Text

TRM Approved Amendment to Units 1 & 2 Technical Requirements Manual, Effective 07/28/03
	ML032200317
Person / Time
Site:	Susquehanna
Issue date:	08/04/2003
From:	; Susquehanna
To:	Rose G; Office of Nuclear Reactor Regulation
References
	2003-35704
	Download: ML032200317 (84)
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TRM APPROVED AMENDMENT TO UNIT 1 TECHNICAL REQUIREMENTS MANUAL EFFECTIVE DATE:

0712812003 Replace the following pages of the Technical Requirements Manual with the enclosed pages.

The revised pages are identified by Effective Date and contain vertical lines indicating the area of change.

as-

-: ;-REMOVEPAGES IN R

AGEid Es A. TE DATE TRM / LOES-1 through TRM / LOES-6 TRM I LOES-1 through TRM I LOES-6 07/28/2003 TRM / 3.2-2 through TRM 3.2-35 TRM / 3.2-2 through TRM 3.2-35 07/28/2003 gA~Lic Docs\\TRM Word\\TRM Remove InserL\\ReminsShellUnlt1.2dcc 07rAMW

SUSQUEHANNA STEAM ELECTRIC STATION I

LIST OF EFFEC77VE SEC77ONS (TECHNICAL REQUIREMENTS MANUAL)

\\J Section i

C

-~ 0TOC Title Effective Date TABLE OF CONTENTS 05/16/2003 1.0 USE AND APPLICATION Pages TRM / 1.0-1 through TRM /1.0-3 10104/2002 2.0 3.0 3.1 3.2 3.3 PLANT PROGRAMS Pages 2.0-1 through 2.0 Page TRM /2.0-3 Page TRM /2.0 Pages TRM /2.0-5 through Page TRM 2.0-7 Page TRM /2.0-8 Page TRM 2.0-9 Pages TRM /2.0-10 throughlTRM /2.0-12 Page TRM /2.0-13 APPLICABILITY Pages TRM /3.0-1 and TRM /3.0-2 AlIt

^

.I I

-08/31/1998 08/01/2001 06/25/2002 04/02/1999 03/29/2000 09/04/2002 04/02/1999 06/16/2000

).

oc q

Al i

I A -., 7 7.,

rayes IrnM / J.;

R 0-

>S Page TRMI3.0-4 REACTIVITY CONTROL SYS Pages 3.1-1 through3.1-

)

PagesTRM/3.1-7 andRM!

183.1-8 Pages TRM / 3.1-9 aRllT

/T3.1-9a Page TRM / 3.1

-1p-CORE OPERATlAtG LIViTS REPORT Page TRM13.'N t-h,

=

Pages TNM 3.2-through TRM / 3.2-35 INSTRIMENtATION-pag4s TRM / 3.3-1 through TRM 3.3-3 tPage HM/3.34 Pa $ 3.3-5through 3.3-8

- *ages 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 through TRM 13.3-15 Page TRM / 3.3-16 Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM / 3.3-19 through TRM /3.3-21 Page 3.3-22 Pages TRM /3.3-23 through TRM /3.3-25 Page TRM / 3.3-26

-04/08/1999 03/15/2002 04/08/1999 08131/1 998

-06/05/2002 02/18/1999 02/18/1999 07/07/1999

-07/28/2003 I

07/1611999 11/2812000 08/31/1998

-12/17/1998 12/17/1998 03/30/2001 12/14/1998 06/27/2001 06/14/2002 12/14/1998 08131/1998 05/1612003 04/02/1999 SUSQUEHANNA - UNIT I TRM / LOES-1 EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION UST OFEFFEC11VE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section 3.4 Trle Effective Date 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 / 3.5-4 Pages 3.5-5 through 3.5-7 08/31/1998 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 I 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 I 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 08102/1999 12/29/1999 08/02/1999 11/16/2001 10/0512002 02/01/1999 08/31/1998 08/11/2000 08/31/1998 10/13/1998 03/08/2003 03/09/2001 04/15/2003 07/29/1999 3.8 ELECTRICAL POWER Pages TRM / 3.8-1 and TRM / 3.8-2 Page 3.8-3 Page TRM / 3.8-4 Pages TRM / 3.8-5 and TRM / 3.8-6 Pages TRM / 3.8-7 through TRM / 3.8-9 Page TRM / 3.8-10 Page TRM / 3.8-11 Page TRM / 3.8-1 la Pages 3.8-12 through 3.8-14 Pages TRM / 3.8-15 through TRM / 3.8-17 IFage 3.8-18 Page TRM / 3.8-19 04/02/2002 08/31/1998 12/31/2002 04/02/2002 08/31/1998 07/19/2001 04/02/2002 04/02/2002 08/31/1998 04/02/2002 08/Si/1998 04/02/2002 SUSQUEHANNA - UNIT I TRM / LOES-2 EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25 08/31/1998 06/06/1999

-08/31/1998 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Pages 3.10-1 through 3.10-4 Page TRM / 3.10-5 Page TRM / 3.10-6 Page TRM / 3.10-7 08/31/1998 03/08/2003 06/05/2002 04/07/2000 Corrected 04/17/2002 Page TRM / 3.10-B 3.11 RADIOACTIVE EFFLUENTS -

Pages 3.11-1 through 3.11-12 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 08131/1998 3.12 4.0 LOADS CONTROL PROGRAM -

X Pages TRM / 3.12-1 through TRM / 3.12-5 ADMINISTRATIVE CONTROLS 0

Pages 4.0-1 through 4.0-8 02/05/1999 08131/1998 SUSQUEHANNA - UNIT I TRM / LOES EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION USTOFEFFECTIVESECTIONS(TECHNICAL REQUIREMENTS MANUAL)

Section B 3.0 B3.1 Title Effective Date APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 I

Pages TRM / B 3.0-11 through TRM I B 3.0-15 08/31/1998 03/15/2002 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 Page B 3.1-4 Pages TRM / B 3.1-5 through TRM / B 3.1-7 Page TRM I B 3.1-8 07/13/1999 08/31/1998 07/1311999 02t18/1999 B3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 Page B 3.3-2 Pages TRM I B 3.3-3 and TRM I B 3.3-3A Pages TRM I B 3.3-4 through TRM I B 3.3-6 Pages TRM / B 3.3-7 through TRM / B 3.3-9 Pages B 3.3-10 through B 3.3-13 Page TRM / B 3.3-14 Page TRM I B 3.3-14a Page TRM / B 3.3-14b Page B 3.3-15 Pages TRM / B 3.3-16 and TRM / B 3.3-17 Pages TRM I B3.3-18 through TRM I B 3.3-21 04/07/2000 08/31/1998 12/29/2000 03/21/2003 03130/2001 08/31/1998 06/25/2002 06/14/2002 C 06/14/2002 08/31/1998 04W07/2000 05/16/2003 B3.4 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 08131/1998 B3.6 CONTAINMENT BASES Page TRM / B 3.6-1 Page TRM I B 3.6-2 Page B 3.6-3 Page TRM / B 3.6-4 Page TRM / B 3.6-5 Pages TRM / B 3.6-6 through TRM / B 3.6-11 07/26/2001 02/01/1999 08/31/1998 09/23/1999 01/07/2002 12/31/2002 SUSQUEHANNA - UNIT 1 TRM / LOES-4 EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section B3.7 B3.8 B.3.9 Title Effective Date PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 Pages TRM / B 3.7-3 through TRM / B 3.7 Page TRM / B 3.7-7a Pages TRM / B 3.7-8 through TRM I B 3.7-10 Page TRM / B 3.7-1 Oa Pages TRM / B 3.7-11 and TRM / B 3.7-11 a Pages TRM / B 3.7-12 through TRM I B 3.7-14 Pages TRM / B 3.7-t4a 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 TRMfB 3.7-21 through TRMlB 3.7-21 a Pages TRM/B 3.7-22 and TRMfB 3.7 Pages B 3.7-24 through B 3.7-30 Pages TRM / B 3.7-31 and TRM / B 3.7-32 Page TRM / B 3.7-33 Pages TRM I B 3.7-34 and TRM / B 3.7-35 08/31/1998 08J02/1999 08/0211999 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 04I02f2002-04/02/2002 04/02/2002 04/02f2002 04/02/2002 04/02/2002 08/31/1998 04/02/2002 08131/1998 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRM I B 3.8-2 Page TRM I B 3.8-2a Page TRM I B 3.8-3 Page TRM I B 3.8-3a Page TRM / B 3.8-4 Page TRM I B 3.8-4a Page TRM / B 3.8-5 Pages TRM I B 3.8-6 through TRM / B 3.8:17 REFUELING OPERATIONS BASES Pages B 3.9-1 through B 3.9-7 B 3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 Page TRM I B 3.10-3

