ML20154H893

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Rev 24 to Fermi 2 Technical Requirements Manual,Vol I
ML20154H893
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 10/08/1998
From:
DETROIT EDISON CO.
To:
References
PROC-981008, NUDOCS 9810150060
Download: ML20154H893 (20)
v • d • e


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AUTOMATED RECORD MANAGEMENT DISTRIBUTION CONTROL LIST

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US NRC PAGE 1

DOCUMENT CNTRL DESK WASHINGTON, DC 20555 l

Media: 8.1/2-X 11-1 Number Cnt Issue j

DTC Doc. Serial Number Page.Rev Copies Lvl Date Sec Status i

I TMTRM TRM VOL I 24 11 IR 10/08/98 AFC

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A Please destroy or. mark all revised,. superseded, or cancelled documents I

as such. CONTROLLED stamps must be voided by lining through and initialing.

1 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, i

Ref: E51833-9810150060 981008 '"

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THE DISTRIBUTION OF TRM VOL I REVISION 24, THAT WAS ISSUED ON 10/8/98, WILL NOT BE STAMPED CONTROLLED DUE TO THE ISSUANCE OF TRM VOL I REVISION 25 ON 10/9/98. HOWEVER; PLEASE INSERT TRM VOL I REVISION 24 INTO YOUR MANUAL BEFORE INSERTING TRM VOL I REVISION 25. THANK YOU!

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'e LICENSING DOCUMENT TRANSMITTAL TECIINICAL REQUIREMENTS MANUAL,, VOLUME 1 Instructions for Revision 24 dated 10/8/98 Immediately upon receipt of the item (s) below, please insert and/or remove the documents i

indicated. Destroy the removed documents. Be sure Revision 23 has been placed in TRM Vol I prior to inserting these pages.

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Location Remove Insert Title Page Title Page Title Page Rev 23 09/23/98 Rev 24 10/8/98 List of Effective Pages LEP-1, Rev. 23 9/98 LEP-1, Rev. 24 10/98 l

LEP-2, Rev. 23 9/98 LEP-2, Rev. 24 10/98 J

Core Operating COLR Cycle 6, Rev 1 COLR Cycle 7, Rev 0 Limits Report Pages 1 - 16 Pages 1 - 15 lO l

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Fermi 2 Technical Requirements Manual O~

Volume I Detroit Edison ARAfS-INFORAfATION DTC: TMTRM l File: 1754 DSN: TRM VOLI l Rev:24 Date: 10/8/98 Recipient S'.1 j

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m FERMI 2 - TECHNICAL REOUIREMENTS MANUAL LIST OF EFFECTIVE PAGES

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.i-23 3/4 6-3 19 ii 20 3/4 6-4 19 iii 23 3/4 6-5 19 iv 20 3/4 6-6 19 v.

20 3/4 6-7' 19 3/4 6-8 19 TECHNICAL REOUIREMENTS

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COLR - 7 Revision 0 Page 1 of 15

),o FERMI 2 V

CORE OPERATING LIMITS REPORT CYCLE 7 A

Prepared by:

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/.a f 9h1[ff B. L. Ni[ers

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Date Principal Engineer - Nuclear Fuel Reviewed by:

,Y e 9 D '/6 O

L. J. Fdsson V

Date Senior Engineer - Nuclear Fuel 3/u/3s J. M. Thorfon Date Supervisof-Reactor Engineering M-Serit-9 9 G. A. Rubiey Date COLR Checklist Reviewer Approved by:

/NIcA tm d/Iu

  1. !N

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S. T-C. Hsieh Date Supervisor - Nuclear Fuel SEPTEMBER 1998

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Page 2 of 15 l

TABLE OF CONTENTS i

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1.0 INTRODUCTION

AND S UMM A R Y...........................................

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- 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 MINIM UM CRITICAL POWER RATIO................................................

... 9 3.I De fi n i t i o n........................................................

.... 9 3.2 Determination of Operating Limit MCPR............................................ 9 3.3 Calculation of MCPR(P)................

