NRC-06-0043, 2,Transmittal of Cycle 12 Core Operating Limits Report, Revision 1

2,Transmittal of Cycle 12 Core Operating Limits Report, Revision 1

ML061660136
Person / Time
Site:	Fermi
Issue date:	06/08/2006
From:	Gaston R Detroit Edison
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NRC-06-0043
Download: ML061660136 (24)

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Fermi 2 6400 North Dixie Ihwy., Newport, MI 48166 Detroit Edison June 8, 2006 NRC-06-0043 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001

References:

1) Fermi 2 NRC Docket No. 50-341 NRC License No. NPF-43

2) Detroit Edison Letter NRC-06-0034, Transmittal of Cycle 12 Core Operating Limits Report, dated April 27, 2006 Transmittal of Cycle 12 Core Operating Limits Report, Revision 1

Subject:

In accordance with Fermi 2 Technical Specification 5.6.5, Detroit Edison hereby submits a copy of the Core Operating Limits Report (COLR), Cycle 12, Revision 1.

This COLR will be used during the Fermi 2 twelfth operating cycle.

Should you have any questions or require additional information, please contact me at (734) 586-5197.

Sincerely, Ronald W. Gaston Manager, Nuclear Licensing Enclosure cc:

D. H. Jaffe

[w/ Enclosure]

C. A. Lipa

[w/o Enclosure]

NRC Resident Office

[w/Enclosure]

Regional Administrator - Region HI

[w/Enclosure]

Supervisor, Electric Operators, Michigan Public Service Commission

[w/o Enclosure]

'ýý I A DTE Energy Company

ENCLOSURE TO NRC-06-0043 CORE OPERATING LIMITS REPORT ICOLR]

CYCLE 12 REVISION 1

COLR - 12 Revision I Page 1 of 22 FERMI 2 CORE OPERATING LIMITS REPORT CYCLE 12 REVISION 1 Prepared by:

P. R. Kiel 9.

Dýate/

Date Reviewed by:

T. W. Morrison Station Nuclear Engineer 5Y12711*f tLz Date R. O'Sullivan COLR Checklist Reviewer R. A. Gailliez C)

Supervisor - Reactor Engineering Approved by:

Date May 2006

COLR - 12 Revision I Page 2 of 22 TABLE OF CONTENTS 1.0 INTRODU CTION AND SUM M ARY................................................................................

4 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE.............................................

5 2.1 D efinition.........................................................................................................

5 2.2 Determ ination of M APLHGR Limit....................................................................

5 2.2.1 Calculation of M APFAC(P)....................................................................

7 2.2.2 Calculation of M APFAC(F)....................................................................

8 3.0 M ]N[M UM CRITICAL POW ER RATIO............................................................................

9 3.1 Definition.........................................................................................................

9 3.2 Determ ination of Operating Limit M CPR...........................................................

9 3.3 Calculation of M CPR(P)....................................................................................

10 3.3.1 Calculation of Kp..................................................................................

11 3.3.2 Calculation oftr......................................................................................

12 3.4 Calculation of M CPR(F)....................................................................................

13 4.0 LINEAR HEAT GENERATION RATE...........................................................................

14 4.1 Definition..............................................................................................................

14 4.2 Determ ination of LH GR Lim it...........................................................................

14 4.2.1 Calculation of LH GRFAC(P)...............................................................

16 4.2.2 Calculation of LH GRFAC(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 REFEREN CES.......................................................................................................................

21 7.1 Source References.............................................................................................

21 7.2 Basis References...............................................................................................

21

COLR - 12 Revision 1 Page 3 of 22 LIST OF TABLES TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS........................

6 TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS...............................

8 TABLE 3 OLMCPR1 oI 0io5 AS A FUNCTION OF EXPOSURE AND Tr............................

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 FIL T E R....................................................................................................................

18 TABLE 8 BSP REGION DESCRIPTIONS.........................................................................

19 LIST OF FIGURES FIGURE 1 BSP REGIONS FOR NOMINAL FEEDWATER TEMPERATURE............... 20

COLR - 12 Revision I 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 12, 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 (Reference 9).

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

OPERATING LIMIT APLHGR MCPR LHGR RBM BSP REGIONS TECHNICAL SPECIFICATION 3.2.1 3.2.2 3.2.3 3.3.2.1 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 - 12 Revision I 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 BEAT 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 9 and 10, 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 9 and 10 will be met.

