ML052770243

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Transmittal of Core Operating Limits Report (COLR)
ML052770243
Person / Time
Site: Ginna Constellation icon.png
Issue date: 09/26/2005
From: Korsnick M
Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML052770243 (14)
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Maria Korsnick Site Vice President Constellation EnergyW Generation Group R.E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, New York 14519-9364 585.771.3494 585.771.3943 Fax maria.korsnick@constellation.com September 26, 2005 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:

SUBJECT:

Document Control Desk R.E. Ginna Nuclear Power Plant Docket No. 50-244 Transmittal of Core Operating Limits Report (COLR)

In accordance with the R.E. Ginna Nuclear Power Plant Improved Technical Specification 5.6.5, which requires the submittal of revisions to the COLR, the attached report is hereby submitted. Should there be any questions, please contact George Wrobel at (585) 771-3535 or george.wrobel(constellation.com.

Very truly yours, Mary G. Korsnick Enclosure cc:

S. J. Collins, NRC P. D. Milano, NRC Resident Inspector, NRC

-A Do/

I (01u105

COLR Cycle 32 Constellation Energy R.E. Ginna Nuclear Power Plant R.E. Ginna Nuclear Power Plant Core Operating Limits Report COLR Cycle 32 Revision I Responsible Manager4 W

George Wrobe Effective Date:

9 - 2/-2 oc5 9/21/2005 Controlled Copy No.

Record Cat.# 4.43.2 R.E. Ginna Nuclear Power Plant COLR-1 Revision 1

COLR Cycle 32 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for the R.E. Ginna Nuclear Power Plant has been prepared in accordance with the requirements of Technical Specification 5.6.5.

The Technical Specifications affected by this report are listed below:

2.1 Safety Limits (SLs) 3.1.1 SHUTDOWN MARGIN (SDM) 3.1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC) 3.1.5 Shutdown Bank Insertion Limit 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor (FQ(Z))

3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (FN H) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 3.3.1 Reator Trip System (RTS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits 3.9.1 Boron Concentration R.E. Ginna Nuclear Power Plant COLR-2 Revision I

COLR Cycle 32 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using the NRC approved methodologies specified in Technical Specification 5.6.5. All items that appear in capitalized type are defined in Technical Specification 1.1, Definitions.

2.1 SAFETY LIMITS (SLs)1 (2.1) 2.1.1 In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) average temperature, and pressurizer pressure shall not exceed the SLs specified in Figure COLR - 1.

2.2 SHUTDOWN MARGIN' (LCO 3.1.1) 2.2.1 The SHUTDOWN MARGIN in MODE 2 with Keff < 1.0 and MODES 3 and 4 shall be greater than or equal to the limits specified in Figure COLR - 2 for the number of reactor coolant pumps in operation (non main feedwater operation).

2.2.2 The SHUTDOWN MARGIN in MODE 4 when both reactor coolant pumps are not OPERABLE and in operation and in MODE 5 shall be greater than or equal to the one loop operation curve of Figure COLR - 2.

2.2.3 The SHUTDOWN MARGIN required in LCO 3.1.4, LCO 3.1.5, LCO 3.1.6, LCO 3.1.8, and LCO 3.4.5 shall be greater than the limits specified in Figure COLR -

2 for the number of reactor coolant pumps in operation and the status of the main feedwater system.

2.3 MODERATOR TEMPERATURE COEFFICIENT' (LCO 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOL ARO/HZP - MTC shall be less positive than +5.0 pcm/GF for power levels below 70% RTP and less than or equal to 0 pcm/OF for power levels at or above 70% RTP.

The EOL ARO/RTP - MTC shall be less negative than -42.9 pcm/lF.

where:

ARO stands for All Rods Out BOL stands for Beginning of Cycle Life R.E. Ginna Nuclear Power Plant COLR-3 Revision 1

COLR Cycle 32 EOL stands for End of Cycle Life HZP stands for Hot Zero Power RTP stands for RATED THERMAL POWER I

2.4 I

I 2.5 Shutdown Bank Insertion Limitl (LCO 3.1.5) 2.4.1 The shutdown bank shall be fully withdrawn which is defined as 2 221 steps.

