ML20249A406
| ML20249A406 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/12/1998 |
| From: | Kattic M BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20249A400 | List: |
| References | |
| NUDOCS 9806160407 | |
| Download: ML20249A406 (22) | |
Text
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CALVERT CLIFFS NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT l
for UNIT 1, CYCLE 14 REVISION 0
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+ M8 RESPONSIBLE ENGINEER / DATE TYli A.I Q 4/9/9s
' INDEPENDENT REVIEWER / DATE l 2. 4 p,. f h%
PRINCIPAL ENGINEER-NEU / DATE f
9906160407 990611 l
PDR ADOCK 05000317; i
P PDR Calvert Cliffs 1, Cycle i4 COLR Page 1 of 22 Rev.O t
L CORE OPERATING LIMITS REPORT-CALVERT CLIFFS UNIT 1, CYCLE 14 l
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The following limits are included in this Core Operating Limits Report:
Specification Iitig pagg introd uction.........................................
................................4 2.2.1 Reactor Trip Setpoints............ - --
..............................5 3.1.1.1 Shutdown Margin - Tavg > 200 'F...................................................................... 5 3.1.1.2 -
Shutdown Margin - Tavg s 200 *F............................................................... 5
.3.1.1.4 Moderator Temperature Coefficient.............................................................. 5 3.1.3.1
' C EA Pos it ion..........................................................................
..........5 3.1.3.6 Regulating CEA Insenion Limits..................................................................... 5 3.2.1 Linear Heat Rate........................................................................................ 5 3.2.2.1 Total Planar Radial Peaking Factor..................................................................... 6 3.2.3 -
Total Integrated Radial Peaking Factor........................................................... 6 3.2.5 DN B Parame ters............................................................................................. 6 3.9.1 Boron Concentration.......................................................................................... 6 List of Approved Methodologies................................................................. 19 i
~ The following figures are included in this Core Operating Limits Report:
- Number Titic Eage Figute 2.2.1 '
Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power......................
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Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint - Pan 1............................................ 8 l-Figure 2.2 Ther M Margin /1 ny Pressure Trip Setpoint - Part 2.......................................... 9 Figure 3.1.1-1_ Shu'mwn Margiri lis. Time in Cycle.............................................................. 10
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Figure 3.1.3-1 Allowable Time To Realign CEA Versus
. Initial Total Integrated Radial Peaking Factor............
......................................... I 1
. Figure 3.1.3-2 CEA Group insertion Limits vs. Fraction of Rated Thermal Power.......................12 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle.........................................13 Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits...........................................14 L
Figure 3.2.1 Total Planar Radial Peaking Factor /Fxy vs.
T Maximum Allowable Fraction of Rated Thermal Power.......................................15 Figure 3.2.2-1 Total Planar Radial Peaking Factor vs. Allowable Fraction of Rated Therm al Powe r............................................................................................. I 6 Figure 3.2.3-1' Total Integrated Radial Peaking Factor vs.
E Allowable Fraction of Rated Thermal Power................................................. I 7 Figure 3.2.3-2. DNB Axial Flux Offset Control Limits.............................................................. I 8 r
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i Calvert Cliffs 1, Cycle 14 COLRi Page 2 of 22 Rev.O 4
l UNIT 1 CORE OPERATING LIMITS REPORT
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Calvert Cliffs 1, Cycle 14 COLR Page 3 of 22 Rev.0
INTRODUCTION This report prcvides the cycle-specific limits for operation of Calvert Cliffs Unit 1, Cycle 14. It contams the limits for:
Reactor Trip Setpoints Shutdown Margm Moderator Temperature Coefficient CEA Position
. Regulating CEA Insertion Limits Linear Heat Rate Total Planar Radial Peaking Factor Total Integrated Radial Peaking Factor DNB Parameters -
Refueling Boron Concentration In addition, this report contains a number of figures which give limits on the parameters listed above H any of the limits contained in this report are exceeded, corrective action will be taken as defbed in the Technical Specifications.
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This report has been prepared in accordance with the requirements of Technical Specifications.
The cycle specific limits have been developed using the NRC-approved methodologies given in the " List of Approved Methodologies" section of this report and m the Technical Specifications.
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Calvert Cliffs 1, Cycle 14 COLR Page 4 of 22 Rev.0
G CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 14 I
2.2.1 Reactor Trip Setpoints The Axial Flux Offset trip setpoint and allowable values are given in COLR Figure 2.2-1.
l The Thennal Margin / Low Pressure trip setpoint is given in COLR Figures 2.2-2 and 2.2-3.
The allowable values'are to be not less than the larger of(l) 1875 psia or (2) the value calculated from COLR Figures 2.2-2 and 2.2-3.
3.1.1.1 Shutdown Margin -Tavg > 200 'F The shutdown margin shall be equal to or greater than the limit line of COLR Figure 3.1.1-1.
3.1.1.2 Shutdown Margin -Tavg < 200 *F l
The shutdown margin shall be 2 3.0% op.
3.1.1.4 Moderator Temperature Coefficient (Not Applicable in Modes 5 and 6) 3.1.3.1 CEA Position l
The allowable time to realign a CEA versus the initial total integrated radial peaking factor is given in COLR Figure 3.1.3-1.
3.1.3.6 Regulating CEA Insertion Limits The regulating CEA groups insertion limits are shown on COI.R Figure 3.1.3 2.
3.2.1 Linear Heat Rate The linear heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1.
The axial shape index power dependent control limits are given in COLR Figure 3.2.1-2.
When using the excore detector monitoring system (SR 4.2.1.3h The axial shape index alarm setpoints are shown on COLR Figure 3.2.12.
