ML043490182

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Technical Requirements Manual Vol. 1, Revision 71, Dated 11/30/2004
ML043490182
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Issue date: 12/01/2004
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DETROIT EDISON - FERMI 2 AUTOMATED RECORD MANAGEMENT DISTRIBUTION CONTROL LIST 12/01/04 To: 00935 US NRC PAGE 1 DOCUMENT CNTRL DESK WASHINGTON, DC 20555 Media: 8 1/2 X 11 Number Cnt Issue DTC Doc. Serial Number Page Rev Copies Lv1 Date Sec Status TMTRM TRM VOL I 71 11 IR 11/30/04 AFC Please destroy or mark all revised, superseded, or cancelled documents as such. CONTROLLED stamps must be voided by lining through and initialing.

Detroit Edison EF2, C/O Info Mgmt 140 NOC, 6400 North Dixie Highway, Newport MI 48166. (734) 586-4338 OR (734) 586-4061 for questions or concerns.

Ref: e56075 W6

LICENSING DOCUMENT TRANSMITTAL FERMI 2 TECHNICAL REQUIREMENTS MANUAL - VOL I Revision 71 dated 11/30/04 Immediately, upon receipt of the item(s) below, please insert and/or remove the pages indicated.

Destroy the removed pages. Be sure that Revision 70 has been inserted prior to inserting these pages.

Location Remove Insert In Front of TRAM Manual Title Pa.ge.Rev 70 10/29/04 , Title Page Rev 71 11/30/04 Immediately following List of Effective Pages List of Effective Pages Title Page LEP-l through LEP- 4 Rev 70 10/29/04 LEP-l through LEP- 4 Rev 71 11/30/04 3.4 Reactor Coolant Page TRM 3.4-la Rev 34 Page TRM 3.4-la Rev 71 System Page TRM 3.4-lb Rev 34 Page TRM 3.4-lb Rev 71 3.6 Containment Systems Page TRM 3.6-13 Rev 31 Page TRM 3.6-13 Rev 71 BASES B3.4 Reactor Coolant Page TRM B3.4.1-2 Rev 34 Page TRM B3.4.1-2 Rev 71 System Page TRM B3.4.1-3 Rev 34 Page TRM B3.4.1-3 Rev 71 Page TRM B3.4.1-4 Rev 34 Page TRM B3.4.1-4 Rev 71 Page TRM B3.4.1-5 Rev 34 Page TRM B3.4:1-5 Rev 71 Core Operating Limits Report COLR Cycle 10, Revision I COLR Cycle 11, Revision 0 END

Fermi 2 Technical Requirements Manual Volume I Detroit Edison ARMS - INFORAM TION DTC: TMTRM I File: 1754 IDSN: TRM VOL I [ Rev: 71 Date 11/30/04 lRecipientq'.

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FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOL I LIST OF EFFECTIVE PAGES Page Revision Page Revision TRN 5.0-5 Revision 31 TRM B3.5-1 Revision 31 TRM 5.0-6 Revision 31 TRM B3.6.1-1 Revision 31 TRM 5.0-7 Revision 31 TRM B3.6.2-1 Revision 67 TRM 5.0-8 Revision 31 TRM B3.6.3-1 Revision 68 TRM 5.0-9 Revision 31 TRM B3.6.4-1 Revision 31 TRM B1.0-1 Revision 31 TRM B3.6.5-1 Revision 31 TRM B2.0-1 Revision 31 TRM B3.6.6-1 Revision 70 TRM B3.0-1 Revision 63 TRM B3.6.7-1 Revision 31 TRM B3.0-2 Revision 63 TRM B3.6.8-1 Revision 31 TRM B3.0-2a Revision 63 TRM B3.7.1-1 Revision 31 TRM B3.0-2b Revision 63 TRM B3.7.2-1 Revision 31 TRM B3.0-3 Revision 31 TRM B3.7.3-1 Revision 31 TRM B3.0-4 Revision 31 TRM B3.7.4-1 Revision 31 TRM B3.0-5 Revision 54 TRM B3.7.4-2 Revision 31 TRM B3.0-6 Revision 54 TRM B3.7.5-1 Revision 31 TRM B3.0-7 Revision 54 TRM B3.7.6-1 Revision 31 TRM B3.1-1 Revision 31 TRM B3.7.7-1 Revision 31 TRM B3.2-1 Revision 31 TRM B3.7.8-1 Revision 31 TRN B3.3.1-1 Revision 31 TRM B3.7.9-1 Revision 31 TRM B3.3.1-2 Revision 31 TRM B3.7.9-2 Revision 31 TRN B3.3.2-1 Revision 31 TRM B3.8.1-1 Revision 31 TRM B3.3.2-2 Revision 31 TRM B3.8.2-1 Revision 31 TRM B3.3.3-1 Revision 67 TRM B3.8.3-1 Revision 31 TRM B3.3.4-1 Revision 31 TRM B3.8.4-1 Revision 31 TRM B3.3.4-2 Revision 31 TRM B3.8.5-1 Revision 31 TRM B3.3.5-1 Revision 31 TRM B3.8.6-1 Revision 43 TRM B3.3.5-2 Revision 31 TRM B3.9.1-1 Revision 31 TRM B3.3.6-1 Revision 31 TRM B3.9.2-1 Revision 65 TRM B3.3.6-2 Revision 31 TRM B3.9.3-1. Revision 31 TRM B3.3.6-3 Revision 31 TRM B3.9.4-1 Revision 31 TRM B3.3.6-4 Revision 31 TRM B3.10-1 Revision 31 TRM B3.3.6-5 Revision 31 TRM B3.11.1-1 Revision 31 TRM B3.3.7-1 Revision 31 TRM B3.12.1-1 Revision 31 TRM B3.3.7-2 Revision 31 TRM B3.12.2-1 Revision 44 TRM B3.3.8-1 Revision 31 TRM B3.12.3-1 Revision 31 TRM B3.3.9-1 Revision 31 TRM B3.12.4-1 Revision 31 TRM B3.3.10-1 Revision 56 TRM B3.12.5-1 Revision 31 TRM B3.3.11-1 Revision 45 TRM B3.12.6-1 Revision 31 TRM B3.3.12-1 Revision 62 TRM B3.12.7-1 Revision 31 TRM B3.3.13-1 Revision 31 TRM B3.12.8-1 Revision 31 TRM B3.3.14-1 Revision 31 TRM B3.4.1-1 Revision 31 TRM B3.4.1-2 Revision 71 TRM B3.4.1-3 Revision 71 TRM B3.4.1-4 Revision 71 TRM B3.4.1-5 Revision 71 TRM B3.4.2-1 Revision 31 TRM B3.4.3-1 Revision 31 TRM B3.4.4-1 Revision 31 TRM B3.4.5-1 Revision 31 TRM B3.4.6-1 Revision 31 TRM B3.4.7-1 Revision 31 TRM Vol. I LEP-3 REV 71 11/30/04

FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOL I LIST OF EFFECTIVE PAGES CORE OPERATING LIMITS REPORT COLR 11, Revision 0 Page Revision Notation Page 1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0 18 0 19 0 20 0 21 0

  • 22 0 TRM Vol. I LEP-4 REV 71 11/30/04

Recirculation Loops Operating - Regions TR 3.4.1.1 TR 3.4 REACTOR COOLANT SYSTEM (RCS)

TR 3.4.1.1 Recirculation Loops Operating - Regions TRLCO 3.4.1.1 The reactor core shall not exhibit core thermal-hydraulic instablity or operate in the "Scram" or "Exit" Regions as defined in the Core Operating Limits Report (COLR).

I APPLICABILITY: MODE 1, within TS Action Statement 3.3.1.1.3 for RPS function 2.f. inoperable.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor core ------------NOTE---------------

operating in the Restart of an idle "Exit" Region. recirculation loop or resetting a recirculation flow limiter is not allowed.

A.1 Initiate action to Immediately insert control rods or increase core flow to restore operation outside the "Exit" Region.

B. No recirculation loops B.1. Place the reactor Immediately operating while in mode switch in the MODE 1. shutdown position.

OR Reactor core operating in the "Scram" Region OR Core thermal hydraulic instability evidenced.

TRM Vol. I TRM 3.4-la REV 71 11/04

Recirculation Loops Operating - Regions TR 3.4.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE .FREQUENCY TRSR 3.4.1.1.1 ---------------- NOTE---------------------

Only required to be perforned when operating in the "Stability Awareness" Region as defined in the COLR.

Verify the reactor core is not exhibiting 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> core thermal-hydraulic instability.

TRM Vol. I TP11 3. 4- lb REV 71 11/04

PCIVs TR 3.6.3 TABLE TR3.6.3-1 (Page 11 of 22)

Primary Contaiument Isolation Valves '

MAXIMUM ISOLATION TIME FUNCTION (seconds) ")

2. Remote-Manual Isolation ValvesXd) (continued)
y. EECW Return from Drywell Equipment Isolation Valves Division I: P4400-F607A NA P4400-F616 NA Division II: P4400-F607B NA P4400-F6l5- NA
z. Deleted I

aa. TIP System Shear Valvesfl))

C5100-FOOIA NA C5100-FOOlB NA C5100-FOOlC NA C5100-FOOlD NA C5100-FOOlE NA ab. Post Accident Sampling Isolation Valves

1. Drywell Atmosphere Sample Suction Valves Division I: P34-F404B NA P34-F403B NA Division II: P34-F403A NA P34-F404A NA
2. Suppression Pool Atmosphere Sample Suction Valves Division I: P34-F405B NA P34-F406B NA Division II: P34-F405A NA P34-F406A NA (continued)

TRM Vol. I TRM 3.6-13 REV 71 11/04

Recirculation Loops Operating - Regions TR B3.4.1.1 TR B3.4 REACTOR COOLANT SYSTEM (RCS)

TR B3.4.1.1 Recirculation Loops Operating - Regions BASES BACKGROUND I GDC 12 of 10 CFR 50 Appendix A (Reference 1) states that the reactor core and associated coolant, control, and protection systems shall be designed to assure that power oscillations which can result in exceeding specified fuel design limits are not possible or can be reliably detected and suppressed.