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

.I1 3.4 Calculation of MCPR(F).............................................

......................12 4.0 LINEAR HEAT GENERATION RATE.....................................

........................13 4.1 Definition...................,.......

................................. 13 4.2 Determination of LHGR Limit...........

..............................13 5.0 CONTROL ROD B LOCK INSTRUMENTATION.............................................. 1

/O 5.1 O

Defmition........................................................................

....... 14

6. 0 R E FE R E N C ES.......................................................

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COLR - 7 Revision 0 Page 3 of 15 LIST OF TABLES i O.

j TABLE 1 FUEL TYPE-DEPENDENT STANDARD MAPLHGR LIMITS.................... 6 TABLE 2 FLOW-DEPENDENT MAPLHGR LIMIT COEFFICIENTS..

......8 s

TABLE 3 OLMCPRmyio3 AS A FUNCTION OF EXPOSURE AND T....

... 10 M

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TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS...................

.... 12 4

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TABLE 5 LHGR LIMITS FOR VARIOUS FUEL TYPES........

.....................13 TABLE 6 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH l

FILTER...........................................................................................14 1

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4 COLR - 7 Revision 0 Page 4 of 15 1.0 INTRDDUCTION AND

SUMMARY

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This report provides the cycle specific plant operating limits, which are listed below, for Fermi 2, Cycle 7, as required by Technical Specifications 6.9.3. The analytical methods used to determine

> these core ope, rating limits are those

' Regulatory Commission in GESTAR II.i.2gA5reviously reviewed and approved by the Nu The cycle specific limits contained within this report are valid for the full range of the licensed operating domain.6#

4 OPERATING LIMIT TECHNICAL SPECIFICATION APLHGR 3/4.2.1 i

i MCPR 3/4.2.3 3%%

k LHGR 3/4.2.4 i

RBM 3/4.3.6 APLHGR = AVERAGE PLANAR LINEAR HEAT GENERATION RATE MCPR MINIMUM CRITICAL POWER RATIO

=

LHGR LINEAR HEAT GENERATION RATE

=

RBM ROD BLOCK MONITOR SETPOINTS

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COLR - 7 Revision 0 Page 5 of 15 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE I

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V TECH SPEC IDENT OPERATING LIMIT 3/4.2.1 APLHGR 2.1 Definition Tne AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHOR) shall be applicable to a specific planar height and is equal to averaging the LINEAR HEAT GENERATION RATE over each fuel rod in the plane.

2.2 Determination of MAPLHGR Limit The maximum APLHGR (MAPLHGR) limit is a function of reactor power, core flow, lattice type, and average planar exposure. The limit is developed to ensure gross cladding failure will not occur following a loss of coolant accident (LOCA) and that fuel thermal-mechanical design criteria will not be violated during any postulated transient events. 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 I and 2 will be met.

i The MAPLHGR limit is calculated by the following equation:

AfAPLHGRuwr = MIN (AIAPLHGR (P), AIAPLHGR (F))

where:

l AfAPLHGR(P)= AfAPFAC(P)x AfAPLHGRsm i

l AfAPLHGR (F) = AfAPFAC (F) x AfAPLHGRsw MAPLl-lGRsTo, the standard MAPLHGR limit, is defined at a power of 3430 MWt and flow of i

105 Mlbs/hr for each fuel type as a function of average planar exposure and is presented in Tabie 1. Since fuel types may contain more than one lattice type (axially), Table I represents the most limiting lattice type at each exposure point for that fuel type. When hand calculations are required as specified in Technical Specification 3/4.2.1, MAPLHGR hall be determined by interpolation from Table 1.

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COLR - 7 Revision 0 Page 6 of 15 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.