Control Bank Insertion Limitsl (LCO 3.1.6) 2.5.1 The control banks shall be limited in physical insertion as shown in Figure COLR - 3.

2.5.2 The control banks shall be moved sequentially with a 100 (+/- 5) step overlap between successive banks.

I I

1 2.6 1

Heat Flux Hot Channel Factor (FQ(Z))2 (LCO 3.2.1) 2.6.1 FQ(Z) < ((FQ) *K(Z) / P) when P > 0.5 FQ(Z) * ((FQ) *K(Z) / 0.5) when P

  • 0.5 I

where:

Z is the height in the core, FQ = 2.45, K(Z) is provided in Figure COLR - 4, and P = THERMAL POWER I RATED THERMAL POWER Nuclear Enthalpy Rise Hot Channel Factor (FNAH)1 (LCO 3.2.2) 2.7 R.E. Ginna Nuclear Power Plant COLR-4 Revision I

COLR Cycle 32 2.7.1 F NAH

  • FRTPAH * (1 + P FAH (1-P))

where:

FRTPAH= 1.75, PFAH = 0.3, and P = THERMAL POWER / RATED THERMAL POWER 2.8 AXIAL FLUX DIFFERENCE 3 (LCO 3.2.3) 2.8.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +/- 5%. The actual target bands are provided by Procedure RE-11.1.

2.8.2 The AFD acceptable operation limts are provided in Figure COLR - 5.

2.9 Reactor Trip System (RTS) Setpoints5 l

(LCO 3.3. 1)

R.E. Ginna Nuclear Power Plant COI-R-5 Revision I

COLR Cycle 32 2.9.1 Overtemperature AT Setpoint Parameter Values Parameter Value Overtemperature AT reactor trip setpoint K1

  • 1.20 Overtemperature AT reactor trip K2 2 0.000900/psi depressurization setpoint penalty coefficient Overtemperature AT reactor trip heatup K3 2 0.0209/OF penalty setpoint coefficient Measured lead time constant T, 2 25 seconds Measured lag time constant t 2 < 5 seconds f(AI) constants f(AI) = 0 when qt - qb is < + 13% RTP f(AI) 1.3 {(qt - qb) - 13) when qt - qb is > + 13% RTP 2.9.2 Overpower AT Setpoint Parameter Values Parameter Value Overpower AT reactor trip setpoint K4 < 1.077 Overpower AT reactor trip heatup setpoint K5 = 0/0F for T < T' penalty coefficient 2 0.0011/OF for T 2 T' Overpower AT reactor trip thermal K6 2 0.0262/0F for increasing T time delay setpoint penalty

= 0.00/1F for decreasingT Measured impulse/lag time constant T3 < 10 seconds f(AI) constants f(AI) = 0 when qt - qb is * + 13% RTP f(AI)= 1.3 {(qt - qb) -13) when qt - qb is > + 13% RTP 2.10 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits4 (LCO 3.4.1) 2.10.1 The pressurizer pressure shall be 2 2205 psig.

R.E. Ginna Nuclear Power Plant COLR-6 Revision I

COLR Cycle 32 2.10.2 The RCS average temperature shall be < 577.5 "F.

2.10.3 The RCS total flow rate shall be 2 177,300 gpm (includes 4% minimum flow uncertainty per Revised Thermal Design Methodology).

2.11 Boron Concentration1 (LCO 3.9.1) 2.11.1 The boron concentrations of the hydraulically coupled Reactor Coolant System, the refueling canal, and the refueling cavity shall be 2 2300 ppm.

3.0 REFERENCES

1.

WCAP-9272-P-A, Westinghouse Reload Safety Evaluation Methodology, July 1985.

2.

WCAP-10054-P-A and WCAP-10081-A, "Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code," August 1985.

3.

WCAP-1 0924-P-A, Volume 1, Revision 1, "Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 1: Model Description and Validation Responses to NRC Questions," and Addenda 1,2,3, December 1988.

4.

WCAP-10924-P-A, Volume 2, Revision 2, "Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 2: Application to Two-Loop PWRs Equipped with Upper Plenum Injection," and Addendum 1, December 1988.

5.

WCAP-10924-P-A, Volume 1, Revision 1, Addendum 4, "Westinghouse Large-Break LOCA Best-Estimate Methodology, Volume 1: Model Description and Validation, Addendum 4: Model Revisions," March 1991.