BWR cores typically operate.with the presence of global flux noise in a stable mode which is due to random boiling and flow noise. As the power/flow conditions are changed, along with other system parameters (xenon, subcooling, power distribution, etc.) the thermal-hydraulic/reactor kinetic feedback mechanism can be enhanced such that perturbations may result in sustained limit cycle or divergent oscillations in power and flow.

Two major modes of oscillations have been observed in BWRs. The first mode is the fundamental or core-wide oscillation mode in which the entire core oscillates in phase in a given axial plane. The second mode involves regional oscillation in which one half of the core oscillates 180 degrees out of phase with the other half.

Studies have indicated that adequate margin to the Safety Limit MCPR may not exist during regional oscillations.

APPLICABLE Thermal-hydraulic stability analysis (Reference 2) has SAFETY ANALYSES concluded that procedures for detecting and suppressing power oscillations that might be induced by a thermal-hydraulic instability are necessary to provide reasonable assurance that the requirements of Reference 1 are satisfied in the absence of an operable OPRM function (APRM function 2.f).

LCO Operations that exhibit core thermal-hydraulic instability are not permitted. Additionally, in order to avoid potential power oscillations due to thermal-hydraulic instability, operation at certain combinations of power and flow are not permitted. These restricted power and flow regions are referred to as the "Scram" and "Exit" regions and are defined in the COLR.

TRM Vol. I TRM B3.4.1-2 REV 71 11/04

Recirculation Loops Operating - Regions TR B3.4.1.1 BASES ACTIONS A.1 When operating in the "Exit" region (refer to COLR), the potential for thermal-hydraulic instabilities is increased and sufficient margin may not be available for operator response to suppress potential power oscillations.

Therefore, action must be initiated immediately to restore operation outside of the "Exit" region. Control rod insertion and/or core flow increases are designated as the means to accomplish this objective.

Required Action A.1 is modified by a Note that precludes core flow increases by restart of an idle recirculation.loop, or by resetting a recirculation flow limiter. Core flow increases by these means would not support timely completion of the action to restore operation outside the "Exit" Region.

B.1 If operating with no recirculation pumps in operation in MODE 1 or operating in the "Scram" region (refer to COLR), or if core thermal-hydraulic instability is detected, then unacceptable power oscillations may result. Therefore, the reactor mode switch must be immediately placed in the shutdown position to terminate the potential for unacceptable power oscillations.

Thermal-hydraulic instability is evidenced by a sustained increase in APRM or LPRM peak to peak noise level reaching 2 or more times its initial level and occurring with a characteristic period of less than 3 seconds.

If entry into this condition is an unavoidable and well known consequence of an event, early initiation of the Required Action is appropriate. Also, it is recognized that during certain abnormal conditions, it may become operationally necessary to enter the "Scram" or "Exit" region for the purpose of: 1) protecting plant equipment, which if it were to fail could impact plant safety, or 2) protecting a safety or fuel operating limit. In these cases, the appropriate actions for the region entered would be performed as required.

These requirements are consistent with References 2 and 3.

SURVEILLANCE SR 3.4.1.1.1 REQUIREMENTS This SR provides frequent periodic monitoring for core thermal-hydraulic instability by monitoring APPIAT and LPRi signals for a sustained increase in APRM or LPRM peak to peak noise level reaching 2 or more times its initial level and occurring with a characteristic period of less than 3 seconds. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> frequency is based on the small potential for core thermal-hydraulic oscillations to occur outside the "Scram" or (continued)

TRMG Vol. I TRM B3.4.1-3 REV 71 11/04

Recirculation Loops Operating - Regions TR B3.4.1.1 BASES SURVEILLANCE REQUIREMENTS (continued)

"Exit" regions. Therefore, frequent monitoring of the APRM and LPRM signals is appropriate when operating in the "Stability Awareness" region.

This SR is modified by a Note that states performance is only required when operating in the "Stability Awareness" region (refer to COLR) (i.e., in the power-to-flow region that is I near regions of higher probability for core thermal-hydraulic instabilities). This is acceptable because outside the "Stability Awareness" region, power and flow conditions are such that sufficient margin exists to the potential for core thermal-hydraulic instability to allow routine core monitoring. Any unanticipated entry into the "Stability Awareness" region would require immediate verification of core stability since the Surveillance would not be current.

REFERENCES 1. 10 CFR 50, Appendix A, GDC 12

2. NRC Generic Letter 94-02, "Long-Term Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors,". July 1994.
3. BWROG Letter 94078, "BWR Owners' Group Guidelines for Interim Corrective Action," June 1994.

