ML040330571

Transmittal of Core Operating Limits Report (COLR) for R.E. Ginna Nuclear Power Plant

ML040330571
Person / Time
Site:	Ginna
Issue date:	01/23/2004
From:	Widay J Rochester Gas & Electric Corp
To:	Clark R Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML040330571 (12)

Text

Joseph A. Widay R OW Vice President Always at Your Service January 23, 2004 and Plant Manager Mr. Robert L. Clark Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

Transmittal of Core Operating Limits Report (COLR)

Rochester Gas & Electric Corporation R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a):

Technical Specification 5.6.5

Dear Mr. Clark:

Ginna Station Technical Specification 5.6.5 requires that RG&E provide the NRC with any revisions of the COLR. As such, attached please find a copy of Revision I of this document for Cycle 31.

Future revisions to this document will be forwarded to the NRC in accordance with the applicable technical specification.

Very truly yours, a-4~~a se A. Widay Attachment xc:

Mr. Robert Clark (Mail Stop 0-8-C2)

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S. NRC Ginna Senior Resident Inspector An equal opportunity employer 89 East Avenue I Rochester, NY 14649 tel (585) 546-2700 www.rge.com

/0 0

An Energy East Company

COLR Cycle 31 R.E. Ginna Nuclear Power Plant Core Operating Limits Report COLR Cycle 31 Revision 1 Responsible Manager:

Effective Date:

Mark Flaherty

-A

% Z 013 2 -2 01 2004 Controlled Copy No.

Record Cat.# 4.43.2 R.E. Ginna Nuclear Power Plant C01-R-1 Revision 1

COLR Cycle 31 1.0 CORE OPERATING LIMITS REPORI 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:

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 (FNAH) 3.2.3 AXIAL FLUX DIFFERENCE (AFD) 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 1

COLR Cycle 31 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed n 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 SHUTDOWN MARGIN' (LCO 3.1.1) 2.1.1 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 - 1 for the number of reactor coolant pumps in operation (non main feedwater operation).

2.1.2 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 - 1.

2.1.3 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 -

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

2.2 MODERATOR TEMPERATURE COEFFICIENT' (LCO 3.1.3) 2.2.1 The Moderator Temperature Coefficient (MTC) limits are:

The BOL ARO/HZP - MTC shall be less positive than +5.0 pcm/OF 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/0F.

where:

ARO stands for All Rods Out BOL stands for Beginning of Cycle Life EOL stands for End o Cycle Life HZP stands for Hot Zero Power RTP stands for RATED THERMAL POWER R.E. Ginna Nuclear Power Plant COLR-3 Revision 1

COLR Cycle 31 2.3 Shutdown Bank Insertion Limit (LCO 3.1.5) 2.3.1 The shutdown bank shall be fully withdrawn which is defined as 2 221 steps.

2.4 Control Bank Insertion Limits (LCO 3.1.6) 2.4.1 The control banks shall be limited in physical insertion as shown in Figure COLR - 2.

2.4.2 The control banks shall be moved sequentially with a 100 ( 5) step overlap between successive banks.

2.5 Heat Flux Hot Channel Factor (F0 (Z)) 2 (LCO 3.2.1) 2.5.1 FQ(Z) < ((F0 ) *K(Z) / P) when P > 0.5 FQ(Z)

((FQ) *K(Z) 0.5) when P 0.5 where:

Z is the height in the core, F0 = 2.45, K(Z) is provided in Figure COLR - 3, and P = THERMAL POWER / RATED THERMAL POWER 2.6 Nuclear Enthalpy Rise Hot Channel Factor (FNH)l (LCO 3.2.2) 2.6.1 FN AH < FRTPAH * (1 + PFAH * (1-P))

where:

FRTPAH= 1.75, PFAH = 0.3, and P = THERMAL POWER / RATED THERMAL POWER R.E. Ginna Nuclear Power Plant COLR-4 Revision 1

COLR Cycle 31 2.7 AXIAL FLUX DIFFERENCE 3 (LCO 3.2.3) 2.7.1 The AXIAL FLUX DIFFERENCE (AFD) target band is +/- 5%. The actual target bands are provided by Procedure RE-11.1.