- =

Pages TRM I B 3.104 and TRM / B 3.10-5

-IPages TRM / B 3.10-6 and TRM / B 3.10-7 08131/1998 03/08/2003 08/23/1999 04/17/2002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 PageTRM/B3.11-10 Pages TRMIB 3.11-11 and TRM/B 3.11-1 la Pages TRM/B 3.11-12 and TRM/B 3.11-13 Page TRM B 3.11-14 Page TRM B 3.11-15 Pages B 3.11-16 through B 3.11-19 Page TRM t B 3.11-20 08130/1998 02/01/1999 04/07/2000 02/01/1999 11/01/1999 02101/1999 08130/1998 04/02/2002 SUSQUEHANNA - UNIT I TRM / LOES-5 EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECT7ONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page TRM I B 3.1 1-20a Pages TRM / B 3.11-21 through TRM B 3.11-23 Page TRM / B 3.11-23a Page TRM/B 3.11-24 Page TRM / B 3.11-25 Pages B 3.11-26 through B 3.11-35 Page TRM I B 3.11 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM / B 3.12-3 04/02/2002 04/02/2002 04/0212002 03/21/2003 04/15/2003 08/30/1998 02/12/1999 02/05/1999

.g:\\I~c Docs\\TRM-Word\\TRM Manual\\0.00 Usts\\Unlt l~Ul TRM LOES~doc SUSQUEHANNA - UNIT 1 TRM / LOES-6 EFFECTIVE DATE 07/28/2003

PL-NF-02-001 Rev. 1 Page 1 of 34 Susquehanna SES Unit 1 Cycle 13_

CORE OPERATING LIMITS

-~

REPORT Nuclear Fuels Engineering July 2003 SUSQUEHANNA UNIT 1 TRM/3.2-2 EFFECTIVE DATE 07/28/2003

PL1NF-02-001 Rev. 1 Page 2 of 34 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.

Affected No.

Sections I

Description/Purpose of Revision 0

1 ALL 5.0 6.0 8.0 Issuance of this COLR is in support of Unit 1 Cycle 13 operation.

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

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

This revision is administrative in nature and nounderlying calculations or plotted data were altered..

FORM NFP-OA-008-2, Rev. 1 SUSQUEHANNA UNIT 1 TRM/3.2-3 EFFECTIVE DATE 07/28/2003

PL-NF-02-001 Rev. 1 Page 3 of 34 SUSQUEHANNA STEAM ELECTRIC STATION Unit 1 Cycle 13 CORE OPERATING LIMITS REPORT Table of Contents 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.D.

INTRODUCTION............

4 DEFINITIONS..................................................................................

5.......................

SHUTDOWN MARGIN...............

6 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR).............

7 MINIMUM CRITICAL POWER RATIO (MCPR)..................I.............9 LINEAR HEAT GENERATION RATE fLHGR)..................................................

20 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS,..........23 RECIRCULATION LOOPS - SINGLE LOOP OPERATION.................................

26 REFERENCES.3OITOR........GAIN.AND.SETPOINTS......................................................

3 SUSQUEHANNA UNIT 1 TRM/3.2-4 EFFECTIVE DATE 07/28/2003

PL-LNF-02-O01 i::: D

~~~~~~Ret 1l Page 4 of 34

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 and APRM 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 07/28/2003

PL-NF-02-001 Rev. I Page 5 of 34 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 07/28/2003

PL-NF-02-001 Rev. 1 Page 6 of 34 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 bumup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, 'R". The adder, BR', 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 I TRM/3.2-7 SEFFECTIVE DATE 07/28/2003

PL-NF-2-001 Rev. 1 Page 7 of 34 4.0 AVERAGE PLANAR UNEAR HEAT GENERATION RATE (APLHGR) 4.1 Technical Specification Reference Technical Specification 32.1 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 and EOC-RPT Operable and Inoperable in Two Loop operation.

The APLHGR limits for Single Loop operation are provided in Section 8.0.

SUSQUERANNA UNIT 1 TRM/3.2-8 EFFECTIVE DATE 07/28/2003

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PL-NF-02-001 Rev. 1 Page 9 of 34 5.0 MINIMUM CRITICAL POWER RATIO (MCPR) 5.1 Technical Specification Reference Technical Specification 3.2.2,3.7.6, and 3.3.4.1 5.2 Description The MCPR limit is specified as a function of core power, core flow, average scram Insertion time per Section 5.3 and plant equipment operability status. The MCPR limits for all fuel types (ATRIUM'-1 0) shall be the greater of the Flow-Dependent or the Power-Dependent-MCPR, depending on the applicable equipment operability status.

a)

EOC-RPT and Main Turbine Bypass Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b)

Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 5.2-3: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC C)

EOC-RPT Inoperable I Main Turbine Bypass Operable.

Figure 5.2-5: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 52-1 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 07/28/2003

PL-NF-02-001 Rev. 1 Page 10 of 34 EOC-RPT and Main Turbine Bypa'ss

-Operable p~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

SUSQUERANNA UNIT I TRM/3.2-11 UEFFECTIVE DATE 07/28/2003

C/

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PL-NF-02-OO1 Rev. 1 Page 13 of 34 Main Turbine Bypass Inoperable I EOC-RPT*

Operable SUSQUEHANNA UNIT 1 TRM/3.2-14 EFFECTIVE DATE 07/28/2003

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~~~~~~~I l

I I_

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 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 2.0

--I RA W'

N-C,,

.9 1.9 1.8 0.

0 0IL 1.7 2

I I

USED IN DETERMINING MFLCPR (30,1.78)

_(37,1.75)

I I

.9 I

I A

I-I 9

54 B

I (108,1.75)

I I

I

I 4

1.6 mn

-n

-n m

C-)

N-4 rn

-I r'3 CA, 1.5 1.4 l

REFERENCE:

T.S. 3.2.2 1.3 30 40 50 60 70 80 90 100 Total Core Flow (MLB/HR)

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

FIGURE 5.2-3 110 lam lar6 to _

-0b 6r eP 0-A

3.0 SSES UNIT 1 CYCLE 13 C=

2.9 -

c LEGEND 2.8 CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM 2.7 -(25,2.64)_

INSERTION TIME 2.6 CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.5 2.4 SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS

E 2 3

\\

~~~~~~~~VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2

~2.3

~ 2.2 3

! 2 2

=

0

\\\\

l R3 j~~~~~~UED N DETEFIMINING MFLCPR 2.0 1.9 (40,2.04) 1.8 B

(100,1.75) rn 1.7 (68-2,1.75) c, 1.6-1.5 -;

REFERENCE:

T.S. 3.7.6 and 3.

1.4 20 30 40 50 60' 70 80 90 100 Core Power (% RATED)

N3 C>

'to'.

r.

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

C.)

0 FIGURE 5.2-4

PL-NF-02-001 Rev.

Page 16 of 34 EOC:RPT noperable I Main Turbine Bypass-Operable-

-I

- f N

SUSOUEHANNA UNIT 1 TRM/3.2-17 EFFECTIVE DATE 07/28/2003

C' 2)

(92 SSES UNIT 1 CYCLE 13 V/)

'9-I

--i

)-A 2.3 2.2 2.1 LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR 2.0

--I r.4.

OD 6'1.9-E19 c

A1.8 0.

& 1.7

-4

4.

1

4.

1

I (30,1.64)

(

,(108,1.64)

I 4

4.

I 4.-

-I.

1.6 rn C-n m

M, CA) 1.5 1.4 1.3

REFERENCE:

T.S. 3.2.2:

I_.

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

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

FIGURE 5.2-5 110

.0 ;

.AAb

-14

-4.

l0 60

C)

SSES UNIT 1 CYCLE 13

(.,.

Vd) ri~

--I 3.0 2.9 2.8 2.7 2.6 2.5

-I4 CA13 I-h~

" 2.4 E:1 2.3 vi on 2.2 1!

g2.1 a 2.0 1.9 1.8 m

-I m

S-1 r%)

CD) 1.7 1.6 1.5 1.4 (100,1.64) 1.3 _-

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

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

FIGURE 5.2-6 100 N 0 al 0

9b

PL-NF-02-001 Rev. 1 Page 19of34 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)

Position 45 0.470 0.480 0.490 0.500 0.10 0.520 39 0.630 0.676 0.722 0.768 0.814 0.860 25

.1.500 1582 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 07/28/2003

f: ::.

0.

~PL-NF-0.2-001 R~~~ev.

1 Page 20 of 34 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The LHGR limits are specified below as a function of Main Turbine Bypass operability for each fuel type as follows:

Main Turbine Bvpass Onerable

.The LHGR for ATRIUMTM-1 0 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.

