3F0902-09, Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3

Submittal of Core Operating Limits Report, Cycle 13, Revision 1, for Crystal River Unit 3

ML022770525
Person / Time
Site:	Crystal River
Issue date:	09/24/2002
From:	Terry J Florida Power Corp
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
3F0902-09, ITS 5.6.2.18
Download: ML022770525 (24)

Text

Florida Power A Progress Energy Company Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: ITS 5.6.2.18 September 24, 2002 3F0902-09 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Crystal River Unit 3 - Core Operating Limits Report, Cycle 13, Revision 1

Dear Sir:

Florida Power Corporation hereby submits the Core Operating Limits Report (COLR),

Cycle 13, Revision 1, for Crystal River Unit 3 (CR-3). The COLR, including any midcycle revisions or supplements, is required to be submitted to the NRC upon issuance for each reload cycle in accordance with CR-3 Improved Technical Specifications, Section 5.6.2.18.

This letter established no new regulatory commitments.

If you have any questions regarding this submittal, please contact Mr. Sid Powell, Supervisor, Licensing and Regulatory Programs at (352) 563-4883.

Sincerely, JZiX.Terry Engineering Manager JHT/ff Attachment xc: Regional Administrator, Region II Senior Resident Inspector NRR Project Manager Crystal River Nuclear Plant 15760 W Power Line Street Crystal River, FL34428

FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 Core Operating Limits Report Cycle 13, Revision I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 1 of 22 Florida Power Corporation Crystal River Unit 3 Cycle 13 Core Operating Limits Report Revision 1 I Referencing Improved Technical Specifications

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 2 of 22 1.0 Core Operating Limits This Core Operating Limits Report for CR3 Cycle 13 has been prepared in accordance with the requirements of Technical Specification Section 1.1 and 5.6.2.18. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. I These methods are documented in BAW-10179PA, Rev. 3 "Safety Criteria and Methodology for Acceptable Cycle Reload Analyses". The Cycle 13 limits generated using this methodology above are documented in BAW-2391, Revision 1, "Crystal River Unit 3 Cycle 13 Reload Report", dated September 2001.

The following limits are included in this report.

SL 2.1.1.1 AXIAL POWER IMBALANCE PROTECTIVE LIMITS SL 2.1.1.2 AXIAL POWER IMBALANCE PROTECTIVE LIMITS LCO 3.1.1 SHUTDOWN MARGIN LCO 3.1.3 MODERATOR TEMPERATURE COEFFICIENT SR 3.1.7.1 API/RPI POSITION INDICATION AGREEMENT LCO 3.2.1 REGULATING ROD INSERTION LIMITS LCO 3.2.2 AXIAL POWER SHAPING ROD INSERTION LIMITS LCO 3.2.3 AXIAL POWER IMBALANCE OPERATING LIMITS LCO 3.2.4 QUADRANT POWER TILT LCO 3.2.5 POWER PEAKING FACTORS LCO 3.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SR 3.4.1.1 RCS PRESSURE DNB LIMITS SR 3.4.1.2 RCS TEMPERATURE DNB LIMITS SR 3.4.1.3 RCS FLOW RATE DNB LIMITS LCO 3.9.1 REFUELING BORON CONCENTRATION I

F01-0002, Revision 1 Crystal River Unit 3 Attachment I Cycle 13 Core Operating Limits Report Page 3 of 22 Axial Power Imbalance Protective Limits 120 -

(-43.0, 112.0) (28.9, 112.0) 110+

Ac ceptable 4 Puimp Operation J (-52.3, 99.9) 100+

(-43.0, 89.5) Ar'~ (28.9. 89.5)

(52.6, 79.9)

(-52.3, 77.4)

Acceptable 3 and 4 70+/-

Pump Operation 60+

(52.6, 57.4) 50+

This Figure is referred to byT.S SI 2.1.1.1 1040 This Figure is referred to by T.S SL 2.1.1.2

'a

• o E

.~30 I-n: 20~

10+

I U I I  :. LI

-80 -60 -40 -20 0 20 40 60 80 Axial Power Imbalance, %

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F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 4 of 22 Shutdown Margin (SDM)

Normal operating procedures require RCS boration to 1.0%Ak/k Subcritical at 73'F prior to bypassing EFIC actuation on low steam generator pressure, or when high steam generator levels exist during secondary system chemistry control and steam generator cleaning in MODES 3, 4, and 5,

therefore Mode 3,4,5 SDM > 1.0% Ak/k These limits are referred to by Technical Specification LCO 3.1.1

Reference:

Improved Technical Specification Bases B3.1.1.

