3 USE AND APPLICATION Pages TRM / 1.0-1 through TRM /.1.0-3 PLANT PROGRAMS Pages 2.0-1 through 2.0-2 Page TRM / 2.0-3 Page TRM /2.0-4 Page TRM / 2.0-5 Pages TRM /2.0-6 and TRM /2.0-7 Page TRM / 2.0-8 Page TRM / 2.0-9 Pages TRM / 2.0-10 and TRM /2.0-1 1, Page TRM / 2.0-12 Page TRM / 2.0-13 APPLICABILITY Pages TRM / 3.0-1 and TRM Pages TRM / 3.0-3 Page TRM /3.0-4 REACTIVITY CONTROL SYSTEMS Pages 3.1-1,through 3. 16 Pages TRMU 3.1-7,aned TRM / 3.1-8 PagesTRM 1,3.1-9 and TRM / 3.1-9a Page-TRM'/ 3:1.-10 CORE OPERATING LIMITS REPORT

  • PagejRM / 3.2-1 Pages TRM / 3.2-2 through TRM / 3.2-37 INSTRUMENTATION Pages TRM / 3.3-1 through TRM / 3.3-3 Page TRM / 3.3-4 Pages 3.3-5 through 3.3-8 Pages TRM / 3.3-9 and TRM / 3.3-9a Pages TRM / 3.3-10 and TRM / 3.3-11 Page TRM / 3.3-12 Pages TRM / 3.3-13 and TRM / 3.3-14 Page TRM / 3.3-15 Page TRM / 3.3-16 Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM / 3.3-19 through TRM / 3.3-21 10/04/2002 0813111998 08/01/2001 06/25/2002 04102/1999 10122/2003 03/2912000 09/0412002 04/02/1999 10/22/2003 06/1612000 04/08/1999 03/15/2002 04/08/1999 08/31/1998 06/05/2002

.~'

02/18/1999 02/18/1-999 07/07/1999 11/0112003 I

07/16/1999 1112812000 08/31/1998 12/17/1998 12/17/1998 03/30/2001 12/14/1998 10/22/2003 06/27/2001 06/1412002 10/2212003 SUSQUEHANNA - UNIT 1 TRM / LOES-1 EFFECTIVE DATE 11/01/2003

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 3 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page 3.3-22 Pages TRM / 3.3-23 through TRM / 3.3-25 Page TRM / 3.3-26 08/31/1998 05/16/2003 10/22/2003 3.4 REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-13 10/23/1998 08/31/1998 3.5 EMERGENCY CORE COOLING AND RCIC Pages 3.5-1 through 3.5-3 Page TRM / 3.54 Pages 3.5-5 through 3.5-7 08131/1998 04/17/2000 08/31/1998 3.6 3.7 CONTAINMENT Pages 3.6-1 through 3.6-3 Page TRM / 3.6-4 Page 3.6-5

-Pages TRM / 3.6-6 through TRM / 3.6-8 08/31/1998 01/07/2002 08/31/1998 12/31/2002 PLANT SYSTEMS Pages 3.7-1 through 3.7-3 Pages TRM / 3.7-4 through TRM / 3.7-10 Page TRM / 3.7-11 Pages TRM / 3.7-12 through TRM / 3.7-27 Pages TRM / 3.7-28 through TRM / 3.7-34 Page TRM / 3.7-34a Pages TRM / 3.7-35 through TRM / 3.7-37 Pages 3.7-38 through 3.7-40 Pages TRM / 3.7-41 and TRM / 3.7-41 a Pages 3.7-42 and 3.7-43 Pages 3.7-44 through 3.7-48 Page TRM / 3.7-49 Pages TRM / 3.7-50 and TRM / 3.7-51 Pages TRM / 3.7-52 and TRM / 3.7-53 Page TRM / 3.7-54 08/31/1998

- 08/02/1999 12/29/1999 08/02/1999 11/1612001 10/05/2002 02/01/1999 08/31/1998 08/11/2000 08/31/1998 10/13/1998 03/08/2003 03/0912001 04/15/2003 07129/1999 3.8 ELECTRICAL POWER Pages TRM / 3.8-1 and TRM / 3.8-2 Page 3.8-3 Page TRM / 3.8-4 Pages TRM / 3.8-5 and TRM / 3.8-6 Pages TRM / 3.8-7 through TRM / 3.8-9 Page TRM / 3.8-10 Page TRM / 3.8-11 04/02/2002 08/31/1998 12/31/2002 04/02/2002 08/31/1998 07/1912001 04/02/2002 SUSQUEHANNA - UNIT I TRM / LOES-2 EFFECTIVE DATE 11/01/2003