TRM Vol. I TRM B3.4.1-4 REV 71 11/04

Recirculation Loops Operating - Regions TR B3.4.1.1 FIGURE B 3.4.1-1 HAS BEEN DELETED (Relocated to COLR)

THIS PAGE INTENTIONALLY LEFT BLANK TRM Vol. I TRM B3.4.1-5 REV 71 11/04

COLR - II Revision 0 Page 1 of 22 FERMI 2 CORE OPERATING LIMITS REPORT CYCLE 11 REVISION 0 Prepared by: // -3'o0 P. R. Kiel Date Reload Core Design Team Leader Reviewed by: //- 70,- Vt T. W. Morrison Date Station Nuclear Engineer BC. yers Date COLR Checklist Reviewer Approved by: //- 3q Date R. A. Gailliez Date Supervisor - Reactor Engineering November 2004

COLR - 11 Revision 0 Page 2 of 22 TABLE OF CONTENTS

1.0 INTRODUCTION

AND

SUMMARY

................................................ 4 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ... 5 2.1 Definition .5 2.2 Determination of MAPLHGR Limit .5 2.2.1 Calculation of MAPFAC(P) .7 2.2.2 Calculation of MAPFAC(F)........................................................................8 3.0 MINIMUM CRITICAL POWER RATIO . . . 9 3.1 Definition ... 9.........................9 3.2 Determination of Operating Limit MCPR ............................. 9 3.3 Calculation of MCPR(P) ............................ 10 3.3.1 Calculation of Kp ............................. 11 3.3.2 Calculation of t ............................ 12 3.4 Calculation of MCPR(F) ............................ 13 4.0 LINEAR HEAT GENERATION RATE .14 4.1 Definition .. 14 4.2 Determination of LHGR Limit .. 14 4.2.1 Calculation of LHGRFAC(P) .16 4.2.2 Calculation of LHGRFAC(F) .17 5.0 CONTROL ROD BLOCK INSTRUMENTATION . . 18 5.1 Definition .18 6.0 BACKUP STABILITY PROTECTION REGIONS . .19 6.1 Definition .19

7.0 REFERENCES

.21

COLR - 11 Revision 0 Page 3 of 22 LIST OF TABLES TABLE I FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS ............... .............. 6 TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS ................................... 8 TABLE 3 OLMCPR 1 001 105 AS A FUNCTION OF EXPOSURE AND T ................................. 10 TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS .......................................... 13 TABLE 5 STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES ............................... 15 TABLE 6 FLOW-DEPENDENT LHGR LIMIT COEFFICIENTS .......................................... 17 TABLE 7 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER ................................................... 18 TABLE 8 BSP REGION DESCRIPTIONS ................................................... 19 LIST OF FIGURES FIGURE I BSP REGIONS FOR NOMINAL FEEDWATER TEMPERATURE .20

COLR - 11 Revision 0 Page 4 of 22

1.0 INTRODUCTION

AND

SUMMARY

This report provides the cycle specific plant operating limits, which are listed below, for Fermi 2, Cycle 11, as required by Technical Specification 5.6.5. The .analytical methods used to determine these core operating limits are those previously reviewed and approved by the Nuclear Regulatory Commission in GESTAR II.

The cycle specific limits contained within this report are valid for the full range of the licensed operating domain.

OPERATING LIMIT TECHNICAL SPECIFICATION APLHGR 3.2.1 MCPR 3.2.2 LHGR 3.2.3 RBM 3.3.2.1 BSP REGIONS 3.3.1.1 APLHGR = AVERAGE PLANAR LINEAR HEAT GENERATION RATE MCPR = MINIMUM CRITICAL POWER RATIO LHGR = LINEAR HEAT GENERATION RATE RBM = ROD BLOCK MONITOR SETPOINTS BSP = BACKUP STABILITY PROTECTION

COLR - 11 Revision 0 Page 5 of 22 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE TECH SPEC IDENT OPERATING LIMIT 3.2.1 APLHGR 2.1 Definition The AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) shall be applicable to a specific planar height and is equal to the sum of the LINEAR HEAT GENERATION RATEs (LHGRs) for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

2.2 Determination of MAPLHGR Limit The maximum APLHGR (MAPLHGR) limit is a function of reactor power, core flow, fuel type, and average planar exposure. The limit is developed, using NRC approved methodology described in References 1 and 2, to ensure gross cladding failure will not occur following a loss of coolant accident (LOCA). The MAPLHGR limit ensures that the peak clad temperature during a LOCA will not exceed the limits as specified in 10CFR50.46(b)(1) and that the fuel design analysis criteria defined in References 1 and 2 will be met.

The MAPLHGR limit during dual loop operation is calculated by the following equation:

MAPLHGRUMI. = MIN (MAPLHGR (P), MAPLHGR (F))

where:

MAPLHGR (P) = MAPFAC (P) x MAPLHGRJD MAPLHGR (F) = MAPFAC (F) x MAPLHGRSTD Within four hours after entering single loop operation, the MAPLHGR limit is calculated by the following equation:

MAPLHGRUMT = MIN (MAPLHGR (P), MAPLHGR (F), MAPLHGR(SLO))

where:

MAPLHGR (SLO)= 1.0 x MAPLHGRSh The Single Loop multiplier is 1.0 since the offrated ARTS limits bound the single loop MAPLHGR limit.

COLR - 11 Revision 0 Page 6 of 22 MAPLHGRsTD, the standard MAPLHGR limit, is defined at a power of 3430 MWt and flow of 105 Mlbs/hr for each fuel type as a function of average planar exposure and is presented in Table

1. When hand calculations are required, MAPLHGRsTD shall be determined by interpolation from Table 1. MAPFAC(P), the core power-dependent MAPLHGR limit adjustment factor, shall be calculated by using Section 2.2.1. MAPFAC(F), the core flow-dependent MAPLHGR limit adjustment factor, shall be calculated by using Section 2.2.2.

TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS GEl 1 Exposure GEl 1 MAPLHGR GE14 Exposure GE14 MAPLHGR GWD/ST KW/FT GWD/ST KW/FT 0.0 13.42 0.0 12.82 19.72 13.42 19.13 12.82 27.22 12.29 57.61 8.00 63.50 8.90 63.50 5.00 Fuel Types 15 = GEI I-P9CUB378-4G6/8G5-1OOT-146-T6-3955 19 = GEI I-P9CUB408-12GZ-IOOT-146-T6-2604 16 = GEI 1-P9CUB396-13GZ-IOOT-146-T6-3954 20 = GEI I-P9CUB380-12GZ-IOOT-146-T6-2605 17 = GE1I-P9CUB380-lIGZ-IOOT-146-T6-2542 I = GE14-PIONAB400-16GZ-IOOT-150-T6-2787 18 = GEI I-P9CUB404-12GZ-IOOT-146-T6-2543 2 = GE14-PIONAB399-16GZ-IOOT-150-T6-2788

COLR - 11 Revision 0 Page 7 of 22 2.2.1 Calculation of MAPFAC(P)

The core power-dependent MAPLHGR limit adjustment factor, MAPFAC(P), shall be calculated by one of the following equations:

For 0 <P <25:

No thermal limits monitoring is required.

For 25 <P < 30:

With turbine bypass OPERABLE, For core flow < 50 MlbW/hr, MAPFAC (P) = 0.606 + 0.0038 (P - 30)

For core flow > 50 Mlbs/hr, MAPFAC (P) = 0.586 + 0.0038 (P - 30)

With turbine bypass INOPERABLE, For core flow < 50 Mlbs/hr, MAPFAC(P)= 0.490 + 0.0050(P- 30)

For core flow > 50 Mlbs/hr, MAPFAC(P) = 0.438 + 0.0050(P-30)

For 30 <P < 100:

MAPFAC(P) = 1.0+0.005224(P-100) where: P = Core power (fraction of rated power times 100).

COLR - 11 Revision 0 Page 8 of 22 2.2.2 Calculation of MAPFAC(F)

The core flow-dependent MAPLHGR limit adjustment factor, MAPFAC(F), shall be calculated by the following equation:

ACT MAPFAC(F) = MIN(1.0, AFX 100 + BF) 100 where:

WT = Core flow (Mlbs/hr).

AF = Given in Table 2.

BF = Given in Table 2.

TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS Maximum Core Flow*

(Mlbs/hr) AF BP 110 0.6787 0.4358 As limited by the Recirculation System MG Set mechanical scoop tube stop setting.

COLR - 11 Revision 0 Page 9 of 22 3.0 MINIMUM CRITICAL POWER RATIO TECH SPEC IDENT OPERATING LIMIT 3.2.2 MCPR 3.1 Definition The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest Critical Power Ratio (CPR) that exists in the core for each type of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

3.2 Determination of Operating Limit MCPR The required Operating Limit MCPR (OLMCPR) at steady-state rated power and flow operating conditions is derived from the established fuel cladding integrity Safety Limit MCPR and an analysis of abnormal operational transients. To ensure that the Safety Limit MCPR is not exceeded during any anticipated abnormal operational transient, the most limiting transients have been analyzed to determine which event will cause the largest reduction in CPR. Three different core average exposure conditions are evaluated. The result is an Operating Limit MCPR which is a function of exposure and 'C. T is a measure of scram speed, and is defined in Section 3.3.2.

The OLMCPR shall be calculated by the following equation:

OLMCPR = MAX(MCPR(P), MCPR(F))

MCPR(P), the core power-dependent MCPR operating limit, shall be calculated using Section 3.3.

MCPR(F), the core flow-dependent MCPR operating limit, shall be calculated using Section 3.4.

In case of Single Loop Operation, the Safety Limit MCPR is increased to account for increased uncertainties in core flow measurement and TIP measurement, but OLMCPR does not change.

This is due to the fact that sufficient conservatism exists in the power-dependent MCPR operating limits to allow for the increase in the SLMCPR without requiring a corresponding increase in OLMCPR.

COLR - 1I Revision 0 Page 10 of 22 3.3 Calculation of IMICPR(P)

MCPR(P), the core power-dependent MCPR operating limit, shall be calculated by the following equation:

MCPR(P) = Kp XOLMCPRloo1,o5 Kp, the core power-dependent MCPR Operating Limit adjustment factor, shall be calculated by using Section 3.3.1.

OLMCPRIOO/1 0 5 shall be determined by interpolation from Table 3, and I shall be calculated by using Section 3.3.2.