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

MAPLHGRU,,, = MIN (MAPLHGR (P), MAPLHGR (F))

where:

MAPLHGR (P) = MAPFA C (P) x MAPLHGR,.T, MAPLHGR (F) = MAPFA C (F) x MAPLHGRS, Within four hours after entering single loop operation, the MAPLHGR limit is calculated by the following equation:

MAPLHGRJff = MIN (MAPLHGR (P).MAPLHGR (F), MAPLHGR (SLO))

where:

MAPLHGR (SLO) = 1.0 x MAPLHGR.S,,

The Single Loop multiplier is 1.0 since the offrated ARTS limits bound the single loop MAPLHGR limit.

COLR - 12 Revision I 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 averageplanar 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 GEl1 Exposure GEl1 MAPLHGR GE14 Exposure GE14 MAPLHGR GWD/ST KW/FT GWD/ST KW/FT 0.0 19.72 27.22 63.50 13.42 13.42 12.29 8.90 0.0 19.13 57.61 63.50 12.82 12.82 8.00 5.00 Fuel Types 17 = GEl 1-P9CUB380-1 1GZ-1OOT-146-T6-2542 18 = GEl 1-P9CUB404-12GZ-OOT-146-T6-2543 19 = GE 11 -P9CUB408-12GZ-I OOT-1 46-T6-2604 20 = GEl I-P9CLTB380-12GZ-1OOT-146-T6-2605 1 = GE14-PIOCNAB400-16GZ-10OT-150-T6-2787 2 = GEl 4-P10CNAB399-16GZ-IOOT-150-T6-2788 3 = GEl 4-P 1OCNAB380-10G5/4G4-1OOT-150-T6-2868 4 = GE 14-PI OCNAB381-7G5/8G4-lOOT-150-T6-2869 5 = GE 14-PI OCNAB381-7G6/8G4-100T-150-T6-2877

COLR - 12 Revision I Page 7 of 22 2.2.1 Calculation of MAPFAC(P)

The core power-dependent MAPLHGR limit adjustment factor, MAPFAC(P) (Reference 3),

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, 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 - 12 Revision 1 Page 8 of 22 2.2.2 Calculation of MAPFAC(F)

The core flow-dependent MAPLHGR limit adjustment factor, MAPFAC(F) (Reference 3), shall be calculated by the following equation:

WT MAPFAC(F) = MIN(].O, Apx 1

+ BF) 100 where:

WT AF BF

= Core flow (Mlbs/hr).

= Given in Table 2.

= Given in Table 2.

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

(Mlbs/hr)

AF BF 110 0.6787 0.4358

• As limited by the Recirculation System MG Set mechanical scoop tube stop setting.

COLR - 12 Revision 1 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 (OLIMCPR) (Reference 2 and 8) 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 'i.

'r is a measure of scram speed, and is defined in Section 3.3.2. Cycle 12 operating limits are based on the Dual Loop SLMCPR of 1.08.

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 (Reference 2 and 8) 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 - 12 Revision 1 Page 10 of 22 3.3 Calculation of MCPR(P)

COLR - 12 Revision 1 Page 11 of 22 3.3.1 Calculation of Kp The core power-dependent MCPR operating limit adjustment factor, Kp (Reference 3), 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(

KBYP + (0.032 x (30 - P)))

OLMCPR,0 10o5 where:

KByp = 2.16 for core flow < 50 Mlbs/hr

= 2.44 for core flow > 50 Mlbs/hr When turbine bypass is INOPERABLE,

-( KByp + (0.076 x (30 - P)))

OLMCPRoa,

,o 5 where:

KEyp = 2.61 for core flow < 50 Mlbs/hr

= 3.34 for core flow > 50 Mlbs/hr For 30<P<45 :

For 45<P<60 :

For 60 < P < 100:

K*,P =1.28 + (0.0134 x (45-P))

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

K=

1.0 + (0.00375 x (100-P))

where:

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

COLR - 12 Revision I Page 12 of 22 3.3.2 Calculation of T The value of r, 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:

v,° - "B)

TA -

B where:

A=

1.096 seconds rB=

0.830 + 0.019 x 1.65 n

seconds ZNi i--11 EZNi T

'rave ""

ZNi i~=1 n =

number of surveillance tests performed to date in cycle, Ni =

number of active control rods measured in the ith surveillance test, ri =

average scram time to notch 36 of all rods measured in the it' surveillance test, and N1 = 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 r shall be calculated and used to determine the applicable OLMCPR 10011 05 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 co'htrol 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 t value of 1.0 shall be used to determine the applicable OLMCPR 1 0011 05 value from Table 3.