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 3 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)'

Section Title Effective Date Page TRM / 3.8-11 a Pages 3.8-12 through 3.8-14 Pages TRM / 3.8-15 through TRM /3.8-17 Page 3.8-18 Page TRM / 3.8-19 Page 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25 04102/2002 08/31/1998 04102/2002 08/31/1998 04/02/2002 08/31/1998 06/06/1999 08/31/1998 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Pages 3.10-1 through 3.10-4 Page TRM / 3.10-5 Page TRM /3.10-6 Page TRM / 3.10-7 08/31/1998 03/08/2003 06/05/2002 04/07/2000 Corrected 04/1712002 Page TRM / 3.10-8 3.11 3.12 4.0 RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-121 Pages 3.11-13 through 3.11-16 Pages 3.11-17 through 3.11-21 Pages TRM / 3.11-22 through TRM / 3.11-24 Pages 3.11-25 through 3.11-32 Pages 3.11-33 through 3.11-47 08/31/1998 09/01/1998 08/31/1998 04/02/2002 09/01/1998 08/31/1998 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-5 ADMINISTRATIVE CONTROLS Pages 4.0-.1 through 4.0-8 02105/1999 08/31/1998 SUSQUEHANNA - UNIT 1 TRM / LOES-3 EFFECTIVE DATE 11/01/2003

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev.-3 UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)-

Section Title Effective Date B3.0 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM / B 3.0-11 through TRM / B 3.0-15 08/31/1998 03115/2002 B3.1 B 3.2 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 Page B 3.1-4 Pages TRM I B 3.1-5 through TRM / B 3.1-7 PageTRM/B3.1-8 CORE OPERATING LIMITS BASES Page B 3.2-1 07/1311999 08/31/1998 07/1311999 02/18/1999 08/31/1998 B3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 Page B 3.3-2 Pages TRM / B 3.3-3 and TRM / B 3.3-3A Pages TRM / B 3.3-4 through TRM / B 3.3-6 Pages TRM / B 3.3-7 through TRM / B 3.3-9 Pages B 3.3-10 through B 3.3-12 Page TRM / B 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM / B 3.3-14b Pages TRM / B 3.3-15 and TRM I B 3.3-16 Page TRM / B 3.3-17 Pages TRM / B3.3-18 and TRM I B 3.3-19 Page TRM / B 3.3-20 Page TRM / B 3.3-21 04/07/2000 08/31/1998 12/2912000 03/2112003 03/30/2001 08/31/1998 10/22/2003 06/25/2002 06/14/2002 06/14/2002 10/22/2003 04/07/2000 05/16/2003 10/22/2003 05/16/2003 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 Page TRM / B 3.4-5 Page B 3.4-6 08/31/1998 10/15/1999 08/31/1998 B3.5 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 B 3.6 CONTAINMENT BASES Page TRM / B 3.6-1 Page TRM / B 3.6-2 Page B 3.6-3 Page TRM / B 3.6-4 Page TRM / B 3.6-5 07/26/2001 02/01/1999 08/31/1998 09/23/1999 01/07/2002 SUSQUEHANNA - UNIT 1 TRM/LOES4 EFFECTIVE DATE 11/01/2003

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 3 LIST OF EFFECTTIE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)'

Section Title Effective Date Pages TRM / B 3.6-6 through TRM / B 3.6-11

.2

/...

12/31/2002 B3.7 B3.8 B.3.9 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Pages TRM / B 3.7-3 through TRM / B 3.7-7 Page TRM / B 3.7-7a Pages TRM / B 3.7-8 through TRM / B 3.7-10 Page TRM / B 3.7-10a Pages TRM / B 3.7-11 and TRM I B 3.7-1 la Pages TRM / B 3.7-12 through TRM / B 3.7-14 Pages TRM'/ B 3.7-14a and TRM / B 3.7-14b Pages TRM / B 3.7-15 and TRM / B 3.7-16 Pages B 3.7-17 through B 3.7-20 Page TRMIB 3.7-21 through TRM/B 3.7-21 a Pages TRM/B 3.7-22 and TRM/B 3.7-23 Pages B 3.7-24 through B 3.7-30 Pages TRM / B 3.7-31 and TRM I B 3.7-32 Page TRM / B 3.7-33 Pages TRM / B.3.7-34 and TRM / B 3.7-35 08/31/1998 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/02/1999 02/01/1999 08/31/1998 05/11/2001 04/07/2000 08/31/1998 03/09/2001 04/15/2003 07/05/2000 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRMJ/ B 3.8-2 Page TRM / B 3.8-2a Page TRM / B 3.8-3 Page.TRM / B 3.8-3a Page TRM / B 3.8-4 Page TRM / B 3.8-4a Page TRM / B 3.8-5 Pages TRM / B 3.8-6 through TRM / B 3.8-17 04/02/2002 04/02/2002 04/02/2002 04/02/2002 04/02/2002 04/02/2002 08/31/1998 04/02/2002 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7' 08/31/1998 B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 Page TRM / B 3.10-3 Pages TRM / B 3.10-4 and TRM /B3.10-5 Pages TRM / B 3.10-6 and TRM / B 3.10-7 08/31/1998 03/0812003 08/23/1999 04/17/2002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Page TRM / B 3.11-10 Pages TRM/B 3.11-11 and TRM/B 3.11-1 1a Pages TRM/B 3.11-12 and TRM/B 3.11-13 08/30/1998 02/0111999 04/07/2000 02/01/1999 SUSQUEHANNA - UNIT I TRM / LOES-5 EFFECTIVE DATE 11/01/2003