TABLE 3 OLMCPR 1 ooo1 05 AS A FUNCTION OF EXPOSURE AND T EXPOSURE CONDITION (MWD/ST) 1 oo/1 os (MWD/ST)OLMCPR Both Turbine Bypass and Moisture Separator Reheater OPERABLE BOC to 6800 T=O 1.35

'T= I 1.46 6800 to 8800 1=o 1.39 T=1 1.50 8800 to EOC T=0 1.44 T= 1 1.61 Either Turbine Bypass or Moisture Separator Reheater INOPERABLE BOC to EOC 1.49

'T= I 1.66 Both Turbine Bypass and Moisture Separator Reheater INOPERABLE BOC to EOC T=0 1.52 T=1 1.69

COLR - I I Revision 0 Page 11 of 22 3.3.1 Calculation of Kp The core power-dependent MCPR operating limit adjustment factor, Kp, shall be calculated by using one of the following equations:

For 0<P<25 No thermal limits monitoring is required.

For 25 <P<30 When turbine bypass is OPERABLE, KP (KBRYP+(0.032x(30-P)))

OLMUPRiowizos where: KBYP = 2.16 for core flow < 50 Mlbs/hr

= 2.44 for core flow > 50 Mlbs/hr When turbine bypass is INOPERABLE, Kp- (KBYP+(OO76x(3O-P)))

OLMUPRmloa0 ,s where: KBYP = 2.61 for core flow < 50 Mlbs/hr

= 3.34 for core flow > 50 Mlbs/hr For 30<P<45 Kp= 1.28 + (0.0134 x (45- P))

For 45<P<60:

Kp= 1.15 + (0.00867 x (60 - P))

For 60<P<100:

Kp= 1.0 + (0.00375 x (100- P))

where: P = Core power (fraction of rated power times 100).

COLR - 11 Revision 0 Page 12 of 22 3.3.2 Calculation of T The value of X, which is a measure of the conformance of the actual control rod scram times to the assumed average control rod scram time in the reload licensing analysis, shall be calculated by using the following equation:

= (Tvcy IB )

TA TB where: TA = 1.096 seconds TB = 0.830 + 0.019 x 1.65 seconds Ni i=1 zNi v rave = n XNi

=,

n = number of surveillance tests performed to date in cycle, Ni = number of active control rods measured in the ith surveillance test,

= average scram time to notch 36 of all rods measured in the ith surveillance test, and N. = total number of active rods measured in the initial control rod scram time test for the cycle (Technical Specification Surveillance Requirement 3.1.4.4).

The value of X shall be calculated and used to determine the applicable OLMCPRjoo/lo 5 value from Table 3 within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the conclusion of each control rod scram time surveillance test required by Technical Specification Surveillance Requirements 3.1.4.1, 3.1.4.2, and 3.1.4.4.

Prior to performance of the initial scram time measurements for the cycle, a ¶ value of 1.0 shall be used to determine the applicable OLMCPRI 00 /105 value from Table 3.

COLR - 11 Revision 0 Page 13 of 22 3.4 Calculation of MCPR(F)

MCPR(F), the core flow-dependent MCPR operating limit, shall be calculated by using the following equation:

10T MCPR(F)= MAX(1.21,(AFX- + BF))

100 where:

WT = Core flow (Mlbs/hr).

AF = Given in Table 4.

BF = Given in Table 4.

TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS Maximum Core Flow (Mlbsfhr) AF BF 110 -0.601 1.743 lAs limited by the Recirculation System MG Set mechanical scoop tube stop setting.

COLR - 11 Revision 0 Page 14 of 22 4.0 LINEAR HEAT GENERATION RATE TECH SPEC IDENT OPERATING LIMIT 3.2.3 LHGR 4.1 Definition The LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length. By maintaining the operating LHGR below the applicable LHGR limit, it is assured that all thermal-mechanical design bases and licensing limits for the fuel will be satisfied.

4.2 Determination of LHGR Limit The maximum LHGR limit is a function of reactor power, core flow, fuel and rod type, and fuel rod nodal exposure. The limit is developed, using NRC approved methodology described in References 1 and 2, to ensure the cladding will not exceed its yield stress and that fuel thermal-mechanical design criteria will not be violated during any postulated transient events. The LHGR limit ensures the fuel mechanical design requirements as defined in References 1 and 2 will be met.

The LHGR limit during dual loop operation is calculated by the following equation:

LHGR,,f,, = MIN (LHGR (P), LHGR (F))

where:

LHGR (P) = LHGRFAC (P) x LHGRs,,,

LHGR (F) = LHGRFAC (F) x LHGR,,.

LHGRSTD, the standard LHGR limit, is defined at a power of 3430 MWt and flow of 105 Mlbs/hr for each fuel and rod type as a function of fuel rod nodal exposure and is presented in Table 5.

Table 5 contains only the most limiting Gadolinia LHGR limit for the maximum allowed Gadolinia concentration of the applicable fuel product line. When hand calculations are required, LHGRSTD shall be determined by interpolation from Table 5. LHGRFAC(P), the core power-dependent LHGR limit adjustment factor, shall be calculated by using Section 4.2.1.

LHGRFAC(F), the core flow-dependent LHGR limit adjustment factor, shall be calculated by using Section 4.2.2.