COLR - 12 Revision 1 Page 13 of 22 3.4 Calculation of MCPR(F)

MCPR(F), the core flow-dependent MCPR operating limit (Reference 3), shall be calculated by using the following equation:

WT MCPR(F)= MAX(l.21,(AFx7+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*

(Mlbs/hr)

AF BF 110

-0.601 1.743

• As limited by the Recirculation System MG Set mechanical scoop tube stop setting.

COLR - 12 Revision I 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 9 and 10, 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 8 will be met.

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

LHGRUMT* = MIN (LHGR (P), LHGR (F))

where:

LHGR (P) = LHGRFAC (P) x LHGRW LHGR (F) = LHGRFAC (F) x LHGRS, 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 - 12 Revision I Page 15 of 22 TABLE 5 STANDARD LHGR LIMITS FOR VARIOUS FUEL TYPES GEl 1 Uranium Only Fuel Rods Exposure LHGR GWD/ST KW/FT 0.0 14.40 GEl 1 Most Limiting Gadolinia Bearing Fuel Rods Exposure LHGR GWD/ST KW/FT 0.0 12.74 10.59 12.74 13.24 27.22 63.50 14.40 12.29 8.90 23.99 58.81 10.87 7.88 GE14 Uranium Only Fuel Rods Exposure LHGR GWD/ST KW/FT 0.0 13.40 GE14 Most Limiting Gadolinia Bearing Fuel Rods Exposure LHGR GWD/ST KW/FT 0.0 12.26 14.51 57.61 63.50 13.40 8.00 5.00 12.28 55.00 60.84 12.26 7.32 4.57 17 = GEl -P9CUB380-1 1 GZ-100T-146-T6-2542 18 = GEl 1-P9CUB404-12GZ-1OOT-146-T6-2543 19 = GEl I-P9CUB408-12GZ-1OOT-146-T6-2604 20 = GEl 1-P9CUB380-12GZ-100T-146-T6-2605 Fuel Types 1 = GE14-P 1OCNAB400-16GZ-10OT-150-T6-2787 2 = GE14-PIOCNAB399-16GZ-IOOT-150-T6-2788 3 = GE14-PIOCNAB380-10G514G4-1OOT-150-T6-2868 4 = GE14-PIOCNAB381-7G5/8G4-1OOT-150-T6-2869 5 = GE14-PI OCNAB381-7G6/8G4-1OOT-150-T6-2877 I

COLR - 12 Revision I Page 16 of 22 4.2.1 Calculation of LHGRFAC(P)

The core power-dependent LHGR limit adjustment factor, LHGRFAC(P) (Reference 3), 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 Mlbsfhr, LHGRFAC (P) = 0.586 + 0.0038 (P - 30)

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

For core flow > 50 Mlbs/hr, LHGRFAC(P) = 0.438 + 0. 0050(P - 30)

For 30 < P < 100:

LHGRFA C(P) = 1.0 + 0. 005224(P - 100) where:

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

COLR - 12 Revision I Page 17 of 22 4.2.2 Calculation of LHGRFAC(F)

The core flow-dependent LHGR limit adjustment factor, LHGRFAC(F) (Reference 3), shall be calculated by the following equation:

WVT LHGRFAC(F)= MIN(1.0, Arx7+ BF) 100 where:

WT = Core flow (Mlbs/hr).

AF = Given in Table 6.

BF = Given in Table 6.

TABLE 6 FLOW-DEPENDENT LHGR LIMIT COEFFICIENTS Maximum Core Flow*

(Mlbs/hr)

AF BF 110 0.6787 0.4358 As limited by the Recirculation System MG Set mechanical scoop tube stop setting.

COLR - 12 Revision 1 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. (References 2, 6, 7, 8, & 16).

TABLE 7 CONTROL ROD BLOCK INSTRUMEINTATION SETPOINTS WITH FILTER Setpoint Trip Setpoint 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 - 12 Revision 1 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). (Reference 5 and 8)

The boundaries of these regions are established on a cycle specific basis based upon core decay ratio calculations performed using NRC approved methodology. The Cycle 12 regions are valid to a cycle exposure of 12,600 MWd/st. (Reference 2 and 8)

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 12 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).