SUSQUEHANNA STEAM ELECTRIC STATION PPL Rev. 3 LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANlUAL)'

Section Title Effective Date Page TRM B 3.11-14 PageTRMlB3.11-15 Pages B 3.11-16 through B 3.11-19 Page TRM / B 3.11-20 Page TRM B 3.11-20a Page TRM B 3.11-21 Page TRM I B 3.11-22 Page TRM / B 3.11-23 Page TRMI B 3.11-23a Page TRMI B 3.11-24 Page TRM/B3.11-25 Pages B 3.11-26 through B 3.11-35 Page TRM / B 3.11-36 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 11/01/1999 02/01/1999 08/30/1998 04/02/2002 04/02/2002 04/02/2002 0912612003 04/0212002 04/02/2002 03/2112003 04/1512003 08/30/1998 02/12/1999 02/05/1999 NFMTRMI WAx MOESA=o

.SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 11/01/2003

Core Operating Limhits Report (COLR) 3.2.1 PPL Rev. 1 3.2 Core Operating Limits Report (COLR) 3.2.1 Core Operating Limits Report (COLR)

TRO 3.2.1 The Core Operating Limits specified in the attached COLR shall be met.

APPLICABILITY:

Specified in the referenced Technical Specifications.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core Operating Limits A.1 Perform action(s)

Specified in not met.

described in referenced referenced Technical Specification.

Technical Specifications.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY

-NOTE N/A No associated Surveillances. Surveillances are implemented in the applicable Technical Specifications.

SUSQUEHANNA - UNIT 1 TRM / 3.2-1 EFFECTIVE DATE 7/07/1999

PPL Rev. 1 PL-NF-02-001

- Rev. 2

.. Page 1 of 36 Susquehanna SES Unit 1 Cycle 13 CORE OPERATING LIMITS REPORT Nuclear Fuels.

Engineering November 2003 SUSQUEHANNA UNIT 1 TRM/3.2-2 EFFECTIVE DATE 11/01/2003

PPL Rev. I PL-NF-02-001 Rev. 2 Page 2 of 36 CORE OPERATING LIMITS.REPORT..

r REVISION DESCRIPTION INDEX Rev.

Affected No.

Sections Description/Purpose of Revision 0

1 ALL 5.0 6.0 8.0 TOC 1.0 9.0 10.0 Issuance of this COLR is in support of Unit I Cycle 13 operation.

This revision adds a text box to all appropriate plots. This text box indicates that for all bypass operable cases, four bypass valves are assumed operable. For the bypass inoperable cases, the text box indicates that two or more bypass valves are assumed inoperable.

This revision was generated'in response to Facility Operating License Amendment 210 which altered SR 3.7.6.1.

This revision is administrative in nature and no underlying calculations or plotted data were altered.

This revision adds the Power ? Flow map to the COLR. Section 1.0 was revised to include the stability regions as part of the COLR. The Power /

Flow map was added as Section 9.0. The Reference section was renumbered as Section.10.0 and a stability reference added.

This revision is administrative in nature since the Power I Flow map is already included in NDAP-QA-0338.

FORM NFP-QA-008-2, Rev. I SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 11/01/2003

PPL Rev. 1 PL-NF-02-001 Rev. 2

--~.

Page 3 of 36 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 13 CORE OPERATING LIMITS REPORT Table of Contents

1.0 INTRODUCTION

4 2.0 DEFINITIONS...............