Main Turbine Bvpass Inoperable The LHGR for ATRIUMT'-10 fuel shall not exceed the UHGR limit determined from Figure 6.2-2.

The LHGR limits in Figures 6.2-1 and 62-2 are valid for Two Loop and Single Loop operation.

SUSQUEHANNA UNIT 1 TRM/3.2-21 SEFFECTIVE DATE 07/28/2003

(.

(

i

('Allen SSES UNIT I CYCLE 13 tli Li)

C=

q-f1

--i CA)

T R 16

'14 -

0e i

I 0010 0

5-J a

a s

a l SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 0.0,13.4. *

' 15000.0,i3.4- "- ' *. * '- ' * * * ' **.',-*'-

REFERENCE:

T.S. 3.2.3 1

l

~~~

~.

a a

a USED IN DETERMINING FDLRX l

.4._.

5 6

'0 I

@

l

I.

S

5 5 5 5 5 S 5 a a aw a p g

e..e.&...S.......

4. 4. b.b

@w,,

1,*., *,...

4.. 4.

S 5 5 *

5

5 *

5 *

'l

S 5 5 5f.

5

. 550.

5.

5. 5 Sg S

S, p,

5...

5

,,..,..,.,,.,...,.5u,....,...SS......

i

^,,,,,,,

5,

5 mn1

-n m

m m

f%*)

6-A-v 0

10000 20000 30000 40000 50000 6

Average Planar Exposure (MWDIMTU)

LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS OPERABLE ATRIUMTM.10 FUEL FIGURE 6.2-1 60000

70000, a~ 0 to 5 5*50 0

-P

(1):

SEUN C

SSES UNIT 1.CYCLE 13 C

d (A

C=

-*1 Jo T.)

16 14

-S 10.

I.

I, a

S bC a a :

a :

a a a a : ~

SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS a.

a a

a.

a a

a VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 I-n

-l.2.

.s--

a.-.

a a

a

a a a a* a aa a

a aa a

REFERENCE:

TaS. 3.2 3 and 3.7.6 0.0,12.3:

15000.0,12.3 a

aaaaaaas 0.0,13 '

@ 10Q0,02.3

@ l ye s

§ e@

l UED INDEr-TERMINING FDLRX

..aa...a..

S.~~~~~~~~~~~~~~~~0..

0..

.S

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

a.

a a

a

59400,7.3 a

a r

,_**,a.,d,,,

l,,*,+....a....a....a..d.....b....a..'....a..J...A..S...

l a

a a

a 2

a a

A a

M a

a

' a a

a a

A a a

O A aa a

a a

a a a a

a a

'.a a

a a

_.X.4.

.b....s.i...

W.b...._.....b..

a a

a

'a a

a s a a

a a

a '

a a

p a _

a a

a.

a a

a

'a a :

a a

a

_ a a

a a

'a a

a a ~

~

a a

aL a

a a

._.a_.

M

-n m

4-4

-4 r1%3 CA) 6 4

0 100010 20000 30000 40000' 50000 6

Average Planar Exposure (MWD/MTU)

LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE MAIN TURBINE BYPASS INOPERABLE ATRIUMTm-10 FUEL FIGURE 6.2-2 60000 70000.

M M m

%o 6

$)

0

'P.

-A

P-L-NF-02-001 Rev. 1 Page 23 of 34 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 Descrintion The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRB) shall be established as specified in Table 7.2-1 and Table 7.2-2, including any adjustments per Technical Specification LCO 3.2.4.

Technical Specification LCO 3.2.4 provides an option to adjust the APRM setpoints when MFLPD is greater than FRACTION OF RATED THERMAL POWER (FRTP). The adjustment applies to both the APRM flow biased simulated thermal power-upscale scram trip setpoint and flow biased neutron flux-upscale control rod block trip setpoint for Two Loop and Single Loop operation. The APRM setpoints for Specification 3.2.4 are established in Tables 7.2-1 and 7.2-2.

SUSQUEHANNA UNIT I TRM/3.2-24 E

EFFECTIVE DATE 07/28/2003

PL!-NF-02-001 Rev. 1 Page 24 of 34 Table 7.2-1 APRM Setpoint for Two Loop Operation Trip Setpoint S * (0.58W + 59%) T Snp < (0.58W + 50%) T

- - Allowable Value

_S <(0.58W + 62%) T' SRB * (0.58W + 53%1) T i

Table 7.2-2 APRM Setpoint for Single Loop Operation Trip Setpoint Allowable Value IS < (0.58W +F 540%) T -S

(0.58W + 57%) T.

SRB < (0.58W + 45%) T SRB < (0.58W + 48%) T where: S and Sm are in percent of RATED THERMAL POWER W =

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

=

Lowest value of the ratio of FRTP divided by the.MFLPD. 2 The FLPD is the actual LHGR divided by the applicable LHGR limit for APRM Setpoints. The LHGR limit for APRM setpoints for ATRIUMm-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 07/28/2003

I C,1.I

~

C)

SSES UNIT 1 CYCLE 13 ja:

18 16

--I r..3 0cn E

0 10 -

8-S a a a

a a

a.

a a

a...aa a

a a

aEaEa a

Ea Ca a

a. 3.

a2 a4 1a a

a a

a~W a r

af a

a

a a

a I

Ia a

a.

SE aI a

aETER INIa FO aLK a

a

a.

a a

115~~~~~~~~~~~~~~~~~~~

fta.

a a

a a..

a a

a

4E R R~~~~~4~g~ a a

a a

a

a.

.a.

a a... a

-r.

4a a

a a

a.

a a

.a a

a a

a-a 4

Anf a.a.a a

a a

a a~~~S a

a.

a a

aIa a

L a

J a

a a

a

..~I m

m m

m

'-"I

-I.

4=

wA 6 1 10000 20000 30000 40000 50000 60000 Average Planar Exposure (MWDIMTU)

LINEAR HEAT GENERATION RATE LIMIT FOR APRM SETPOINTS VERSUS AVERAGE PLANAR EXPOSURE ATRIUM~m -10 FUEL FIGURE 7.a-l

70000, 0I 0~

ft

PLkNF-02-001 Rev. I Page 26 of 34 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION 8.1 Technical Specification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Description APLHGR The APLHGR limit for ATRIUM Th -10 fuel shall be equal to the APLHGR Umit from Figure 8.2-1.

The APLHGR limits in Figure 82-1 are valid for Main Turbine Bypass Operable and Inoperable and EOC-RPT Operable and Inoperable In Single Loop operation.

Minimum Critical Power Ratio Limit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limit for all fuel types (ATRIUMT"-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 82-3: EOC-RPT and Main Turbine Bypass Operable frorm1BOC to EOC Figure 8.2-4: Main Turbine Bypass Inoperable i EOC-RPT Operable from BOC to EOC Figure 82-5: 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 ULmit; The LHGR limits for Single Loop Operation are defined in Section 6.0.

SUSQUEHANNA UNIT 1 TRM/3.2-27 EFFECTIVE DATE 07/28/2003

PL-NF-02-001 Rev. I Page 27 of 34 Average Power Range Monitor (APRM) Gain And Setpoints APRM setpoints and the LHGR limit for APRM setpoints for Single Loop operation are defined in Section 7.0.

SUSQUEHANNA UNIT-1 TRM/3.2-28 EFFECTIVE DATE 07/28/2003

(I)

~~~~~SSES UNIT 1 CYCLE 13 12

6 P.

S S

S S6S S

J a 5

£

S I

S S

S P

5' 5

P 5

5 P

P S~~~~~~~~~~~~~~~~~~~~~~U ED IN 0

RM NI G

ETAP A

I 0

REFERENCE.T.S..3.4.1.an 1165 co 9

S e

4S S

I S 0)r.

~

Cto*.

J..d..A..b..'....S...S...J..&..b..S...S...S..~

~~~~

I..I.I.b.S.

I.S..d.I*I.I,..1 7. ~ ~ ~

~

~.

.F..I..I..~~~~~~~~~~~~~~~~~~~~~~.~.

.w r

I r

4 I.

59400,5.4--..

M

~

01 0000 20000 30000 40000 50000 60000 70000 Average Planar Exposure (MWD/MJTU)

Ml ft

~~~AVERAGE PLANAR LINEAR HEAT GENERATIoN -RATE LIMIT VERSUS AVERAGE PLANAR EXPOSUREA CD SINGLE LOOP OPERATION 0

ATRIUMTM-10 FUELC)0 FIGURE 8.2-1

(lI

(,

C i' SSES UNIT I CYCLE 13 V) c-1 CA)

CA)4 2.6 2.5 2.4

2.3 0,

1 2.2 0.

0

-a.

> 2.1 I

I I

I I.