1 i

TABLE 1 FUEL TYPE. DEPENDENT STANDARD MAPLHGR LIMITS i

Standard MAPLHGR Limit (KW/FT)

Exposure Fuel Type GWD/ST 2

10 H

D D

B l

00 11.73 I l.5I i1.73 10.75 11.73 11.0L 0.2 11.79 11.54 11.79 10.79 11.79 l 1.07 1.0 11.90 11.62 l 1.90 IJ.90 11.90 11.18 2.0 12.01 11.71 12.01 11.11 12.01 11.33 3.0 12.10 11.79 12.10 11.36 12.10 11.48 4.0 12.20 11.87 12.20 11.54 12 20 11.64 50 12.30 11.96 l 2.30 11.67 12.30 I l.80 J

6.0 12.40 12.04 12.40 11.31 12.40

!! 96 i

7.0 12.51 12 13 12.51 11.95 12.51 12.13 8.0 12.62 12 23 12.62 12.09 12.62 12.29 i

9.0 12.68 12.44 12 68 12.23 12.68 12 45 1

10.0 12.70 12 48 12.70 12.39 12.70 12.61 3

g9 12.5 12 57 12.50 12.57 12.46 12.57 12.70 x /

15,0 12.17 12 19 12.17 12.18 12.17 12.48 i

17.5 11.78 11.82 11.78 11.88 l 1.78 12 18 20.0 11,39 i!45 l 1.39 11.57 11.39 11.87 25 0 10.63 10 71 10 63 10 88 10.63 11.25 t

30 0 9 91 9 99 9 91 10.15 9 91 10.64 35.0 9.24 9 28 9.24 9 43 9.24 10 01 40 0 8 62 8 59 H 62 8.73 8.62 9 28 45 0 N 03 7.91 8 01 8 05 8.03 8.59 50 0 7.45 7.24 7 45 7.37 7.45 7.93 55.0 6.84 6.56 6 84 6.68 6.84 7.25 l

56 37 6.37 56 83 6 60 6 60 6 60 57.I2 6 39 57.24 6.37 58.84 6 67 l

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Fuel Types t

9 = gel 1-P9 CUB 331-1IGZ-100M-146-T 12 = gel 1-P9 CUB 366-15GZ-100T-146-T l

10 = gel 1 P9 CUB 353-10GZ-100M-146-T 13 = gel 1-P9 CUB 331-1 IGZ-100M-146-T 1I = gel 1-P9 CUB 331-1IGZ-100M-146-T 14 = gel 1-P9 CUB 380-12GZ-100T-146-T i

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2.2.1 Calculation of MAPFAC(P) 0 (f

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

For 0 s P < 25 :

No thermal limits monitoring is required.

For 25 s P < 30 :

With turbine hvuass OPERABLE, l

For core flow s 50 Mlbs/hr, AfAPFAC (P) = 0.606 + 0.0038 (P - 30)

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

A With turbine hvoass INOPERAHLE, l

For core flow s 50 Mlbs/hr, i

t AfAPFAC(P) = 0.490 + 0.0050(P -30) l

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

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For 30 s P s 100 :

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AfAPFAC(P) = 1.0 + 0.005224(P - 200)

F where:

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

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COLR - 7 Revision 0 4

Patre 8 of I5 2.2.2 Calculation of MAPFAC(F)

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

For core now s 43.5 Mlbs/hr,

%T MAPFAC(F) = ( Arx 100 )+.Br where:

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WT = Core Dow (Mlbs/hr).

Ap = Given in Table 2.

Be = Given in Table 2.

For core flow > 43.5 Mibs /hr and s 55 Mlbs/hr, MAPFAC(F) = 0.730 For core flow > 55 Mlbs/hr, (3

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WT MAPFAC(F) = MIN (l.0, Arx 100 + Br) where:

WT = Core flow (Mlbs/hr).

Ap = Given in Table 2.

1 Be = Given in Table 2.

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

(Mlbs/hr)

Ap Be i10 0.6800 0.4340

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

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COLR - 7 Revision 0 Page 9 of 15 3.0 MINIMUM CRITICAL, POWER RATIO n.

U' TECH SPEC IDENT OPER.ATING LIMIT 3/4.2.3 MCPR 3.1

. Definition The CRITICAL POWER RATIO (CPR) shall be the ratio of that power in the assembly which is j

calculated by application of an NRC approved critical power correlation to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR that exists in the core.