6.

WCAP-13677-P-A, "10 CFR 50.46 Evaluation Model Report: WCOBRA/TRAC Two-Loop Upper Plenum Injection Model Updates to Support ZIRLOTM Cladding Option,"

February 1994.

7.

WCAP-12610-P-A, "VANTAGE + Fuel Assembly Reference Core Report," April 1995.

8.

WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report,", September 1974.

9.

WCAP-1 1397-P-A, "Revised Thermal Design Procedure", April 1989.

10.

WCAP-8745, "Design Basis for the Thermal Overpower Delta T and Thermal 10 Overtemperature Delta T Trip Functions", March 1977.

R.E. Ginna Nuclear Power Plant COLR-7 Revision I

COLR Cycle 32 670 660 650 640 p630 C 620 1 610 600 590 580 570 '-

0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 POWER (Fraction of Nominal)

I Figure COLR - 1 Reactor Safety Limits R.E. Ginna Nuclear Power Plant COLR-8 Revision 1

COLR Cycle 32 3

2.5 ERATION

-0245) 8(15 tO,1.00 (1002.40)

L*WT o

r

-Ml Tw LC.

op

  • u UF-en St ~i ewtrUtmi Udh U) 1.5 ERAIO 0

1501000 500 0

COOLANT BORON CONCENTRATION (ppm)

. (m op Operabon Two Loop Operation. non MFW -

Two Loop Opmraon - MFW N07E:

Two Loop Overatbr. rmn mFW meam mat Irn m~in toodw~lo systam is nct suppmmr tie tarni gneat8r.0 TWO Loop 0PKa~I1*n MFW Moons tin lie Main Feedwater 3yotem is mijpalbg thSteteam generali.

Figure COLR -2 REQUIRED SHUTDOWN MARGIN R.E. Ginna Nuclear Power Plant COLR-9 Revision 1

COLR Cycle 32 C 220 =

=-

8.34 B 200 Ba -

sI 180 to_

7c184 160

@ 120

-Dtn 1 2g hi0 O

.2100 0 80-20 3

40 5

~60-Core Power (Percent of 1520 MWTf)

"The fully withdrawn position is defined as 2 221 steps.

Figure COLR -3 CONTROL BANK INSERTION LIMITS R.E. Ginna Nuclear Power Plant COLR-1 0 Revision 1

COLR Cycle 32 1.2 A-%

X 1.0

%Wo 0

4-u U

LI. 0.8 4 0.6 a.

4 0.4 la E 0.2 Lo 0

z 0.0 Total Fo = 2.450 Elevaton (ft)

KS 0.0 1.0 11.783 1.0 0.0 2.0 4.0 I

6.0 Elevation (ft) 10.0 11.783 FIGURE 3 Figure COLR -4 K(Z) - NORMALIZED FQ(Z) AS A FUNCTION OF CORE HEIGHT R.E. Ginna Nuclear Power Plant COLR-1 1 Revision 1

COLR Cycle 32 100 DO NOT OPERATE IN THIS AREA WITH AFD OUTSIDE THE TARGET BAN)

.....................C........

... -,..........1 -

80/.

\\

/_

ACCEPTABLE OPERATION O

/

WITH AFO Q:............... t

' D H'..

O M D TH

./UT=

SDE

\\h TARGET BAND WITH (1 I R PENALTY 60 DEYAON fl, THAE

_ ~~~~~~~~..................... __............... _............

CK

~~(-31,60)

.1f0 fiE 40 I-...ACCEPTABLE

...... OEAIN...

OPERATION 20

-30

.20

-10 0

10 20 30 AXIAL FLUX DIFFERENCE (%)

Figure COLR - 5 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATED THERMAL POWER R.E. Ginna Nuclear Power Plant COLR-1 2 Revision 1

COLR Cycle 32 END NOTES

1.

(Limits generated using Reference 1)

2.

(Limits generated using References 1 through 7)

3.

(Limits generated using References I and 8)

4.

(Limits generated using Reference 9)

5.

(Limits generated using Reference 10)

R.E. Ginna Nuclear Power Plant COLR-1 3 Revision 1

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