9 9-D A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME I

'1 t~~~~~~~1

.%uFIvff r

I I

I USED IN DETERMINING MFLCPR I

1

.9 V

I (30,2.20)

A-l r% ~ ~

L

4.

I M

D 2

n

'-4 F-I

--i CA) 2.0 1.9- _F ERENCE: T.S. 3.4.1 and 3.2.2

_ I 1.8 30 40 50 60 70 80 90 100 f.

L Total Core Flow (Mlbm/hr)

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

FIGURE 8.2-2 110 la :n l (Z _ z 0

ZS (D

6 v

A -

Of.

Nez/t (6

C>

e-,

C=

V-4-Hi 3.5 3.4 3.3 3.2 3.1 3.0

la,

= 2.9 E

C 4-

2. 2.7 Q0a 2.6 m 2.5 SSES UNIT 1 CYCLE 13

_L_

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERTION TIME SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES (25,2.81)

(30,2.81)

ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 USED IN DETERMINING MFLCPR

-A B-1

~~(38.5,2.20)

REFERENCE:

T.S. 3.4.1 and 3.2.2 2.4 m-n

-I, Im

-im

-J1 I%3 00

=0 CA) 2.3 2.2 2.1 2.0 1.9 (100,2.20) 20 30 40 50 60 CoreIPower (% RATED) 70 80 90 MCPR OPERATING LIMIT VERSUS CORE POWER EOC-RPT AND MAIN TURBINE BYPASS OPERABLE SINGLE LOOP OPERATION (BOC to EOC)

FIGURE 8.2-3 100 la mul

?

'U 2

0r 0

CA

(

(2 ~-

(3 SSES UNIT 1 CYCLE 13 LA) c m

P-4

--A

§~

3.5 3.4 3.3 3.2 3.1 i

I I

I 4

i i

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

.1 I

4.-

I

4.

I

_(25,3.07) l~~

~

~~~

4.l I

3.0

~x. 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

-I CA) r(3 r%)

im 2.8 c

2 2.7 0:

0 cc 2.6 L.

0 r

2 2.5 N

I IIlW SS*I*f I

1~~~~

~

2.,l~ftgsmml~

f k

I 4.

U~u iPli Ut: i =M1VII1PRAiI M~rL%&rml I

r 2.4 (40,2.8) f__

A (54.6,2.20) m

n

'1 m

C)m

-4

-i

-S%

co P5-2.3 2.2 2.1 2.0 1.9 (100,2.20)

I:1

{R ENCE: T.S. 3.4.1, 3.7.6, and 3.2.2 r

4.

I

4.

I.

I 9

4.

20 30 40 50 60 70 80 90 Core. Power (°/O RATED)

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

FIGURE 8.2-4 100 t.AN O

-A

0>

0 SSES UNIT 1 CYCLE 13 C>

Ln e-4 p-Iq 3.5 3.4 3.3 3.2 3.1 3.0 CA m

C-,

--I 1-4 m

it I.,

c~o

E 2.9 a 2.8 a 2.6 a.

U2 2.5 2.4 2.3 2.2 2.1 2.0 1.9 (100,2.20) 20 30 40 50 60 70 80 90 100 I

Core Power (% RATED)

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

FIGURE 8.2-5 02 (a

-I z

In1 6

6 f

PL-NF-02-001 Rev. 1 Page 33 of 34

9.0 REFERENCES

9.1 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 1 and 2 (March 1983),

and Volume 1 Supplement 3 (November 1990), 'Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis,'

Exxon Nuclear Company, Inc.

5. ANF-524(P)(A), Revision-2 and Supplement 1, Revision 2,,Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"

November 1990..

6. ANF-1 125(P)(A) and ANF-1 125(P)(A), Supplement I, ANFB Critical Power Correlation,' April 1990.

7. NEDC-32071 P, 'SAFERIGESTR-LOCA Loss of Coolant Accident Analysis,*

GE Nuclear Energy, May 1992.

8. NE-092-001 A, Revision 1, 'Ucensing Topical Report for Power Uprate With Increased Core Flow,' Pennsylvania Power & Ught Company, December 1992 and NRC SER (November 30,1993).

9. PL-NF-90-001, Supplement 1 -A, nApplication of Reactor Analysis Methods for BWR Design and Analysis: Loss of Feedwater Heating Changes and Use of RETRAN MOD 5.1,0 August 1995.

10. PL-NF-94-005-P-A, aTechnical 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.

SUSQUERANNA UNIT 1 TRM/3.2-34 EFFECTIVE DATE 07/28/2003

PL-NF-02-001

= X To t

~~~~Rev. 1 Page 34 of 34

12. ANF-89-98(P)(A) Revision 1 and Revision 1 Supplement 1, 'Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.

13. ANF-91-048(P)(A), uAdvanced 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 DExxon 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, mExxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.

17. EMF-1997(P)(A) Revision 0, "ANFB-10 Critical PowerOorrelatiori, 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, uApplication of Reactor Analysis Methods for BWR Design and Analysis: Application Enhancements," September 1999.

19. Caldon, Inc., TOPICAL REPORT: Improving Thermal Power Accuracy and Plant SafetyWhile Increasing Operating Power Level Using the LEFM' System, Engineering Report - 80P, March 1997.

20. Caldon, Inc., "Supplement to Topical Report ER-80P: Basis for a Power Uprate with the LEFM'Tm or LEFM CheckPlust System," Revision 0, Engineering Report ER-1 60P, May 2000.

21. EMF-85-74(P), -RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements 1 and 2, February 1998.

SUSQUEHANNA UNIT1-TRM/3.2-35 EFFECTIVE DATE 07/28/2003

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EMOVEVAGESP, 7 -..

0

-EMOEPAGS -7 i NSERT.PAGES DATe TRM I LOES-1 through TRM / LOES-6 TRM I LOES-1 through TRM I LOES-6 07/28/2003 TRM / 3.2-2 through TRM / 3.2-35 TRM /3.2-2 through TRM /3.2-35 07/2812003 a

a g:AUo Docs\\TRM Word\\TRM Rem~ove 1rrerthRem~nsSheIIUnit1,2.doc 07/2&W~

SUSQUEHANNA STEAM ELECTRIC STATION LISTOFEFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL) -

Section ritle 0 Effective Date TOC 1.0 2.0 TABLE OF CONTENTS USE AND APPLICATION Page TRM /1.0-1 Page TRM /1.0-2 Page TRM /1.0-3 PLANT PROGRAMS Page 2.0-1 Pages TRM / 2.0-2 through TRM /2.0-4 Pages TRM / 2.0-5 through TRM /2.0-7 Page TRM 12.0-8 Page TRM 1 2.0-9 Pages TRM / 2.0-10 through TRM /2.0-12 Page TRM / 2.0-13 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM / 3.0-2 Page TRM / 3.0-3 Page TRM / 3.0-4 7

3.1 REACTIVITY CONTROL Pages 3.1-1 through 3 Pages TRM / 3.1-7aam Pages TRM / 3.1 -9 66 Page TRM / 3.1;(0 \\

-3.1-9a 05/16/2003 08/31/1998 10/04/2002 08/31/1998 08/31/1998 06/25/2002 04/12/1999

)0-08130/2001 09/06/2002 04/12/1999 06/16/2000 04/0811999 03/15/2002 04/0811999 08/31/1998 06/05/2002 02/18/1999 02/18/1999 08131i/1998 07/28/2003 07/16/1999 11/28/2000 08/31/1998 12/17/1998 12/17/1998 03130J2001 12114/1998 06/27/2001 06/14/2002 12/14/1998 08/31/1998 05116/2003 04/02/1999 3.2 3.3 CORE OPERATINS LIMITS REPORT-Page 3.2-I Pagep tRMP >2 through TRM J 3.2-35 IN MT ATION PagTM / 3.3-1 through TRM 13.3-3 PagTRI 3.3-4

'~~es 3.3-5 through 3.3-8 Pages TRM / 3.3-9 and TRM I 3.3-9a Pages TRM / 3.3-10 and TRM / 3.3-11 Page TRM / 3.3-12 Pages TRM / 3.3-13 through TRM / 3.3-15 Page TRM / 3.3-16 Pages TRM / 3.3-17 and TRM / 3.3-18 Pages TRM I 3.3-19 through TRM /3.3-20 Page 3.3-21 Pages TRM I 3.3-22 through TRM /3.3-24 Page TRM / 3.3-25 I