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F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 5 of 22 Moderator Temperature Coefficient Limit Lower Limit MTC at HFP > -3.58x10- 4 A k/k/OF Upper Limit MTC < 0.9x10-4 A k/k/OF when Thermal Power < 95% RTP MTC < 0.0 when Thermal Power > 95 % RTP The following Upper Limits may not be exceeded (Limits ensure the validity of the ECCS analysis is preserved) for operation in MODES 1 and 2:

1 0.9 --------------------------------------------------

0.8 - - - - - - - - - - - . . . . . . . . . . . . . ---------

oD 0

0.7 -------- --- ----------- --------- ----------..........

LL 0.6 ------------- --------- ------------------

0 0.5 ------------ ------ --- --------- ------------ --------

E 01 0

2 0.4 ---------------------- ------- -------------------

0

=E 0.3 . . . . . . . . . . - - - - - - - - - - . . . . . . - - - - - - - - - --- - - - - - - - -

0.2 . . . . . . . . . . - - - - - - - - - --- - - - - - - - -

0.1 ------------------------------------ --------------

0 0 20 40 60 80 100 Percent Full Power These limits are referred to by Technical Specification LCO 3.1.3 I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 6 of 22 Absolute Position Indicator / Relative Position Indicator Agreement Limits 2.7 % when the comparison is performed using the plant computer, or 3.5% when the comparison is performed using the panel meters on the main control board.

These limits are referred to by Technical Specification SR 3.1.7.1

Reference:

"Crystal River Unit 3 - Issuance of Amendment Re: Dual Channel Control Rod Position Indication (TAC No. M82990)", Licensing Amendment No. 144, Letter from H.S. Silver to P.M. Beard, June 25, 1992.

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F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 7 of 22 Regulating Rod Group Insertion Error Adjusted Limits Four Pump Operation 0 EFPD to EOC 110 100 90 80 0

70 E

I"(D 60 (D 50 I

M*

-0 40 0~

30 20 10 0

0 50 100 150 200 250 300 Rod Index, % Withdrawn Note 1: A Rod group overlap of 25 +/-5% between sequential groups 5 and 6, and 6 and 7 shall be maintained Note 2" This figure shall be used up to, during, and after APSR withdrawal per LCO 3.2.2 I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 8 of 22 Regulating Rod Group Insertion Error Adjusted Limits Three Pump Operation 0 EFPD to EOC 110 100 90 80 0

70 a

60 cc 50

-0 40 0

M-30 20 10 0

0 50 100 150 200 250 300 Rod Index, % Withdrawn Note 1: A Rod group overlap of 25 +5% between sequential groups 5 and 6, and 6 and 7 shall be maintained Note 2: This figure shall be used up to, dunng, and after APSR withdrawal per LCO 3 2 2

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 9 of 22 AXIAL POWER SHAPING ROD INSERTION LIMITS Up to 630 EFPD the APSRs may be positioned as necessary. The APSRs shall be completely withdrawn (100%) by 650 EFPD. Between 630 and 650 EFPD, the APSRs may be withdrawn.

However, once withdrawn during this period, the APSRs shall not be reinserted.

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F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 10 of 22 Axial Power Imbalance Error Adjusted Operating Limit and Trip Setpoint Envelopes Four Pump Operation 0 EFPD to EOC 120

(-30, 108) (17, 108)

/ (-16.5, 106.5) ,1111-- (16.27, 106.5)

.- (-17* 102) 100 (14, 102) "

(-42 90.5) (-22. 92) 90 (20, 92) M

(-33.7,(89.3) N

,(.30, 80) 80 (23, 80) ..

S" ,(34,74)

• 70-¶ 70"!(43, 70.5)

I *.