2.7.2 The AFD acceptable operation limits are provided in Figure COLR - 4.

2.8 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB)

Limits4 (LCO 3.4.1) 2.8.1 The pressurizer pressure shall be 2 2205 psig.

2.8.2 The RCS average temperature shall be

• 577.5 F.

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

2.9 Boron Concentration (LCO 3.9.1) 2.9.1 The boron concentrations of the hydraulically coupled Reactor Coolant System, the refueling canal, and the refueling cavity shall be 2 2300 ppm.

R.E. Ginna Nuclear Power Plant COI-R-5 Revision 1

COLR Cycle 31

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-10924-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-1 0924-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-1 0924-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-1 3677-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-1261 0-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-11397-P-A, "Revised Thermal Design Procedure", April 1989.

R.E. Ginna Nuclear Power Plant COLR-6 Revision 1

COLR Cycle 31 3-x 05 OPERATION (02.40)

Ii Z

(1500JAS 1

U)05 0

1500 1000 500 0

COOLANT BORON CONCENTRATION (ppm)

O---

eOLoopOperaton TwoLoopO peraion-nonMFW - -

TwoLoopOperabon-MFWl NOTE:

Two Loop Opertbn non MFW means that the main featsr systsn Is not supy he steam Getwom.

Tv Locp Operation MFW leanis mathe main fedwater system is suvDyina tthe UamDewators.

Figure COLR - 1 REQUIRED SHUTDOWN MARGIN R.E. Ginna Nuclear Power Plant COLR-7 Revision 1

COLR Cycle 31

+ 220

=)8

_ =

=

B 200 B

Bank (1X. 14)

-o 180 (0l84)7-g160 0-140 t120

.0 100 o 80

~60 m40 20

~~~~~~~~~~(30, 0

10 20 30 40 50 60 70 80 90 100 Core Power (Percent of 1520 MWT)

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

Figure COLR - 2

. CONTROL BANK INSERTION LIMITS R.E. Ginna Nuclear Power Plant COLR-8 Revision 1

COLR Cycle 31 1.2 N

v 1.0 Lo 0

(U LL 0.8_

m.

L 0.6 Total F 2.450 Elevaton ft)

Kg

< 0.4 0.0 l.0 0.4 11.783 1.0 E 0.2 0z 0.0 0.0 2.0 4.0 6.0 8.0 10.0 11.783 Elevation (ft)

FIGURE 3 Figure COLR - 3 K(Z) - NORMALIZED F(Z) AS A FUNCTION OF CORE HEIGHT R.E. Ginna Nuclear Power Plant COLR-9 Revision

COLR Cycle 31 1-0 a-i:

100 80 60 40 DO NOT OPERATE IN THIS AREA WTH AFD

(.11,90)

(190)

ACCEPTABLE OPERATION WITH AFD

....... OT. S ETHE'- '- '

TARGET BAND WITH ci HR PENALTY DEVIATION TIME J........... ;_____...........

(-31,50) p1,60)

OPERATION W.............

.W.....................

20

' 0

-30

-20

-10 0

10 20 30 AXIAL FLUX DIFFERENCE (%)

FIMIRWV A Figure COLR - 4 AXIAL FLUX DIFFERENCE ACCEPTABLE OPERATION LIMITS AS A FUNCTION OF RATED THERMAL POWER R.E. Ginna Nuclear Power Plant COLR-1 0 Revision 1

COLR Cycle 31 END NOTES

1.

(Limits generated usirid Reference 1)

2.

(Limits generated using References 1 through 7)

3.

(Limits generated using References 1 and 8)

4.

(Limits generated using Reference 9)

R.E. Ginna Nuclear Power Plant C01-R-1 1 Revision 1