SUSQUEHANNA - UNIT 2 TRM I LOESA EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date 3.4 REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 Pages 3.4-6 through 3.4-13 10/23/1998 08131/1998 3.5 EMERGENCY CORE COOLING AND RCIC Pages 3.5-1 through 3.5-3 Page TRM / 3.5-4 Pages 3.5-5 through 3.5-7 08/31/1998 04/17/2000 08/31/1998 3.6 CONTAINMENT Pages 3.6-1 through 3.6-4 Page TRM / 3.6-5 Page 3.6-6 Pages TRM 1 3.6-7 through TRM I 3.6-9 08/31/1998 01/0712002 08/31/1998 12/31/2002 3.7 3.8 PLANT SYSTEMS Pages TRM I 3.7-1 and TRM /3.7-2 Page 3.7-3 Pages TRM I 3.7-4 through TRM /3.7-10 Page TRM / 3.7-11 Pages TRM I 3.7-12 through TRM / 3.7-27 Pages TRM / 3.7-28 through TRM / 3.7-32 Page TRM / 3.7-33 Pages TRM / 3.7-34 through TRM /3.7-36 Pages 3.7-37 through 3.7-39 Pages TRM / 3.7-40 and TRM / 3.7-40a Pages 3.7-41 and 3.7-42 Pages 3.7-43 through 3.7-47 Page TRM / 3.7-48 Pages TRM / 3.7-49 and TRM / 3.7-50 Pages TRM / 3.7-51 and TRM / 3.7-52 Page TRM / 3.7-53 07/29/1999 08/31/1998 08/02/1999 01/21/2000 08/02/1999

-11/16/2001

10/05/2002 02/01/1!999 08/31/1998

- 08/11/2000 08/31/1998 10/1311998 03108/2003 03/09/2001 04/15/2003 07/29/1999 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 / 3.8-8 Page TRM / 3.8-9 Page 3.8-10 Page TRM / 3.8-11 Page TRM / 3.8-1 la Pages 3.8-12 through 3.8-14 Pages TRM / 3.8-15 through TRM / 3.8-17 Page 3.8-18 04/02/2002 08/31/1998 12/31/2002 04/02/2002 08/31/1998 08/24/2001 08/31/1998 04/02/2002 04/0212002 08/31/1998 -

04/02/2002 02/01/1999 SUSQUEHANNA - UNIT 2 TRM / LOES EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION UST OFEFFECTIVE SEC77ONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page TRM / 3.8-19 Page TRM / 3.8-20 Pages TRM / 3.8-21 through TRM / 3.8-23 Pages 3.8-24 and 3.8-25 04/02/2002 02/01/1999 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 08/30/1998 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 3.11-12 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 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM /3.12-5 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/1998 09/01/1998 08/31/1998 t04/02/2002 09/01/1998 08/31/1998 02/05/1999.

-08/31/1998 SUSQUEHANNA - UNIT 2 TRM / LOES-3 EFFECTIVE DATE 07/2812003

SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SEC77ONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date B 3.0 B 3.1 B 32 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 Pages TRM / B 3.0-11 through TRM I B 3.0-15 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 Page B 3.1-4 Pages TRM / B 3.1-5 through TRM / B 3.1-7 Page TRM / B 3.1-8 CORE OPERATING LIMITS BASES Page B 3.2-1 08131/1998 03115/2002 07/13/1999 08/31/1998 07/13/1999 02/18/1999 08/31/1998 B 3.3 B3.4 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 3.3-13 Page TRM / B 3.3-14 Page TRM / B 3.3-14a Page TRM / B 3.3-14b Page B 3.3-15 Page TRMIB 3.3-16 Page B 3.3-17 Pages TRM / B 3.3-20 through TRM / B 3.3-23 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 04/07/2000 08/31/1998 12129/2000 03121/2003 03J30/2001 08/31/1998

-06/25/2002 p6114/2002 06/14/2002 08/31/1998 04/07/2000

-08131/1998 05/1612003 08131/1998 10/15/1999 08/31/1998 B3.5 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08131/1998 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 Pages TRM / B 3.6-6 through TRM / B 3.6-11 07/26/2001 02/01/1999 08/31/1998 0912311999 01/07/2002 12/31/2002 SUSQUEHANNA - UNIT 2 TRM / LOES-4 EFFECTIVE DATE 07/28/2003 SUSQUEHANNA - UNIT 2 TRM / LOES-4 EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date B 3.7 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 I 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 3.7-1 Oa Pages TRM / B 3.7-11 through TRM I B 3.7-14 Page TRM / B 3.7-14a Pages TRM / B 3.7-15 and TRM / B 3.7-16 Pages B 3.7-17 through B 3.7-20 Pages TRM / B 3.7-21 through TRM/B 3.7-21 a Pages TRMJB 3.7-22 and TRMIB 3.7-23 Pages B 3.7-24 through B 3.7-30 Pages TRM / B 3.7-31 and TRM / B 3.7-32 Page TRM / B 3.7-33 Pages TRM / B 3.7-34 and TRM I B 3.7-35 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRM I B 3.8-2 Page TRM I B 3.8-2a Page TRM I B 3.8-3 Page TRM I B 3.8-3a.

Page TRM I-B 3.8-4 Page TRM I B 3.8-4a.

Page TRM I B 3.8-5 Pages TRM / B 3.8-6 through TRM /I B 3.8-17 REFUELING OPERATIONS BASES Pages B 3.9-1 and B 3.9-2 Pages B 3.9-3 through B 3.9-7 08/31/1998 08/02/1999 08/02/1999 08/02/1999 08/02/1999 08/0211999 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 04/02/2002 04/02/2002 04/02/2002

.04/02/2002 04/0212002 04/0212002 08/31/1998 04/0212002 08131/1 998 10/2311998 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 /B 3.10-5 Pages TRM I B 3.10-6 and TRM /3.10-7 08131/1998 03/08/2003 08/23/1999 04/17/2002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 Pages TRM/ B 3.11-10

-Pages TRMIB 3.11-11 and TRMIB 3.11-11a Pages TRM/B 3.11-12 and TRAMB 3.1 1-13 Page TRM / B 3.11-14 Page TRM/B 3.11-15 Pages B 3.11-16 through B 3.11-19 Page TRM / B 3.11-20 08/31/1998 02/01/1999 04/07/2000 02/01/1999 11/01/1999 02/01/1999 08131/1998 04/02/2002 SUSQUEHANNA - UNIT 2 TRM / LOES-5 EFFECTIVE DATE 07/28/2003

SUSQUEHANNA STEAM ELECTRIC STATION UST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page TRM / B 3.11-20a Pages TRM I B 3.11-21 through TRM I B 3.11-23 Page TRM / B 3.11-23a Page TRM / B 3.11-24 Page TRM/ B 3.11-25 Pages B 3.11-26 through B 3.11-35 Pages TRM / B 3.11-36 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM / B 3.12-1 through TRM I B 3.12-3 04/02/2002 04102/2002 04/02/2002 03/21/2003 04/15/2003 08/31/1998 02/12/1999 02105/1999 g:'JUC DomrMM WwdlrrRM Mana1O.OktUnit 2/U2RM-LOES doc SUSQUEHANNA - UNIT 2 TRM I LOES-6 EFFECTIVE DATE 07/28/2003 SUSQUEHANNA - UNIT 2 TRM / LOES-6 EFFECTIVE DATE 07/28/2003

PL-NF-03-001 Rev. I Page 1 of 34 Susquehanna SES Unit 2 Cycle 12_

CORE OPERATING LIMITS REPORT

-Nuclear Fuels Engineering July 2003 Ia mu--

r%

0

'w NI

-El SUSQUEHANNA UNIT 2 TRM/3.2-2 EFFECTIVE DATE 07/28/2003

P.L-NF-03o-01 Rev. I Page 2 of 34 CORE OPERATING LIMITS REPORT REVISION DESCRIPTION INDEX Rev.

Affected I

No.

Sections Description/Purpose of Revision 0

1 ALL 5.0 6.0 8.0 Issuance of this COLR is in support of Unit 2 Cycle 12 operation.

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

This revision was generated in response to Facility Operating Ucense Amendment 185 which altered SR 3.7.6.1.

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

d.

FORM NFP-QA-008-2, Rev. I SUSQUEHANNA UNIT 2 TRM/3.2-3 EFFECTIVE DATE 07/28/2003

-P-LbNF-03-001 Rev. 1 Page 3 of 34 SUSQUEHANNA STEAM ELECTRIC STATION Unit 2 Cycle 12 CORE OPERATING UIMITS REPORT Table of Contents

1.0 INTRODUCTION

......................................................4 2.0 DEFINITIONS.........................................e..............5 3.0 SHUTDOWN MARGIN.................................................6

-4.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR).7...........

5.0 MINIMUM CRITICAL POWER RATIO (MCPR).............

9 6.0 LINEAR HEAT GENERATION RATE (LHGR................................20 7.0 AVERAGE POWER RANGE MONITOR (APRM) GAIN AND SETPOINTS.........23 8.0 RECIRCULATION LOOPS - SINGLE LOOP OPERATION......................26 9.D REFERENCES.......................................................