• lp (-30, 60) 60- (30,60) 0 Restricted Acceptable . 50 Acceptable ._.Restricted Operation Operation Operation . Operation 0

ILI

/ a_40:

,, IThis Figure is

/I-- referred to by

/T.S.,co3.2.31

• ~20 Trip Setpoint 10 Envelopes referred

'10o- to by T.S. LCO 3 3.1  :

• , 0.

-50 -40 -30 -20 -10 0 10 20 30 40 50 Axial Power Imbalance, %

- - Allowable Trip Setpoint Envelope - -Operating Limit Envelope --- *-Actual Tnp Setpoint Envelope

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 11 of 22 Axial Power Imbalance Error Adjusted Operating Limit and Trip Setpoint Envelopes Three Pump Operation 0 EFPD to EOC 90-(-30, 806) (17, 80.6)

&- -"R- -

/(-16.5, 79.88) '

. (16.27,79.88)

/- -(-17,77) (14,77) %

70

/ (-22, 69) (20,69) \

(-42,63.1)

(-33.7, 62.68) " (-30, 60) 60 (23,60) .

504 (34, 47.38)

Y (-30,45) (30, 45) u \. (43, 43 1) 40+

S* Acceptable Acceptable Restricted Restricted Operation Operation Operation 0

Operation

• I 30-I E

• I This Figure is referred to byI 20+ IT.S. LCO 3.2.31 Ca Trip Setpoint 0

10+ Envelopes referred I.. to by T.S. LCO 3.3.1 2i A = *

-50 -.40 -30 -20 -10 0 10 20 30 40 50 Axial Power Imbalance, %

-- -- Allowable Trip Setpoint Envelope - - - .-Operating Umit Envelope ---- Actual Tnp Setpoint Envelope II

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 12 of 22 QUADRANT POWER TILT LIMITS FOR THERMAL POWER < 60%

For Operation from 0 EFPD to EOC-13 QUADRANI P POWER TILT STEADY-STATE TRANSIENT MAXIMI JM As Measured By: LIMIT(%) LIMIT(%) LIMIT(

Symmetrical Incore 7.50 10.03 20.0 Detector System Power Range Channels 4.94 6.96 20.0 Minimum Incore Detector 3.07 4.40 20.0 System Measurement System 8.58 11.07 20.0 Independent QUADRANT POWER TILT LIMITS FOR THERMAL POWER > 60%

For Operation from 0 EFPD to 300 + 10 EFPD QUADRAN' T POWER TILT STEADY-STATE TRANSIENT MAXIMi JM As Measured By: LIMIT(%) LIMIT(%) LIMIT(

Symmetrical Incore 4.34 10.03 20.0 Detector System Power Range Channels 1.96 6.96 20.0 Minimum Incore Detector 1.90 4.40 20.0 System Measurement System 4.92 11.07 20.0 Independent For Operation After 300 + 10 EFPD QUADRANT POWER TILT STEADY-STATE TRANSIENT MAXIMUM As Measured By: LIMIT(%) LIMIT(%) LIMIT(%)

Symmetrical Incore 4.16 10.03 20.0 Detector System Power Range Channels 1.96 6.96 20.0 Minimum Incore Detector 1.90 4.40 20.0 System Measurement System 4.92 11.07 20.0 Independent These limits are referred to by Technical Specification LCO 3.2.4 I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 13 of 22 Power Peaking Factors I These Limits are referred to by Technical Specification LCO 3.2.5 1 Heat Flux Hot Channel Factor FQ FQ shall be limited by the following relationships:

FQ < LHRaW`°W(Bu) / [LHR"P

• P] (for P < 1.0)

LHRaI°W0(Bu) = See the following table LHRWvg = 5.95 kW/ft for Mk-B1OZL fuel LHRaVZ = 5.95 kW/ft for Mk-B10I fuel LHRWVg = 5.95 kW/ft for Mk-B10E fuel P = ratio of THERMAL POWER / RATED THERMAL POWER Bu = fuel bumup (MWd/mtU)