.5 3.0 SHUTDOWN MARGIN

6 3.0 H

T O

N M

R I

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 1 TRM/3.2-4 SEFFECTIVE DATE 11/01/2003

PPL Rev. I PL-NF-02-001 Rev. 2 Page 4 of 36

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT for Susquehanna Unit 1 Cycle 13 is prepared in accordance with the requirements of Susquehanna Unit 1, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits, APRM setpoints, and stability regions presented herein were developed using NRC-approved methods and are established such that all applicable limits of the plant safety analysis are met.

SUSQUEHANNA UNIT 1 TRM/3.2-5 EFFECTIVE DATE 11/01/2003

PPL Rev. 1 PL-NF-02-001 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 1 TRM/3.2-6 EFFECTIVE DATE 11/01/2003

PPL Rev. 1 PL-NF-02-001 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 rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and ppison 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, "Rn. 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 1 '

TRM/3.2-7 EFFECTIVE DATE 11/01/2003

PPL Rev. 1

-PL-NF-02-00.1 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 DescriDtion The APLHGRs forATRIUMm-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 1 TRM/3.2-8 EFFECTIVE DATE 11/01/2003

Q) q C,

SSES UNIT 1 CYCLE 13 (A,

C=

-4~-4

--4 C.I

-n

-n C-4

'-S I-.

I' 12 11 io

_ 10

. E a:

om e~

8 m c 8

.C

. 0 I

6 5

0.0,11.'5 15000,11.'5

{EEENCE T.S.3~

___ __E_

ETERMINING __ 3_

59400,6.7 t000

-000

-U I-5X

<v Il 0

10000 20000.

30000 40000 50000 60000 70000 Average Planar Exposure (MWDIMTU)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMTM.10 FUEL FIGURE 4.2-1 IoM la

.,w 0 7 to<

m z

1 W;4 -n 0

6 I

h

,Iw 6

1. 0)

Q-a

PPL Rev. 1 PL-NF-02-001 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 (ATRIUMT'1-10) 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 I 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

. I 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 1 -

TRM/3.2-10 EFFECTIVE DATE 11/01/2003

PPL Rev. 1

(02 (A

(A 0-4 Li C)

SSES UNIT 1 CYCLE 13 2.3

!Al r%3 1-SA 0I 1!

0 a.

C)

-n m

m CD, 30 40 50 60 70 80 90 100 110 Total Core Flow (MLBIHR)

X A

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC.RPT AND MAIN TURBINE BYPASS OPERABLE 6

TWO LOOP OPERATION (BOC TO EOC) a FIGURE 5.2-1

(9; c )

SSES UNIT 1 CYCLE 13 C;

C,)

m

-4

--4 C.,-

1~3 CA, m

7n

-n m

C-.)

-4 ri m

I-.

'-S C)

CD, 3.0 2.9 2.8 2.7 2.6 2.5 2.4 En x 2.3 0)

= 2.2 A.2.1

<- 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 I-ED (100.1.53)

(100,1.47) 20 30 40 50 60 70 80 90 Core Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)

FIGURE 5.2-2 100 CD) 0 0 & )n-

PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 13 of 36 Main Turbine Bypass Inoperable I EOC-RPT-Operable SUSQUEHANNA UNIT I TRM/3.2 EFFECTIVE DATE 11/01/2003

0C2.

C0 SSES UNIT I CYCLE 13 IC0.

Ln C

rr m

D C-2.3 1

1 I

2.2 2.1 4

-4 4

4CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 4

4 4-1~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

I I

I 2;0 I

I I_

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

'-A

(.1n E 1.9 Jow c

! 1.8 0

0.

0 1.7 mn

-n m

C-4 1

'-4 m

L-4 m

t-as (A) 1.6 1.5 (30l1.78)

USED IN DETERMINING MFLCPR (30,1.78)..I_

(108,1.75)

__R_

A B

(37 1.1

75) l

REFERENCE:

TYS. 3.2.2l

.~~4

-U cu I-1.4 1.3 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW MAIN TURBINE BYPASS INOPERABLE I EOC.RPT OPERABLE TWO LOOP OPERATION (BOC TO EOC)

FIGURE 5.2.3 110 m 0

_o <

M.,

0.-4 I wn 7

z

-b

(

(9 C(2 (AZ m

-4i 3.0 2.9 2.8 2.7 2.6 2.5

!:Al 0)~

m

-I, m

4-I

-I I.-

t-S CD) 2.4 E 2.3 a)

, 2.2 I!

K 2.1 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3 SES UNIT 1 CYCLE 113

=

~LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM

._(25,2.64) -

l INSERTION TIME

.___.__\\_

CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

=~~~~~~~~~~UE IN DETERMINING MFLCPR-(40,2.04)A (68.2,1.75)

REFERENCE:

T.S. 3.7.6 and 3.2.2

_ i

' I L

-uu

(-

CD (100,1.75) 20 30 40

FIGURE 5.2-4 la'

.0

,0

'3 CD 5O N)

I,-

z 0

0?

PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 16 of 36 EOC-RPT Inoperable I Main Turbine Bypass Operable SUSQUEHANNA.UNIT I TRM/3.2-17 EFFECTIVE DATE 11/01/2003

0 (In

'-a I'i

-Ilr-rri

--4 m-(i (ii SSES UNIT I CYCLE 13' 2.3 2.2 2.1 2.0 S 1.9 Z3 0

0.a1.

a.

U 1.7 1.6 1.5 1.4 1.3 I

I I

.I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

__._____l JSAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 10 4

+

4 1

4 4

(30,1.64)

AAk I-I

1.

I (108,1.64)

REFERENCE:

T.S. 3.2.21

_X

~~~.

T.'.

.1 40 30 50 60 70 80 90 100 Total Core Flow (MLBIHR)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW EOC-RPT INOPERABLE / MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC TO EOC)

FIGURE 5.2-5 110 4w 6

0I C

SSES UNIT 1 CYCLE 13 (A1 VI)

--I I-a 3.0 2.9 2.8 2.7 2.6 r 'r' r

I I

I I

I ILEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I

I.

I I

I I',

2.5 (25,2.41) i i

i i

(30,2.41)

-4I CA) n,

-n, P1 m

I-a r\\3 CDO 2.4 HE 2.3 0I

= 2.2 O 2.1

& 2.0 1.9 1.8 1.7 1.6 1.5 1.4 1.3

_ SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE L OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (j

. r,-u D

I-(100,1.64)

.\\___.__.

USEID IN DETERMINING MFLCPR

~(40,1.90)

A

_B_

I Rr-FFRFNr-F;. T-s. a~a4i and ~22I2 i

(74,1.64)

~~~z~~a-

  • t I

-t t~~~~

1-I I

.1.

. 1 I

I -_

I

_ I 20 30 40 50 60 70 80 90 Coro Power (% RATED)

MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE TWO LOOP OPERATION (BOC to EOC)

FIGURE 5.2.6 100 co 0

0 X

_b CD

PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 19 of 36

-Table 6.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)

Position 45 0.470 0.480 0.490 0.500 0.510 0.520 39 0.630 0.676 0.722 0.768 0.814 0.860 25 1.500 1.582 1.664 1.746 1.828 1.910 5

2.700 2.848.

2.996 3.144 3.292 3.440 Scram Time 0.000 0.200 0.400 0.600 0.800 1.000 Fraction Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 1 TRM/3.2-20 EFFECTIVE DATE 11/01/2003

PPL Rev. 1 PL-NF-02-001 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 Bypass Onerable The LHGR for ATRIUM'm-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.

Main Turbine Bvpass Inoperable The LHGR for ATRIUMTM-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.

SUSQUERANNA UNIT 1 '

TRM/3.2-21 EFFECTIVE DATE 11/01/2003

0 C/)

(A C=

m DI, r-T 7-4

'-4

--4 m

I-J

.C.,

16 14 I.

12 4.'

0 c

0 G

0-m8 6

4 SSES UNIT 1 CYCLE 13 I I I I I-II I IIIIIIIII_

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE

_ 111

_- _ _ _ _ _ _ _ _ _ _ ____OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.0,13.4 15000.0,13.4

REFERENCE:

T.S.3.2.3 USED IN DETERMINING FDLRXj 59400.0,8.0 I

I 1

1 1

1 C-,-.

r-I. I 0

10000 '

20000 30000 40000 50000 60000 Average Planar Exposure (MWDIMTU)

LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS OPERABLE ATRIUMTM-10 FUEL FIGURE 6.2-1 70000

. TD m Z

. to 0 7 N

1 CA) 0

'. _m

PPL Rev. 1 I I I1 I I

I1 I

I.1 I

PL-NF-02-001

, Rev.2 g.Page. 22 of 36 r

go a,

g N m I'

< U o ox 0 0 0.

o Cl aw W w F1 x a.

2:

za,

< Ul L>

<L a,

c.

ri CO) a:

C, w

UJ w

L.:

w 90 U-W-

0 z

0 r 1 1 ~~~,I I

It I

n I

I IA I0 1Ht A17 1. l 1 -~~~~~~~~~~

CD 40 CD 03 0D 07 w

-i C.)

rl, El

-I I

/

1 1

.1 I 1-II I l/I I I I I

I CD CO CD 0

6 I-0 (U

0 0.

x LU L..

co 0) 0)

LU 0 0.

0.