33 SUSQUEHANNA UNIT 2 TRM/3.2-4 EFFECTIVE DATE 07/28/2003

PLU-NF-03-001 Rev. I Page 4 of 34

1.0 INTRODUCTION

This CORE OPERATING LIMITS REPORT for Susquehanna Unit 2 Cycle 12 is prepared in accordance with the requirements of Susquehanna Unit 2, Technical Specification 5.6.5. As required by Technical Specifications 5.6.5, core shutdown margin, the core operating limits and APRM 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 TRM/3.2-5 EFFECTIVE DATE 07/28/2003

PL-NF-03-001 Rev. 1 Page-5 of 34 2.0 DEFINMONS 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 (FRTPishall be the measured THERMAL POWER divided by the RATED THERMAL POWER.

2.5 FDLRX is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR limit for the applicable fuel bundle type.

2.6 MFLCPR is the ratio of the applicable MCPR operating limit for the applicable fuel bundle type divided by the MCPR calculated by the core monitoring system for each fuel bundle.

2.7 MAPRAT is the ratio of the maximum APLHGR calculated by the core monitoring system for each fuel bundle divided by the APLGHR limit for the applicable fuel bundle type.

2.8 FDLRC is the ratio of the maximum LHGR calculated by the core monitoring system for each fuel bundle divided by the LHGR for APRM Setpoint Limit for the applicable fuel bundle type.

SUSQUEHANNA UNIT 2 TRM/3.2-6 EFFECTIVE DATE 07/28/2003

Pb-NF-3-oO1 Rev. 1 Page 6 of 34 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/ with the highest worth rod determined by test Since core reactivity will vary during the cycle as a function of fuel depletion and -

poison bumup, Beginning of Cycle (BOC) SHUTDOWN MARGIN (SDM) tests must also account for changes in core reactivity during the cycle. Therefore, the SDM measured at BOC must be equal to or greater than the applicable requirement from either 3.2.a or 3.2.b plus an adder, "R". The adder, "R", is the difference between the calculated value of maximum core reactivity (that is, minimum SDM) during the operating cycle and the calculated BOC core reactivity. If the value of 'R" is zero (that is, BOC is the most reactive point in the cycle) no correction to the BOG measured value is required..

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

SUSQUEHANNA UNIT 2 TRM/3.2-7 EFFECTIVE DATE 07/28/2003

PL-NF-03-O01 Rev. I Page 7 of 34 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 and EOC-RPT Operable and Inoperable in Two Loop operation.

The APLHGR limits for Single Loop operation are provided in Section 8.0.

SUSQUEHANNA UNIT 2 TRM/3.2-8 EFFECTIVE DATE 07/28/2003

CZ8 c;/

C5 Ln m

I 14=

-I4 N)1 SSES UNIT 2 CYCLE 12 16 14 II N

.2.I 0m1 m0im P1 E

J S

S S

S 5

5 5

.5.5

.S.S

-0.0,11.5

~

~ ~

5 5

S 5

5 5

5

:~.

: : : : : : : : : : : : : : : REF R.N.

T.S. 3.2.1.:

4 S

5 5

.5 5

5..

S

.5

.5 5.5 5.S.

S S

IJ..

S.

.5.5.5.5.5.5.5.

5 S

S S

5 5

I.~~~~~~~I r

5 5

5 S

5 5

5M OO,5.

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5~~~~-

I 5 5r 5

5 I

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CD) 6 4

I 0

10000 20000 30000 40000 50000

'Average Planar Exposure (MWD/MTU)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE TWO LOOP OPERATION ATRIUMTM'10 FUEL FIGURE 4.2-1 60000 70000 CDZ oco 65 A

PL-NF-03-001 Rev. 1 Page 9 of 34 5.0 MINIMUM CRMCAL 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 0) shall be the greater of the Flow-Dependent or the Power-Dependent MCPR, depending on the applicable equipment operability status.

a)

EOC-RPT and Main Turbine Bypass Operable Figure 5.2-1: Flow-Dependent MCPR value determined from BOC to EOC Figure 5.2-2: Power-Dependent MCPR value determined from BOC to EOC b)

Main Turbine Bypass Inoperable / EOC-RPT Operable Figure 5.2-3: Flow-Dependent MCPR value determined-from BOC.to EOC Figure 5.2-4: Power-Dependent MCPR value determined from BOC to EOC C)

EOC-RPT Inoperable I Main Turbine Bypass Operable -

Figure 5.2-5: Flow-Dependent MCPR value determined from BOC'to EOC Figure 5.2-6: Power-Dependent MCPR value determined from BOC to EOC The MCPR limits in Figures 5.2-1 through 52-6 are valid for Two Loop operation.

The MCPR limits for Single Loop operation are provided in Section 8.0.

5.3 Average Scram Time Fraction Table 5.3-1 provides the relationship between average scram time to control rod position and scram time fraction. The evaluation of scram insertion time data, as it relates to the attached table should be performed per Reactor Engineering procedures.

SUSQUEHANNA UNIT 2 TRM/3.2-10 EFFECTIVE DATE 07/28/2003

v

=

v

=

PL-NF-03-001 Rev. 1 Page 10 of 34 EOC-RPT and Main Turbine Bypass Operable SUSQUEHANNA UNIT 2 TRM/3.2-11 EFFECTIVE DATE 07/28/2003

(:

(C

(

m 1-4 r%a SSES UNIT 2 CYCLE 12 2.3 2.2 2.1 2.0 l~~~~~

I I

I LEGEND ICURVE 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 E

~~~~~~USED IN DETERMINING MFLCPR

_1_

i-a3 "3%

E 1.9

0. 1.8 0

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-(30,1.56)-

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- 4 I..

(108,1.49)

(108,1.47)

I c..Z.z-w In

-=

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-tw.

-

4 I

4.

REFERENCE:

T.S. 3.2.21

" " a w m n O B

. I Ia a

a.,

a l

I (60,1.47)

4.

4

4.

.1 I

1.3 I

I 4

4.

1 I

4.

1.

.1 30 60 40 50 70 80 9o 110 100 I § : Total Core Flow (MLBIHR)

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

FIGURE 5.2-1

-U

-4.

0

-h m r-0w6.

0

("I SSES UNIT 2 CYCLE 12 C

(A CA C=

m i

,-I 3.0 2.9 2.8 2.7 2.6 2.5 2.4 CA>

i 2.3 1 2.2 OL 2.1 IC o 2.0 1.9 l__lLEGEND 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 (25,2.30) 1 eza:

0,.2)

USE

=I

N DETERMINING MFLCPR=

0X;0 X DDX<(40,1.7)

(80,1.49)

REFERENCE:

T.S. 3.2.2

.~~~ ~~~~~~~~t

',.I 47).,.

1.8 m

.9-.

m

-I m

ci, CA) 1.7 1.6 1.5 1.4 1.3 (100,1.49)

(100,1.47) 20 30 40 50 60 70 80 90 100 I

Core Power (/O RATED)

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

FIGURE 5.2-2 to

-9.0

-A

-U z

0 0

PL-NF-03-001 Rev.

Page ISof 34 Main Turbine Bypass Inoperable IEOC-RPT Operable SUSQUEHANNA UNIT 2 TRM/3.2-14 EFFECTIVE DATE 07/28/2003

(

f

\\.,:,,,,1" c,

LA JC

--I SSES UNIT 2 CYCLE 12 2.3 2.2

.9 I

A A

LI~r ID A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.1 I

4 4-I~~~~~~~~~~.fl lour.

I 2.0

'9 4-I I

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

CIO

'-A 01 E 1.9 en 0,c 1 1.8 0.0 I1 o' 1.7.

a 1

I I

I

-I USED IN DETERMINING MFLCPR I

(30,1.79) 3 3

3 A

3= B

- 08,1.7) 1.6 m

F-4 Q-4 m

-4 m

CA) 1.5 1.4 1.3

REFERENCE:

T.S. 3.7.6 and 3.22 I 4.

.9 I

I.

I I

Y I

I

. I 4

4 I

I

- 4 I

1.

5 30 40 50 60 70 80 90 100 110 I

Total Core Flow (MLB/HR)

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

FIGURE 5.2-3 (a

0) 4-h r 0 0-4

(:

(.A (In m

-I'.

ra SSES UNIT 2 CYCLE 12 3.0 2.9 2.8 2.7 2.6

-(25,2.54)-

=

LEGEND CURVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME CURVE B: REALISTIC AVERAGE SCRAM INSERT1ON TIME I

I II I

2.5 A 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 CA) f%3 I-a

= 2.4 E_i 2.3 0I c 2.2 g 2.1

a. 2.0 1.9 L

I I

1.8

\\

.L.......

USED IN DETERMINING MFLCPR (40,2.02)

A 3

(60.1,1.79) i

REFERENCE:

T.S. 3.7.6 an (100,1.79)

-n rn C-q CA:

L m

1.7 1.6 1.5 1.4 1.3 20 30 40 50 60 70 80 90 100 I

Core Power (% RATED)

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

FIGURE 5.2-4 ID m.

Co.1 (D 'Z on 6

v a

PL-NF-03-001 Rev.

Page 16 of 34 EOC=RPT InoperableI Main Turbine Bypass Operable

~~

_i SUSQUEHANNA UNIT 2 TRM/3.2-17 EFFECTIVE DATE 07/28/2003

C

(

I :'

in D,

c-A SSES UNIT 2 CYCLE 12 2.3 2.2 I

I I

D A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME 2.1 I

.&~~~~~~Iru~~~ rn,1I I

2.0 I

I.

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2

.K 03 E 1.9 3CD

! 1.8 Qa1 0

5 1.7 I

i II I

II USED IN DETERMINING MFLCPR

_I I

I N

7

_______ I

_______ iI _______

-(30,1.56) 1.6 -

9 I

7

9 1

'9 9.

.A I

B (108,1.56) rann

-n m

C-)

-I

-4c ran Coi NJ 0;

CA) 4 I

4.

4-

.~~~~

1.5 1.4 I.I I

REFERENCE:

T.S. 3.3.4.1 and 3.2.21

.~~

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

1.3 30 40 50 60 70 80 90 100 110 I

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

-a CD 0-4 CD-u z

0 0

0

f

(

( P (n

C=

m t

'4 NJ SSES UNIT 2 CYCLE 12 3.0 2.9 2.8 2.7 2.6 I

I II I

4*

4-4 GENDu RVE A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME WVE B: REALISTIC AVERAGE SCRAM INSERTION TIME I

4.

2.5 I

4.

4-4~~~~~~~~~~~~~~~~~~~~~~~~~~~

I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 24r CA)

I',

toa E

2.3m C 2.2 b

.1 m 2.0 U

1.9 (25,2.31).

I I

i I

-4

4.

4-4~~~~~~~~~~~~~~~~~~~~~~~~~~~~

1.8 B(30,22

REFERENCE:

TIS. 3.3.4.1 and I

2L

-REd8RE'E: T.S. 3.3.4.1 and 3.2.

(

-74,15C)-

m n

-n

'-9I m

-1

"'3 Col 1.7 1.6 1.5 1.4 1.3 (100,1.56) 20 30 40 50 60 70 80 90 100 Core Power (%/6 RATED)

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

FIGURE 5.2-6

-o (0

co 4.WI CD

-LI 10, I-l z

00

PL-NF-03-001 Rev. 1 Page 19 of 34 Table 5.3-1 Average Scram Time Fraction Table For Use With Scram Time Dependent MCPR Operating Limits Control Rod Average Scram Time to Position (seconds)

Position 45 0.470 0.480 0.490 0.500 0.510 0.520 39 0.630 0.676 0.722 0.768 0.814 0.860 25 1.500 1.582 ff1.664 1.746 1.828 1.910 5

2.700 2.848 2.996 3.144 3.292 3.440 Scram Time 0.000 0.200 0.400 0.600 0.800 1.000 Fraction Average Scram Realistic Maximum Insertion Time Allowable SUSQUEHANNA UNIT 2 TRM/3.2-20 EFFECTIVE DATE 07/28/2003

PL-NF-03-001 Rev. 1 Page 20 of 34 6.0 LINEAR HEAT GENERATION RATE (LHGR) 6.1 Technical Specification Reference Technical Specification 3.2.3 and 3.7.6 6.2 Description The LHGR limits are specified below as a function of Main Turbine Bypass operability for each fuel type as follows:

Main Turbine Bvpass Operable The LHGR for ATRIUMT'-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-1.

Main Turbine Bvpass Inoperable The LHGR for ATRIUMT'-10 fuel shall not exceed the LHGR limit determined from Figure 6.2-2.

The LHGR limits in Figures 6.2-1 and 6.2-2 are valid for-Two Loop and Single Loop operation.

SUSQUEHANNA UNIT 2 TRM/3.2-21 EFFECTIVE DATE 07/28/2003

16

~~~~SSES UNIT 2 CYCLE 12 SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES-ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 140.0,13.4"?1500134:'

i REEENCE:T.S. 3.23-3 I

I t~

~

~~~~~

CA) r1310.......

r......................................

... 1 6

4 6

a.

-4 s

s a

aI s

a a

g a

a s

a a

-n r.

T..

r.

I 6-l

,I

'r __ __ __

rn

'700020003000000500000070 rn~~~~~~~~~~~~~~~~~~~~~~~~~

4 1 ~

LNA ETGNRAINRT II ESSAVRG LNREPSR LINE HAT EN MATIN RTURIE BYPAVESUS OPERAGLE PLNR XOSR ATRIUM~t'l FUEL FIGURE 6.2-1

16

~~~~SSES UNIT 2 CYCLE 12

.SAFETY ANALYSES ASSUME THAT TWO OR MORE BYPASS VALVES ARE INOPERABLE PER SR 3.7.6.1 OR 3.7.6.2 14.-

REFERENCE:

T.S. 3.2.3 and.7.6 PO U

I U

U I.

I.

I S.U I.S S.

USDINDTEMNN G FLR X

..12.-

W c

S m

8

d.

-I, S

S S

I~~~~~~~~1 S

~

.s

.0 4...

.v

'~~~~~~~~~~~~~~~~~~~~~~~1~~~~~~60063 m

6..

I...:..d..&

4~~~~~~~~

IS 000100200300.

00 o

00 00 s

g

a a

u S

I I

U m

S I

I I

s s

I m

Ula M

l I

PO AveragU I

I I

5.

S I

S Plnr xosr (M

DM U S I

ICDS S

r U

S S

~

S I

S ~

g I

S S

I I

U I

I S

S S

S I

S U

ATRIUMM10 FUEL~~~0 FIGURE 6.2-2

PL-NF-03-001 Rev. 1 Page 23 of 34 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 (So) 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 -nd Single Loop operation. The APRM setpoints for Specification 3.2.4 are established in Tables 7.2-1 and 7.2-2.

SUSQUEHANNA UNIT 2 TRM/3.2-24 EFFECTIVE DATE 07/28/2003

PL-NF-03-001 Reov. 1 Page 24 of 34 Table 7.2-1 APRM Setpoint for Two Loop Operation Trip Setpoint Allowable Value S < (0.58W + 59%) T S * (0.58W + 62%) T'7 SRB:5 <0.58W + 50%) T SRB 0.58W + 53%) T Table 72-2 APRM Setpoint for Single Loop Operation Trip Setpoint Allowable Value S s (0.58W + 54%) T S S (0.58W + 57/6) T SRFB S 0;58W + 45%) T SRB S (0.58W + 48%) T where: S and SRB are in percent of RATED THERMAL POWER W -

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

=

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

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

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

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

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

4 ~~:

4 SUSQUEHANNA UNIT 2 TRM/3.2-25 EFFECTIVE DATE 07/28/2003

CA 16

~SSES UNIT 2CYCLE 12 0.0115.0 a~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

.a a

EFERENCE: T.S. 3.2.

12.P4.-1 LI.

3

.b..I~~~~~a.....

.I*A.I 67000,81.03 4

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

a a

MI ~

~

~ ~ ~

a a

a' a

a a

a <

cow a

a a

a a2a a

0. a a0a 00a a4a0000 a

a a

a.

a a0a 0 a7a.0a0 a

a a

a A

vae5'ag Panar axpaura aMWaMTa O

a a

a a.

a a

5 5

-5 4~~~~~~~~~~~~~IUE7.-

~

P -NF-03-001 Rev. 1 Page 26 of 34 8.0 RECIRCULATION LOOPS - SINGLE LOOP-OPERATION 8.1 Technical SDecification Reference Technical Specification 3.2.1, 3.2.2, 3.2.3, 3.2.4, 3.3.4.1, 3.4.1, and 3.7.6 8.2 Descrintion APLHGR The APLHGR limit for ATRIUMk-1 0 fuel shall be equal to the APLHGR Umit 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 Umit The MCPR limit is specified as a function of core power, core flow, and plant equipment operability status. The MCPR limit for all fuel types (ATRIUMT-1 0) 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 82-3: 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 82-5: EOC-RPT Inoperable I Main Turbine Bypass Operable from BOC to EOC The MCPR limits in Figures 8.2-2 through 82-5 are valid only for Single Loop operation.

- Linear Heat Generation Rate Umit The LHGR limits for Single Loop Operation are defined in Section 6.0.