CR-3 Cycle 13 Reload Bounding LHR Limits Batch 15 (Mark-B1OI / Mark-B10E) LHRaII°W Allowable Peak LHR for Specified Bumup Range, kW/ft 0-690 EFPD NAS 18690 -40305 Level MWd/mtU 1 15.1 2 15.4 3 15.9 4 16.1 5 16.4 6 16.2 7 15.6 8 15.4 I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 14 of 22 CR-3 Cycle 13 Reload Bounding LHR Limits Batch 14B (Mark-B1OE) LHR*"O Allowable Peak LHR for Specified Burnup Range, kW/ft NAS 0-526 EFPD 526-556 EFPD 556-600 EFPD 600-640 EFPD 640-690 EFPD Level 18690 - 35167 35167 - 36107 36107 - 37486 37486 - 38739 38739 - 40305 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1 15.1 15.1 14.7 14.4 14.0 2 15.4 15.3 14.9 14.6 14.1 3 15.9 15.8 15.4 15.0 14.5 4 16.1 16.0 15.5 15.1 14.6 5 16.4 16.0 15.6 15.1 14.6 6 16.2 15.9 15.4 15.0 14.5 7 15.6 15.4 15.0 14.6 14.1 8 15.4 15.1 14.7 14.4 14.0 CR-3 Cycle 13 Reload Bounding LHR Limits Batch 14 A,C,D,E (Mark-B1OI) LHRa"-w Allowable Peak LHR for Specified Burnup Range, kW/ft NAS 0-416 EFPD 416-475 EFPD 475-550 EFPD 550-625 EFPD 625-690 EFPD Level 18690 - 31722 31722 - 33570 33570 - 35920 35920 - 38269 38269 - 40305 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1 15.1 14.8 14.2 13.5 12.9 2 15.4 15.0 14.3 13.6 13.0 3 15.9 15.5 14.7 13.9 13.2 4 16.1 15.7 14.8 14.0 13.3 5 16.4 15.7 14.8 14.0 13.3 6 16.2 15.5 14.7 13.9 13.2 7 15.6 15.1 14.3 13.6 13.0 8 15.4 14.8 14.2 13.5 12.9 These tables are referred to by T.S. LCO 3.2.5 I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 15 of 22 CR-3 Cycle 13 Reload Bounding LHR Limits Batch 13A2,B,E2 (Mark-B1OI) & Batch 13C (Mark-B1OE) LHW'ao Allowable Peak LHR for Specified Burnup Range, kW/ft NAS 0-175 EFPD 175-375 EFPD 375-550 EFPD 550-625 EFPD 625-690 EFPD Level 18690 - 24172 24172 - 30437 30437 - 35920 35920 - 38269 38269 - 40305 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1 13.0 12.8 12.5 12.2 11.9 2 13.1 12.8 12.6 12.2 11.9 3 13.3 13.0 12.7 12.3 11.9 4 13.3 13.0 12.7 12.3 11.9 5 13.3 13.0 12.8 12.3 11.9 6 13.3 13.0 12.7 12.3 11.9 7 13.1 12.8 12.6 12.2 11.9 8 13.0 12.8 12.5 12.2 11.9 I

CR-3 Cycle 13 Reload Bounding LHR Limits Batch 12A3 (Mark-B1OZL) LHRaIIO' Allowable Peak LHR for Specified Burnup Range, kW/ft NAS 0-150 EFPD 150-350 EFPD 350-475 EFPD 475-575 EFPD 575-690 EFPD Level 18690 - 23389 23389 - 29654 29654 - 33570 33570 - 36703 36703 - 40305 MWd/mtU MWd/mtU MWd/mtU MWd/mtU MWd/mtU 1 14.3 14.0 13.3 12.7 12.0 2 14.4 14.2 13.4 12.8 12.0 3 14.8 14.5 13.7 12.9 12.1 4 14.9 14.6 13.7 13.0 12.1 5 15.0 14.6 13.7 13.0 12.1 6 14.8 14.5 13.7 12.9 12.1 7 14.4 14.2 13.4 12.8 12.0 8 14.3 14.0 13.3 12.7 12.0 These tables are referred to by Technical Specification LCO 3.2.5