TABLE8 BSP REGION DESCRIPTIONS Scram Region:

> 96% Rod Line, < 43% 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

> 98% Rod Line, < 55% Core Flow

COLR - 12 Revision 1 Page 20 of 22 FIGURE 1 - BSP REGIONS FOR NOMINAL FEEDWATER TEMPERATURE

[10 0%CLT 3430i MF]

Ratd or Fow

-00.0 Mlb/h 60

"* 60 P-H 50 0:

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

COLR - 12 Revision I Page 21 of 22

7.0 REFERENCES

7.1 SOURCE REFERENCES

1. "Fuel Bundle Information Report for Enrico Fermi 2 Reload 11 Cycle 12," Global Nuclear Fuel, 0000-0038-3146-FIBR, Revision 0, January 2006 (LHGR Limits)

2.

"Supplemental Reload Licensing Report for Enrico Fermi 2 Reload 11 Cycle 12," Global Nuclear Fuel, 0000-0038-3146-SRLR, Revision 0, January 2006 (MAPLHGR Limits, SLO Multiplier, MCPR Limits, SLMCPR)

3. "GE14 Fuel Cycle-Independent Analyses for Fermi Unit 2", GE-NE-0000-0025-3282-00 dated November 2004 (ARTS Limits)

4. 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 (TAU Calculation)

5. Evaluation Report, "BSP Stability Evaluation for Fermi 2 Cycle 12," GENE-0000-0048-1142-RO, January 2006 (BSP Limits)

6. CSCCD-C51 K622/C51 R809C Revision 2, "Programming for Rod Block Monitor (RBM-A)

PIS # C51K622 and Operator Display Assembly (ODA) PIS # C51R809C" (RBM A Setpoints)

7. CSCCD-C51 K623/C51 R809D Revision 2, "Programming for Rod Block Monitor (RBM-B)

PIS # C51K623 and Operator Display Assembly (ODA) PIS # C51R809D" (RBM B Setpoints)

8. "Fermi Cycle 12B GESTAR HI Letter and Stability Report" letter FRL-DTE-KH1-06-012 from F.R. Lindquist, GNF, to P.R. Kiel, DECo, dated May 24, 2006 7.2 BASIS REFERENCES

9.

"General Electric Standard Application for Reactor Fuel (GESTAR H)," NEDE-2401 1-P-A, Revision 14 as amended by Amendment 25

10. "The GESTR-LOCA and SAFER Models for the Evaluation of the Loss-of-Coolant Accident

- SAFERIGESTR Application Methodology," NEDE 23785-1-PA, Revision 1, October 1984

11. "Fermi-2 SAFER/GESTR-LOCA, Loss-of-Coolant Accident Analysis," NEDC-31982P, July 1991, and Errata and Addenda No. 1, April 1992

12. "DTE Energy Enrico Fermi 2 SAFERIGESTR Loss of Coolant Accident Analysis for GE14 Fuel" GE-NE-0000-0030-6565 Revision 0 dated September 2004

13. "DTE Energy Enrico Fermi 2 SAFER/GESTR Loss of Coolant Accident Analysis for GEl 1 Fuel" GE-NE-0000-0047-1716 Revision 0 dated December 2005

COLR - 12 Revision 1 Page 22 of 22 7.2 BASIS REFERENCES

14. 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

15. 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

16. "Maximum Extended Operating Domain Analysis for Detroit Edison Company Enrico Fermi Energy Center Unit 2," GE Nuclear Energy, NEDC-31843P, July 1990

17. "Power Range Neutron Monitoring System," DC-4608, Vol. XI DCD, Rev. B and DC-4608 Vol. I Rev. D.

18. 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

19. Methodology and Uncertainties for Safety Limit MCPR Evaluations, NEDC-32601P-A, August 1999

20. Power Distribution Uncertainties for Safety Limit MCPR Evaluation, NEDC-32694P-A, August 1999

21. R-Factor Calculation Method for GEl 1, GEl2, and GE13 Fuel, NEDC-32505P-A, Revision 1, July 1999

22. "Improved LHGR Limits (designated as "GEl 1/13-UPGRADE") for GEl 1 Fuel in Fermi,"

Global Nuclear Fuel, GNF-J 1103057-265, August 2001

23. "Turbine Control Valve Out-Of-Service for Enrico Fermi Unit-2," GE - Nuclear Energy, GE-NE-J1 1-03920-07-01, October 2001

24. Licensing Topical Report, "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," Volume 1, NEDO-24154-A 78NED290R1, August 1986

25. 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)