3.2 Determination of Operating Limit MCPR p

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 of 1.11 and x

.an analysis of abnormal operational transients. To ensure that the Safety Limit MCPR is not exceeded during any anticipated abnormal operational transient, the rr.ost limiting transients have been analyzed to determine which event will cause the largest reduction in CPR. Two different core average exposure conditions are evaluated. The result is an Operating Limit MCPR which is a function of exposure and T.

T is a measure of scram speed, and is defined in Technical Specification Section 3/4.2.3.

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 by 0.02, but OLMCPR does not change.

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COLR - 7 Revision 0 Page 10 of 15 3.3 Calculation of MCPR(P) u( %

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

MCPR(P) = Kex 0LMCPRmnar OLMCPRuxvio3 shall be determined by interpolation from Table 3, and i shall be calculated by using Technical Specification Section 3/4.2.3.

Kp, the core power-dependent MCPR Operating Limit adjustment factor, shall be calculated by using Section 3.3.1.

TABLE 3 OLMCPRwvios AS A FUNCTION OF EXPOSURE AND T EXPOSURE D

CONDITION (MWD /ST)

OLMCPR oono3

.(

lloth Turbine Bypass and i

Moisture Separator Reheater OPERA 11LE BOC to 9000 t=0 1.30 t=1 1.35 9000 to EOC t=0 1.32 t=1 1.40 Either Turbine Bypass or Moisture Separator Reheater INOPERAllLE BOC to EOC t=0 1.37 t=1 1.45 Iloth Turbine Bypass and Moisture Separator Reheater INOPERAllLE BOC to EOC t=0 1.40 t=1 1.48

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COLR - 7 Revision 0 Page 11 of 15 3.3.1 Calculation of Kr

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The core power-dependent MCPR operating limit adjustment factor, Kp, shall be calculated by usine one of the following equations:

For 0 s P < 25 -

No thermal limits monitoring is required.

For 25 s P < 30 -

When turbine bypass is OPERABLE, (Karr + (0.026 x (30- P))) x (1.1I/1.07)

Ke =

OLMCPR mnas i

where:

Kaye = 1.90 for core flow s 50 Mlbs/hr

= 2.23 for core flow > 50 Mlbs/hr

(

When turbine bypass is INOPERABLE, (Kaye + (0.054 x (30- P))) x (1.11/l.07)

Kr =

OLMCPRiwnas where:

KHYP = 2.26 or core flow s 50 Mlbs'hr

= 3.03 for core flow > 50 Mlbs/hr For 30 s P < 45 Ke = 1.23 + (0.0134 x (45-P))

For 45 s P < 60 -

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

For 60 s P s 100 :

Ne = 1.0 + (0.00375 x (IOO-P))

where:

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

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COLR-7 Revision 0

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Page 12 of 15 3.4 Calculation of MCPR(F)

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

WT i

MCPR(F) = (1.1I/l.07) x MAX (l.20, ( Ar 100 + Br))

x where:

WT = Core flow (Mlbs/hr)..

Ar = Given in Table 4.

Be = Given in Table 4.

TABLE 4 FLOW-DEPENDENT MCPR LIMIT COEFFICIENTS Maximum Core Flow *

(Mlbs/hr)

Ar Br I l'0

-0.600' l.731

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

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COLR - 7 Revision 0 Page 13 of 15 4.0 LINEAR HEAT GENERATION RATE OC)

.g TECH SPEC IDENT OPERATTNG LIMIT l

3/4.2.4 LHGR 4.1 Definition The LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit i

length.

4.2 Deterrnination of LHGR Li.mit The thermal expansion rates of UO pellets and Zircaloy cladding are different in that, during 2

heatup, the fuel pellet could come into contact with the cladding and create stress.

By maintaining the operating LHGR below the applicable LHGR limit and the operating MAPLHGR below the applicable MAPLHGR limit, it is assured that all thermal-mechanical design bases and licene.ing limits for the fuel will be satisfied.