COLR - 11 Revision 0 Page 15 of 22 TABLE 5 STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES GE11 Most Limiting GEl I Uranium Only Fuel Rods Gadolinia Bearing Fuel Rods Exposure LHGR Exposure LHGR GWD/ST KW/FT GWD/ST KW/FT 0.0 14.40 0.0 12.74 13.24 14.40 10.59 12.74 27.22 12.29 23.99 10.87 63.50 8.90 58.81 7.88 GE14 Most Limiting GE14 Uratnium Only Fuel Rods Gadolinia Bearing Fuel Rods Exposure LHGR Exposure LHGR GWD/ST KW/FT IGWD/ST KW/FT 0.0 13.40 0.0 12.52 14.51 13.40 12.39 12.52 57.61 8.00 55.44 7.47 63.50 5.00 61.33 4.67 Fuel Types 15 = GE II-P9CUB378-4G6/8G5-IOOT-146-T6-3955 19 = GEI I-P9CUB408-12GZ-lOOT-146-T6-2604 16 = GEl I-P9CUB396-13GZ-lOOT-146-T6-3954 20 = GEI I-P9CUB380-12GZ-lOOT-146-T6-2605 17 = GEl l-P9CUB380-1 IGZ-IOOT-146-T6-2542 1 = GE14-PlONAB400-16GZ-IOOT-150-T6-2787 18 = GEl l-P9CUB404-12GZ-IOOT-146-T6-2543 2 = GE14-PI ONAB399-1 6GZ- IOOT-150-T6-2788

COLR - 11 Revision 0 Page 16 of 22 4.2.1 Calculation of LHGRFAC(P)

The core power-dependent LHGR limit adjustment factor, LHGRFAC(P), shall be calculated by one of the following equations:

For 0<P<25:

No thermal limits monitoring is required.

For 25 < P < 30:

With turbine bypass OPERABLE, For core flow < 50 Mlbs/hr, LHGRFAC(P) = 0.606 + 0.0038 (P - 30)

For core flow > 50 Mlbs/hr, LHGRFAC (P) = 0.586 + 0.0038 (P - 30)

With turbine bypass INOPERABLE, For core flow < 50 Mlbs/hr, LHGRFA C(P)= 0.490 + 0.0050(P-30)

For core flow > 50 Mlbs/hr, LHGRFA C(P)= 0.438 + 0.0050(P- 30)

For 30 < P < 100:

LHGRFAC(P)=1.0 + 0.005224(P-100) where: P = Core power (fraction of rated power times 100).

COLR - 11 Revision 0 Page 17 of 22 4.2.2 Calculation of LHGRFAC(F)

The core flow-dependent LHGR limit adjustment factor, LHGRFAC(F), shall be calculated by the following equation:

LHGRFAC(F)=MIN(].O, AFX 100 + BF) 100 where:

NVT = Core flow (Mlbsfhr).

AF = Given in Table 6.

BF = Given in Table 6.

TABLE 6 FLOW-DEPENDENT LHGR LIMIT COEFFICIENTS

COLR - 11 Revision 0 Page 18 of 22 5.0 CONTROL ROD BLOCK INSTRUMENTATION TECH SPEC IDENT SETPOINT 3.3.2.1 RBM 5.1 Definition The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation are shown in Table 7. These values are consistent with the bases of the APRM Rod Block Technical Specification Improvement Program (ARTS) and the MCPR operating limits.

TABLE 7 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER Setpoint Trip Sctpoint Allowable Value LPSP 27.0 28.4 IPSP 62.0 63.4 HPSP 82.0 83.4 LTSP 117.0 118.9 ITSP 112.2 114.1 HTSP 107.2 109.1 DTSP 94.0 92.3 where:

LPSP Low power setpoint; Rod Block Monitor (RBM) System trip automatically bypassed below this level IPSP Intermediate power setpoint HPSP High power setpoint LTSP Low trip setpoint ITSP Intermediate trip setpoint HTSP High trip setpoint DTSP Downscale trip setpoint

COLR - 11 Revision 0 Page 19 of 22 6.0 BACKUP STABILITY PROTECTION REGIONS TECH SPEC REFERENCE OPERATING LIMIT 3.3.1.1 Action Condition J Alternate method to detect and suppress thermal hydraulic instability oscillations TRM REFERENCE OPERATING LIMIT 3.4.1.1 Scram, Exit, and Stability Awareness Regions 6.1 Definition The Backup Stability Protection (BSP) Regions are an integral part of the Tech Spec required alternative method to detect and suppress thermal hydraulic instability oscillations in that they identify areas of the power/flow map where there is an increased probability that the reactor core could experience a thermal hydraulic instability. Regions are identified (refer to Table 8 and Figure 1) that are either excluded from planned entry (Scram Region), or where specific actions are required to be taken to immediately leave the region (Exit Region). A region is also identified where operation is allowed provided that additional monitoring is performed to verify that the reactor core is not exhibiting signs of core thermal hydraulic instability (Stability Awareness Region).

The boundaries of these regions are established on a cycle specific basis based upon core decay ratio calculations performed using NRC approved methodology.

These regions are only applicable when the Upscale Trip function of the Oscillation Power Range Monitoring System (OPRM) is inoperable. It must be noted that the Cycle 11 region boundaries defined in Table 8 and illustrated in Figure 1 are not applicable to operation with Feedwater Heaters Out-Of-Service (FWHOOS) or with Final Feedwater Temperature Reduction (FFWTR).