LuW 0IL

LU 2 ~

Z I-CO 'mj LUJ z.

z.

tu, LU z

I 1

/ I I-I I -

I I-

=~~~

I-1 11111

°r f~

I I

TT

- 04 Ini C.-

0 CD CZ 40 C)

Q N

.C c

(tuMqI) a!wn fe2 UOpwJausO

eaH Jleaur SUSQUEHANNA UNIT 1 TRM 3.2-23 EFFECTIVE DATE 11/01/2003

PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 23 of 36 "9

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.

K)~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

SUSQUEHANNA UNIT 1,

TRM/3.2-24 EFFECTIVE DATE 11/01/2003

PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 24 of 36 Table 7.2-1 APRM Setpoint for Two Loop Operation Trip Setpoint Allowable Value S 5 (0.58W + 59%) T S < (0.58W + 62%) T' SRB < (0.58W + 50%) T SRB * (0.58W + 53%) T Table 7.2-2 APRM Setpoint for Single Loop Operation Trip Setpoint Allowable Value S < (0.58W + 54%) T S5 A

(.8W + 57%) T'l SRB * (0.58W + 45%) T SRB * (0.58W + 48%) T where: S and SRB are in percent of RATED THERMAL POWER W =

Loop recirculation flow as a percentage of the loopI recirculation flow which produces a core flow of 100 million lbs/hr T.=

Lowest value of the ratio of FRTP divided by the MFLPD.2 The FLPD is the actual LHGR divided by the applicable LHGR limit for APRM Setpoints. The LHGR limit for APRM setpoints for ATRIUMTM-10 fuel shall be taken from Figure 7.2-1.

The LHGR for APRM setpoint limits in Figure 7.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable for both Two and Single Loop operation.

For calculated T-values greater than 1.0, a ratio of 1.0 is used in the above equations.

APRM flow biased simulated thermal power-upscale scram allowable value in this table is equal to the value established in Technical Specification 3.3.1.1.

2 For the calculation of T, the value of MFLPD shall be the maximum value of FDLRC.

SUSQUEHANNA UNIT 1 TRM/3.2 EFFECTIVE DATE 11/01/2003

0i (Ii 0i SSES UNIT 1 CYCLE 13 Ln CA U)

'4i-I 18 16 C.

4 J E:

n E14 C.0 o.

lfi2 0 u 1 o Q) 0 Q-0 01 ZI j J R~~~~~~~EFERENCE: T.S. 3.2.4 15000,15.0 l-l USEDINDETERMINING FDLRC 0.0,1 5.0 59400,9.1

-u

I-m m

C-I m

I-nj I--&

C.,

8 l

6 0

10000 20doo 30000 40000.

50000 60000 Average Planar Exposure (MWDIMTU)

LINEAR HEAT'GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE ATRIUMm -10 FUEL FIGURE 7.2-1 70000 0

to I-7 0*

Z p"J -1

.0&

PPL Rev. 1.

PL-NF-02-001 Rev. 2 Page 26 of 36 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Soecification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUMThU-1 0 fuel shall be equal to the APLHGR Limit from Figure 8.2-1.

The APLHGR limits in Figure 8.2-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable in Single Loop operation.

Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limit for all fuel types (ATRIUM'-10) shall be the greater of:

a)

Flow-Dependent MCPR value determined from Figure 8.2-2 OR b)

The Power-Dependent MCPR value determined from one of the following

  • figures, as appropriate:

Figure 8.2-3: EOC-RPT and Main Turbine Bypass Operable from BOC to EOC Figure 8.2-4: Main Turbine Bypass Inoperable I EOC-RPT Operable from BOC to EOC Figure 8.2-5: EOC-RPT Inoperable / 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 1 TRM/3.2-27 EFFECTIVE DATE 11/01/2003

PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 27 of 36 Average Power Range Monitor (APRM) Gain And Setnoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined in Section 7.0.

SUSQUEHANNA UNIT 1 TRM/3.2 EFFECTIVE DATE 11/01/2003

0~

I-,.'

CLI SSES UNIT I CYCLE 13 m

--I g-a 12 11

--4 m

-4 Ei

'-a I.-

CA)

-10

.0.

E cS 9

c tDo 0.

4-D 0 0 0

8 c

7 0

07 6

5 X

] ]

l

[ 1 1 _ _ __ _ _ _

REFERENCE T.S. 3.4.1 and

_ _ _ _ _ _ _ _ 1 USEDINDETERMINING MAPRAT 0.0,9.2 15t0009.2-7------

A59400.4 I-u I-

0 CD

\\

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 ATRIUMTM-10 FUEL FIGURE 8.2-1 70000

. t o<,

  • 'c z

co Ca o

' 0

°4

C)11 C

c l SSES UNIT 1 CYCLE 13 (A

c-'

CA)

I'

'*1

~1~

CA)

CD MI, I-.