A t

The LHGR limit is defined as a function of lattice type and average planar exposure and is presented in Table 5. Since fuel types may contain m; re than one lattice type (axially), Table 5 represents the most limiting lattice type at each exposure point for that fuel type. When hand calculations are required, the LHGR limit shall be determined by interpolation from Table 5.

TABLE 5 LHGR LIMITS FOR VARIOUS FUEL TYPES LHGR Limit (KW/FT)

Exp>sure Fuel Type MLv1T 9

.19

.U U

D L4 l

00 14 40 14 40 14.40 14 40 14 40 14 40 l

9 81 14 40 14 40 14 40 14 40 10 70 l

14 40 10 82 l

14 40 54 61 l

54.72 6 80 6 80 j

56.20 6.80 6 80 6 80 6 80 Fuel'/ypes (O

9 = GElI P9 CUB 331-1IGZ.100M-146-T

2 = gel 1-P9 CUB 366-15GZ-100T-146 T

,/

10 = Gell-P9 CUB 353-10GZ-100M 146-T 13 = 'lEll P9 CUB 331-llGZ-100M-146-T Ii = gel 1-P9 CUB 331-1IGZ !(X)M-146-T I4 = GCi 1 INCUB380-12GZ-l(XIT-146-T

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4 COLR - 7 Revision 0 Page 14 of 15 5.0 CONTROL ROD BLOCK INSTRUMENTATION.

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TECH SPEC IDENT SETPOINT 3/4.3.6 RBM 5.1 Definition The nominal trip setpoints and allowable values of the control rod withdrawal block instrumentation for use in Technical Specification 3/4.3.6 are shown in Table 6. These values are consistent with the bases of the APRM Rod Block Technical Specification Improvement Program (ARTS) and the MCPR operating limits, TABLE 6 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS WITH FILTER Setpoint Trip Setpoint Allowable Value e

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LPSP 27.0 28.4 j

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 4

where:

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

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E COLR 7 Revision o Page 15 of 15

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6.0 REFERENCES

1.

" General Electric Standard Application for Reactor Fuel (GESTAR H)," NEDE-24011-P-A, Revision 13 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 4

. 3.

" Fermi-2 SAFER /GESTR-LOCA, Loss-of-Coolant Accident Analysis," NEDC-31982P, July 199!, and Errata and Addenda No.1, April 1992 4.

" Lattice-Dependent MAPLHGR Report for Fermi Power Plant Unit 2 Reload 6 Cycle 7,"

.GE Nuclear Energy, Jl1-03346-10AA, Revision 0, September 1998 5.

" Supplemental Reload Licensing Report for Fermi Power Plant Unit 2 Reload 6, 1

Cycle 7," GE Nuclear Energy, Jl1-03346-10, Revision 0, September 1998 6.

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 7.

Letter from J. F. Stang to W, S. Orser, " Amendment No. 53 to Facility Operating License -

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

8.

" Maximum Extended Operating Domain Analysis for Detroit Edison Company Enrico Fermi Energy Center Unit 2," GE Nuclear Energy, NEDC-31843P, July 1990 9.

Letter from R. J. Howard to M. K. Deora and H. I. Hubeny, " Operating Flow Dependent MCPR and MAPLHGR Thermal Limits," TDEC-PE-134, September 30.1990

.10.

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

I 1.

Letter from R. H. Szilard to B. L. Myers," ARTS Multipliers Update for Fermi 2 Cycle 7." September 24,1998

'12.

Letter from R. D. Williams to Dr. S. T-C. Hsieh, "SLMCPR Submittal for Fermi 2 Cycle 7," RDW:98-059, May 8,1998

' 13.

Letter from Andrew J. Kugler (USNRC) to Douglas R. Gipson (Detroit Edison), " Fermi-2

- Issuance of Amendment RE: Cycle-Specific Safety Limit Minimum Critical Power Ratios for Cycle 7 (TAC NO. MA2003), dated September 21,1998 O

.

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