TABLE 8 BSP REGION DESCRIPTIONS Scram Region: > 96% Rod Line, < 41% Core Flow

> 67% Rod Line, < 41% Core Flow Exit Region: > 77% Rod Line, < 48% Core Flow Not in Scram Region -and- > 103% Rod Line, < 50% Core Flow

> 62% Rod Line, < 46% Core Flow Stability Awareness Region > 72% Rod Line, < 53% Core Flow Not in Scram or Exit Region -and- > 98% Rod Line, < 55% Core Flow

COLR - 11 Revision 0 Page 20 of 22 FIGURE 1 - BSP REGIONS FOR NOMINAL FEEDIVATER TEMPERATURE l 00% CLTP =3430MNWt l MELlLA Rod Une lRated Core Flow =100.0 Nflb/hr \

70 C Approx. Natural L. Circulation 0

60 _\ 4 Stbility

\0 Awareness C

C Et \ Scram Region E Riegion E-0Exit Region c1 a-1-

e' '40 .-

30 . .

/0 .

30 40 50 60 Percent (%) of Rated Core Flow

COLR - 11 Revision 0 Page 21 of 22

7.0 REFERENCES

1. "General Electric Standard Application for Reactor Fuel (GESTAR II)," NEDE-24011-P-A, Revision 14 as amended by Amendment 25
2. "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident

- SAFER/GESTR Application Methodology," NEDE 23785-1-PA, Revision 1, October 1984

3. "Fermi-2 SAFER/GESTR-LOCA, Loss-of-Coolant Accident Analysis," NEDC-31982P, July 1991, and Errata and Addenda No. 1, April 1992
4. "DTE Energy Enrico Fermi 2 SAFER/GESTR Loss of Coolant Accident Analysis for GE14 Fuel" GE-NE-0000-0030-6565 Revision 0 dated September 2004
5. "Fuel Bundle Information Report for Fermi 2 Reload 10 Cycle 11," Global Nuclear Fuel, 0000-0025-3998, Revision 0, August 2004 (LHGR Limits)
6. "Supplemental Reload Licensing Report for Fermi 2 Reload 10, Cycle 11," Global Nuclear Fuel, 0000-0025-3998, Revision 0, August 2004 (GEl l MAPLHGR Limits)
7. "Supplemental Reload Licensing Report for Fermi 2 Reload 9, Cycle 10," Global Nuclear Fuel, 0000-00074899, Revision 0, January 2003 (GE14 MAPLHGR & OLMCPR Limits)
8. Letter from T. G. Colburn to W. S. Orser, "Fermi Amendment No. 87 to Facility Operating License No. NPF-43 (TAC NO. M82102)," September 9, 1992
9. Letter from J. F. Stang to W. S. Orser, "Amendment No. 53 to Facility Operating License No.

NPF-43: (TAC No. 69074)," July 27, 1990

10. "Maximum Extended Operating Domain Analysis for Detroit Edison Company Enrico Fermi Energy Center Unit 2," GE Nuclear Energy, NEDC-31843P, July 1990
11. "GE14 Fuel Design Cycle-Independent Analyses for Fermi Unit 2", GE-NE-0000-0025-3282-00, Revision 0, November-2004 (ARTS)
12. "Power Range Neutron Monitoring System," DC-4608, Vol. XI DCD, Rev. B and DC-4608 Vol. I Rev. D.
13. Letter from Greg Porter to B. L. Myers, "Scram Times for Improved Tech Specs." GP-99014, October 22, 1999 containing DRF A12-00038-3, Vol. 4 information from G. A. Watford, GE, to Distribution,

Subject:

Scram Times versus Notch Position

COLR - 11 Revision 0 Page 22 of 22

7.0 REFERENCES

14. Methodology and Uncertainties for Safety Limit MCPR Evaluations, NEDC-32601P-A, August 1999
15. Power Distribution Uncertainties for Safety Limit MCPR Evaluation, NEDC-32694P-A, August 1999
16. R-Factor Calculation Method for GE I1, GE12, and GE13 Fuel, NEDC-32505P-A, Revision 1, July 1999
17. "Improved LHGR Limits (designated as "GE 1 1/13-UPGRADE") for GEl1 Fuel in Fermi,"

Global Nuclear Fuel, GNF-J1 103057-265, August 2001

18. "Turbine Control Valve Out-Of-Service for Enrico Fermi Unit-2," GE - Nuclear Energy, GE-NE-J1 1-03920-07-01, October 2001
19. Licensing Topical Report, "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," Volume 1, NEDO-24154-A 78NED290R1, August 1986
20. BSP Evaluation Report, "Backup Stability Protection Evaluation for Fermi 2 Cycle 11,"

GENE-0000-0029-7256-RO, September 2004 (BSP Limits)

21. Letter from David P. Beaulieu (USNRC) to William T. O'Connor, Jr. (Detroit Edison),

"Fermi Issuance of Amendment RE: Changes To The Safety Limit Minimum Critical Power Ratio (TAC NO. MC4748)," dated November 30, 2004 (SLMCPR Limit)

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