N, CA)

I I

I0 I

2.5 2.4 t: 2.3-E c

0 2.2 cL0 0.

2.0 -

1.9 -

1.8

_~~_.

_I LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME

. ~ ~

~

~

~~~~~~ I..

I I

USED IN DETERMINING MFLCPR (108,2.20)

(30,2.20)

-n

-u I-CD 1

4

'A I

B

~

~

I

-l a.

REFERENCE:

T.S. 3.4.1 and 3.2.2 1 -

t 1

4 I.

II I

I 110 I*-

4.
4.

I-30 40 50 60 70 80 90 100 Total Core Flow (Mlbmlhr)

MCPR OPERATING LIMIT VERSUS TOTAL CORE FLOW SINGLE LOOP OPERATION (BOC to EOC)

FIGURE 8.2-2 fIV

.c0

-. 0) 0 5

I-z

'1 NCD

0al Q)

C-)

CA

.CA 1-4 SSES UNIT I CYCLE 13 3.5 'p 1

I I

I LEGEND 3.4 3.3 3.2I

_I I

l CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 3.'

3.4 1-4 m-n

-I,m

-4 I'

'-a 1-ai I.-

NJ CA)

.d 2.'

4-E0 2.1

.5 2.1 0

i 2.4 a

0.

C.,

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 (25,2.81)

(30,2.81)

USED IN DETERMINING MFLCPR r-6 3

5-

\\

~~~~~~~~~~~~~~.1.

Cr CDw A

2.2 -

B I

1(100,2.20) 4

4.

I~~~~~~~~~~~~~~~r%-----

(38.5,2.20)

L 2.1 *1

1.

4 4

  • I I

I Is 2.0-

.4PERENCE: T.S. 3.4.1 anI 3.2.21..

-t p

t i

I I

.1. I 1.9

~~~~~~~~~~~~~~~~~~~~~~~~.

I 20 30 40 50 60 70 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 80 90 100

.N 1.z I:.0 bvl m

  • o L

CD

-h

0 (i

C SSES UNIT I CYCLE 13 tn V)

C"

'-4 3.5 3.4 3.3 3.2 3.1 I

4 1

4 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME

- I._ I

. ClURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME K-

_(25,3.07IIJ I I

I II I

_II I

I I

I 3.0 9

9 I

I SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

[

CO, mn

-n C-4

'-4 m

P1 I-CD)

T4,2.9 E

i 2.8 c

  • 2.7 a.

0 -

a 2.6 0.

2 2.5 2.4

\\_________

\\__.__=__=

USED IN DETERMINING MFLCPRJ=

-u

-u I-,

0u 2.3 *

(40,2. ^at 3J0)

I A

I B

2.2 2.1 2.0 1.9 I

I (100,2.20)

I (54.6,2.20)

I~

~~~~~~~~

I1

.I

REFERENCE:

T.S5 34.1, 3.7.6, and '3.2.

_.I 20 30 40 50 60 Core Power (% RATED) 70 80 90 100

. w 0.

0)

MCPR OPERATING LIMIT VERSUS CORE POWER MAIN TURBINE BYPASS INOPERABLE I EOC-RPT OPERABLE SINGLE LOOP OPERATION (BOC to EOC)

FIGURE 8.2-4

Cj.

( C.,

K,.

(/1 m

r-,

3.5 3.4 3.3 3.2 3.1 3.0 C.)

m

-n, m

C-,)

m m

1I-h I-hj

.-4 I-'

CA)

._ 2.9 E

  • 3,a, 2.8 c

2.7 0

M 2.6 0.

2 2.5 2.4 2.3 2.2 2.1 2.0 1.9 SSES UNIT I CYCLE 13 I

I I

I 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 (25.2.81)

(30,2.81)

\\

l

~~~~~~~~~~USED INI DETERMINING MFLCPR

\\

~

~~~~~~~A B

(41.3,2.20)

REFERENCE:

T.S. 3.4.1, 3.3.4.1, and 3.2.2 (D

I-

.0u (100,2.20)

,.1

. i 20 30 40 50 60 Core Power (% RATED) 70 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT INOPERABLE I MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)

FIGURE 8.2.5 100 I to

~

0

0) I

-&f

PPL Rev. 1 PL-NF-02-001 Rev. 2 Page 33 of 36 9.0 POWER / FLOW MAP

.., 7, 9.1 Technical Specification Reference I

I I

Technical Specification 3.4.1 9.2 Description' I

Monitor reactor conditions to maintain THERMAL POWER / core flow outside of l Stability Regions I and 11 of the Power / Flow map, Figure 9.1.