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 16 of 22 POWER PEAKING FACTORS This Limit is referred to by Technical Specification LCO 3.2.5 Enthalpy Rise Hot Channel Factor F H FAH 5 ARP [1 + (1I/RH)(1- P/Pm)]

ARP = Allowable Radial Peak, See the following table P = ratio of THERMAL POWER / RATED THERMAL POWER and P

• 1.0 Pm = 1.0 for 4-RCP operation Pm = 0.75 for 3-RCP operation RH = 3.34 Cycle 13 Allowable Radial Peaks (ARP)

Axial Axi*al Location*

Pea k (X/L) zRP 1.1 0.2 1.8899 1.I 0.4 1.8829 1.1 0.6 1.8708 1.1 0.8 1.8497 1.3 0.2 1.9684 1.3 0.4 1.9470 1.3 0.6 1.9103 1.3 0.8 1.8090 1.5 0.2 2.0287 1.5 0.4 1.9406 1.5 0.6 1.8193 1.5 0.8 1.6994 1.7 0.2 1.9271 1.7 0.4 1.8230 1.7 0.6 1.7060 1.7 0.8 1.5997 1.9 0.2 1.7999 1.9 0.4 1.6962 1.9 0.6 1.5944 1.9 0.8 1.5013

• Based on an active core height of 140.6 inches. Linear interpolation is acceptable; extrapolation above 112.48 inches and below 28.12 inches is acceptable.

II

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 17 of 22 RCS Variable Low Pressure Setpoint Equation Prrp >-(11.59

• THOT - 5037.8) psig These limits are referred to by ITS Table 3.3.1-1, Item 5 I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 18 of 22 RCS DNB Pressure Limits RCS loop pressure > 2064 psig (Assumes 20% OTSG tube plugging and bounds either four or three RCPs operating).

FO1-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 19 of 22 RCS DNB Temperature Limit RCS Hot Leg Temperature < 604.6°F (Cycle 13 limit).

To accommodate up to 20% equivalent OTSG tube plugging, RCS Hot Leg Temperature shall be 5 605.8°F (ITS limit).

These limits are referred to by SR 3.4.1.2 I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 20 of 22 RCS DNB Flow Rate Limits For Cycle 13, RCS total flow rate > 139.7 E6 lb/hr with four RCPs operating, or > 104.4 E6 lb/hr with three RCPs operating.

To accommodate up to 20% equivalent OTSG tube plugging, RCS total flowrate shall be >

133.5 E6 lb/hr with four RCPs operating, or > 99.7 E6 lb/hr, with three RCPs operating (ITS limit).

I

F01-0002, Revision 1 Crystal River Unit 3 Attachment I Cycle 13 Core Operating Limits Report Page 21 of 22 Refueling Boron Concentration The boron concentration must be greater than 2879 ppmb.

The value includes 1 %Ak/k for uncertainties and is based on a 660 EFPD cycle 12. The refueling boron concentration must be increased by 2 ppm for each EFPD that the cycle 12 length is less than 660 EFPD, and 1.5 ppm/EFPD may be deducted for each EFPD that the cycle 12 length is more than 660 EFPD.

This limit is referred to by T.S. LCO 3.9.1 I

F01-0002, Revision 1 Crystal River Unit 3 Attachment 1 Cycle 13 Core Operating Limits Report Page 22 of 22 Revision History Revision 0 - September 2001; Original Cycle 13 COLR.

Revision 1 - August 2002; Incorporation of ITS Amendment 204 (LAR #263), "Relocation of Reactor Coolant System Parameters to the Core Operating Limits Report and 20% Steam Generator Tube Plugging."

Revision I adds the RCS Variable Low Pressure Setpoint Equation for use in Table 3.3.1-1, Item5, the RCS Pressure DNB Limits for use in SR 3.4.1.1, the RCS Temperature DNB Limits for use in SR 3.4.1.2, and the RCS Flow Rate DNB Limits for use in SR 3.4.1.3. The revision of BAW-2391, the Crystal River Unit 3 Cycle 13 Reload Report, referenced in Section 1.0 is also updated.

Revision 1 is produced under EGR-NGGC-0017 whereas Revision 0 was produced under NEP-213.

Revision 1 modifies the header and removes the footer.

I