SUSQUEHANNA UNIT 2 TRM/3.2-27 EFFECTIVE DATE 07/28/2003

PL-NF-03-001 Rev. 1 Page 27 of 34 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 2 TRM/3.2-28 EFFECTIVE DATE 07/28/2003

u(:

Alp.

r-

\\

wr LA c:~ 1 rtn C=

m i

14

'.-4--4 SSES UNIT 2 CYCLE 12

-4i NJ

-n

'-c4m CD) 12I E

a.

6 SS..............5

~~~*

..L

: : : :~..

EFE.NC..S3467nd00.S.....

4 0

10000 20000 30000 40000 50000 60000

'Average Planar Exposure (MWD/IMTU)

AVERAGE PLANAR LINEAR HEAT GENERATION RATE LIMIT VERSUS AVERAGE PLANAR EXPOSURE SINGLE LOOP OPERATION ATRIUMTM-10 FUEL FIGURE 822-1 70000 CD.

aCOI

1 c

C,)

AD C,)'

rN, o.-I PO

--I SSES UNIT 2 CYCLE 12 2.6 2.5 2.4

'E 2.3 0) c.5 i.e

- 2.2 0

0 2

0.

2 2.1

.9 Y

1 1

I 1

4.

4 I.

4-4 loITRn D

A: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME B: REALISTIC AVERAGE SCRAM INSERTION TIME 3

Y I

I I

.9 I

USED IN DETERMINING MFLCPR 3

I (30,2.20) 4.

A -B

.9 I

I I

.9 11"l

'I pvv.,2.20) 1*

F 1

.9

'9

.9

.9 c

.n n

-n m

rN,

-S CD) 2.0 1.9

_ I

REFERENCE:

T.S. 3.4.1 nd 3.2.2-

_ _ _ _ _ _ _ _ _ _ _ I 1.8 30 40 50 60 70 80 90 100 110 0

Total Core Flow (MLBEHR)

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

FIGURE 8.2-2 w

r-(D Z

co 0

a 03

-h

(

(j

(.'

Li, JC U,_I

-4i

-*1 SSES UNIT 2 CYCLE 12 3.5 I

Y Y

I I

I LEGEND 3.4 I

4 3.3 32 3.1 -I_~~~1-W' I__

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

3.0 I 4

6.

4.-4 I

SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 C~a I-.'

E 2.9 n 2.8 M 2.7 0m 2.6 0.2 2.5 (25,2.75)

_____l USED IN DETERMINING MFLCPR (30,2.69)

(39.4,2.20) 2.4 m

m

-1 1-4 9-I m

'-1 "A) 00 CA, 2.3 2.2 2.1 2.0 (100,2.20)

.I 1.

I

REFERENCE:

T.S. 3.4.1 and 3.2.21 -,

4 1

i

1 I

I 1.9 -

2C I

4 1

I D

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

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

FIGURE 8.2-3 la m (D

03 0

W-9 I.-

z-n 6

Tb 00

(.

(/I Jo CA) r%)

CA3 rPO SSES UNIT 2 CYCLE 12 C.

3.5 3.4 3.3 3.2 3.1 3.0 n 2.9 a 2.8 c

0 2.7 C.

0a 2.6 2.5 2.4 m

C-)I F-4 m

-q m

C3 2.3 2.2 2.1 2.0 1.9 (100,2.20) 20 30 40 50 60 70 80 90 Core Power (% RATED)

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

FIGURE 8.2-4.

100 ID, 0

co (D

I.

-u z

0 0

C:

LA C=

G)

C C

M 2

3-r-r.3 SSES UNIT 2 CYCLE 12 3.5 3.4 3.3 3.2 3.1 U

9 I

I I

LtbuPND I

I _ tifllolVf A,: MAXIMUM ALLOWABLE AVERAGE SCRAM INSERTION TIME

REALISTIC AVERAGE SCRAM INSERTION TIME I

4 4-3

4.

.9-3.0 0

I SAFETY ANALYSES ASSUME THAT FOUR BYPASS VALVES ARE OPERABLE PER SR 3.7.6.1 AND 3.7.6.2 K

-I cR CA)

2.9

2.8 i 2.7 0.06

° 2.6 a 2.5 I

I 4

WI}_

-I USED IN DETERMINING MFLCPR (30,2.69)

-4.

4.

3 I"

4.

2.4

-~~L

~

A B-a (39.4,2.20)

M n

C-)

c

-91 r

-A 4=,,

-4

-S 0,

M CA 2.3 2.2 2.1 2.0 1.9 9

.9

4.

.9 T

I 1 1 1

(100,2.20) 00 I

4 1

4 4.

20 30 40 50 60

' 70 80 90 I.

Core Power (% RATED)

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

FIGURE &2-5 (0 M

'M z r CD o

-M.

0

PL-NF-03-001 Rev. 1 Page 33 of 34

9.0 REFERENCES

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

1. PL-NF-90-001 -A, "Application of Reactor Analysis Methods for BWR Design and Analysis," July 1992.

2. PL-NF-90-001, Supplement 1-A, Application of Reactor Analysis Methods for BWR Design and Analysis: Loss of Feedwater Heating Changes and Use of RETRAN MOD 5.1," August 1995.

3. PL-NF-90-001, Supplement 2-A, Application of Reactor Analysis Methods for BWR Design and Analysis: CASMO-3G Code and ANFB Critical Power Correlation," July 1996.

4. PL-NF-9M001, Supplement 3-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Application Enhancements," March 2001.

5. XN-NF-80-1 9(A), Volume 1, and Volume 1 Supplements 1 and 2 (March 1983),

and Volume 1 Supplement 3 (November 1990), "Exxon Nuclear Methodology for Boiling Water Reactors: Neutronic Methods for Design and Analysis,"

Exxon Nuclear Company, Inc.

6. XN-NF-80-1 9(P)(A), Volumes 2, 2A, 2B, and 2C "Exxon Nuclear Methodology for Boiling Water Reactors: EXEM BWR ECCS Evaluation Model," September 1982.

7. XN-NF-80-19(P)(A), Volume 3 Revision 2 "Exxon Nuclear Methodology for Boiling Water Reactors Thermex: Thermal Limits Methodology Summary Description," January 1987.

8. XN-NF-80-1 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, Inc. June 1986.

9. XN-NF-85-67(P)(A), Revision 1, "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel," Exxon Nuclear Company, Inc.,

September 1986.

10. ANF-524(P)(A), Revision 2 and Supplement 1, Revision 2, "Advanced Nuclear Fuels Corporation Critical Power Methodology for Boiling Water Reactors,"

November 1990.

11. NE-092-OO 1A, Revision 1, LUcensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power & Ught Company, December 1992 and NRC SER (November 30,1993).

SUSQUEHANNA UNIT 2 TRM/3.2-34 EFFECTIVE DATE 07/28/2003

PL-NF-03-001 Rev. 1 Page 34 of 34

12. ANF-89-98(P)(A) Revision 1 and Revision 1 Supplement 1, "Generic Mechanical Design Criteria for BWR Fuel Designs," Advanced Nuclear Fuels Corporation, May 1995.

13. ANF-91-048(P)(A), "Advanced Nuclear Fuels Corporation Methodology for Boiling Water Reactors EXEM BWR Evaluation Model," January 1993.

4. XN-NF-79-71(P)(A) Revision 2, Supplements 1, 2, and 3, 'Exxon Nuclear Plant Transient Methodology for Boiling Water Reactors," March 1986.

15. EMF-1 997(P)(A) Revision 0, *ANFB-1 0 Critical Power Correlation," July 1998, and EMF-1997(P)(A) Supplement 1 Revision 0, 8ANFB-10 Critical Power Correlation: High Local Peaking Results,' July 1998.

16. Caldon, Inc., 'TOPICAL REPORT: Improving Thermal Power Accuracy and Plant Safety While Increasing Operating Power Level Using the LEFM'~

System,' Engineering Report - 80P, March 1997.

17. Caidon, Inc., mS 4uplement to Topical Rport ER-BOP: Basis for a Power Uprate with the LEFM' or LEFM CheckPlus System," Revision 0, Engineering Report ER-160P, May 2000.

18. EMF-85-74(P)(A), -RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model," Revision 0, Supplements 1 and 2, February 1998.

19. EMF-21 58(P)(A), Revision 0, "Siemens Power Corporation Methodology for Boiling Water Reactors: Evaluation and Validation of CASMO-4/Microbum-B2," Siemens Power Corporation, October 1999.

SUSQUEHANNA UNIT 2 TRM/3.2-35 EFFECTIVE DATE 07/28/2003

ML032200317

Text

1.0 INTRODUCTION

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

9.0 REFERENCES

1.0 INTRODUCTION

1.0 INTRODUCTION

REFERENCE:

=I

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

REFERENCE:

9.0 REFERENCES

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