I SUSQUEHANNA UNIT 1 TRM/3.2-34 EFFECTIVE DATE 11/01/2003

PPL Rev. 1

  • PL-NF-02-001 Rev. 2 Page 34 of 36 120 110 100 90 80 120

Purpose:

.J-.

-L - r

-r POWER I FLOW MAP Iniffal / Daba:

/

-100%R ltod~ne F ~ * ^ ~

tR110 APRM Rod Blockc--

j.

STBILITYpREGIONI

_I r I

REr RICTED REGION IMMEDIATE SCRAM REQUIRED r,

l 100 RAWEON-17GO2

,-i STABILITY REGION 11

-I-IMMEDIATELY EXIT REGION

.L*,AW ON-178-r r02 I -r r

r RESTRICTED REGION (As defined In Attachment G to NDAP-OA4133)

NM-,r y, 1 -rrC

-LI 1

i L.

C.1-0 0.

ra I-70 60 50 40 30 20 10 0

i l.

,t _..

.- T-,-r -n1-11 r -I-Irr-1r1

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I I I5r-I I I I I 11 I~~~~~~~~ I.

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-I-i-_:

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  • T -I t:-

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a.

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  • 80
  • 70

-60

-so

- 40

- 30

- 20

- 10 I

w

  • l I

~~~~~~~

0 10 20 30 40 S0 60 70 80 90 100 110 Total Core Flow (Mlbm/hr)

Figure 9.1 Power / Flow Map SUSQUEHANNA UNIT 1 TRM/3.2-35 EFFECTIVE DATE 11/01/2003

PPL Rev.

PL-NF-02-001 Rev.2 Page 35 of 36

10.0 REFERENCES

10.1 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. PL-NF-90-001-A, "Application of Reactor Analysis Methods for BWR Design and Analysis," July 1992.
2. XN-NF-80-19(P)(A), Volume 4, Revision 1, "Exxon Nuclear Methodology for Boiling Water Reactors: Application of the ENC Methodology to BWR Reloads," Exxon Nuclear Company, Inc. June 1986.
3. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,

September 1986.

4. XN-NF-80-19(A), Volume 1, and Volume 1 Supplements I and 2 (March 1983), and Volume 1 Supplement 3 (November 1990), "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis," Exxon Nuclear Company, Inc.
5. ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors," November 1990...
6. ANF-1125(P)(A) and ANF-1125(P)(A), Supplement 1, "ANFB Critical Power Correlation," April 1990.
7. NEDC-32071P-, "SAFER/GESTR-LOCA Loss of Coolant Accident Analysis,"

GE Nuclear Energy, May 1992.

8. 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).
9. PL-NF-90-001, Supplement 1-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Loss of Feedwater Heating Changes and Use of RETRAN MOD 5.1," August 1995.
10. PL-NF-94-005-P-A, "Technical Basis for SPC 9x9-2 Extended Fuel Exposure at Susquehanna SES," January 1995.
11. PL-NF-90-001, Supplement 2-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: CASMO-3G Code and ANFB Critical Power Correlation," July 1996.

SUSQUEHANNA UNIT 1 TRM/3.2-36 EFFECTIVE DATE 11/01/2003

PPL Rev.1 PL-NF-02-001 Rev. 2 Page 36 of 36

12. ANF-89-98(P)(A) Revision 1 and Revision 1 Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs,"Advanced NuclearFuels 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-80-19(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," September 1982.
15. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," January 1987.
16. XN-NF-79-71(P)(A) Revision 2, Supplements 1, 2, and 3, "Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.
17. EMF-1997(P)(A) Revision 0, "ANFB-10 Critical Power Correlation,"

July 1998, and EMF-1997(P)(A) Supplement 1 Revision 0, "ANFB-10 Critical Power Correlation: High Local Peaking Results," July 1998.

18. PL-NF-90-001, Supplement 3-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Application Enhancements," September 1999.
19. Caldon, Inc.,. 'TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM'TM System," Engineering Report - 80P, March 1997.
20. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM~' or LEFM CheckPlusTm System," Revision 0, Engineering Report ER-160P, May 2000.
21. EMF-85-74(P), URODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements I and 2, February 1998.
22. EMF-CC-074(P)(A), Volume 4, Revision 0, uBWR Stability Analysis:

Assessment of STAIF with Input from MICROBURN-B2," November 1999.

. SUSQUEHANNA UNIT I TRM/3.2-37 EFFECTIVE DATE 11/01/2003

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