The maximum allowable fraction of rated thermal power vs. Fxy' is shown in COLR Figure 3.2.1-3.
When using the incore detector monitoring system (SR 4.2.1.4h The alarm setpoints are set to protect the Linear Heat Rate limits shown on COLR Figure I
3.2.1-1.
Calvert Cliffs 1, Cycle 14 COLR Page 5 of 22 Rev.0
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l CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 14 The uncertainty factors for the incore detector monitoring system are:
1.
A measurement-calculational uncertainty factor of 1.062, 2.
An engineering uncertainty factor of 1.03, 3.
A linear heat rate uncertainty factor of 1.002 due to axial fuel densification and thermal expansion, and 4.a For measured thermal power less than or equal to 50 percent but greater than 20 percent of rated full core power a thermal power measurement uncertainty factor of 1.035.
4.b For measured thermal power greater than 50 percent of rated full core power a thermal power measurement uncertainty factor of 1.020.
3.2.2.1 Total Planar Radial Peaking Factor (Not Applicable in Modes 5 and 6)
The allowable combination of thermal power and Fxy' are shown on COLR Figure 3.2.2-1.
3.2.3 TotalIntegrated Radial Peaking Factor (Not Applicable in Modes 5 and 6)
T The allowable combinations of thermal power and Fr are shown on COLR Figure 3.2.3-1.
The DNB axial flux control limits are shown on COLR Figure 3.2.3-2.
3.2.5 DNB Parameters The axial shape index, thermal power shall be maintained within the limits established by the Better Axial Shape Selection System (BASSS) for CEA insertions of the lead bank of < 55%
when BASSS is operable, or viithin the limits of COLR Figure 3.2.3-2 for CEA insertions specified by COLR Figure 3.1.3-2.
3.9.1 Boron Concentration
- The refueling boron concentration shall be maintained uniform and sufficient to ensure that the boron concentration is.>_2308 ppm. This refueling boron concentration credits 44
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control element assemblies and the boron concentration at 19.8 a/o B'.
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Calvert Cliffs 1, Cycle 14 COLR Page 6 of 22 Rev.0
(Not Applicable in Modes 5 and 6)
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l Figure 2.2-1 Perip.heral Axial Shape Index vs. Fraction of Rated Thermal Power Calvert. Clifts 1, Cycle 14 COLR Page 7 of 22 Rev.0
- -______-__=-.
- - - - - - - ~ - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - ---
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i (Not Applicable in Modes 5 and 6) l
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Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint - Part 1 (ASI vs. A )
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Calvert Cliffs 1, Cycle 14 COLR Page 8 of 22 Rev.0
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(Not Applicable in Modes 5 and 6) l l
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Figure 2.2-3 l
Thermal Margin / Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs. QR )
1 Calvert Clifts 1, Cycle 14 COLR Page 9 of 22 Rev.0
(Not Applicable in Modes 5 and 6)
Figure 3.1.1-1 Shutdown Margin vs. Time in Cycle Calvert Cliffs 1, Cycle 14 COLR Page 10 of 22 Rev.0
1 (Not Applicable in Modes 5 and 6)
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Figure 3.1.3-1
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Allowable Time to Realign CEA Versus initial Totalintegrated Rad al Peaking Factor l
Calvert Cliffs 1, Cycle 14 COLR Page 11 of 22 Rev.0
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(Not Applicable in Modes 5 and 6) 1 l
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Figure 3.1.3-2 CE4 Group Insertion Limits vs. Fraction of Rated Thermal Power i.
Calvert Cliffs I, Cycle 14 COLR Page 12 of 22 Rev.O w_
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l (Not Applicable in Modes 5 and 6) l l
l Figure 3.2.1-1
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Allowable Peak Linear Heat Rate vs. Time in Cycle l
4 Calvert Cliffs 1, Cycle 14 COLR Page 13 of 22 Rev.O l
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(Not Applicable in Modes 5 and 6)
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Figure 3.2.1-2 r
Linear Heat Rate Axial Flux Offset Control Limits l
Calvert Cliffs I, Cycle 14 COLR Page 14 of 22 Rev.0 l
(Not Applicable in Modes 5 and 6) i l
I Figure 3.2.1-3 T
Total Planar Radial Peaking Factor /Fxy vs.
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Maximum Allowable Fraction of Rated Thermal Power (Surveillance 4.2.1.3) 1-Calvert Cliffs 1, Cycle 14 COLR Page 15 of 22 Rev.O i
(Not Applicable in Modes 5 and 6) l l
Figure 3.2.2-1 Total Planar Radial Peaking Factor vs.
Allowable Fraction of Rated Thermal Power (ACTION 3.2.2.1.a.1)
Calvert Cliffs 1, Cycle 14 COLR Page 16 of 22 Rev.0
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4 (Not Applicable in Modes 5 and 6) l I
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i-Figure 3.2.3-1 Totai integrated Radial Peaking Factor vs.
Allowable Fraction of Rated Thermal Power Calvert Cliffs 1, Cycle 14 COLR.
Page 17 of 22 Rev.O
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(Not Applicabic in Modes 5 and 6) 1 l
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1 Figure 3.2.3-2 DNB Axial Flux Offset Control Limits Calvert Cliffs 1. Cycle 14 COLR Page 18 of 22 Rev.0
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LIST OF APPROVED METHODOLOGIES (1)
CENPD-199-P, Rev l-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Setpoint Methodology for Analog Protection Systems," January 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
(2)
CEN-124(B)-P, " Statistical Combination of Uncedainties Methodology Pan 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calved Cliffs Units I and II,"
December 1979 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.2.1,3.2.3)
- (3)
CEN-124(B)-P, " Statistical Combination of Uncenainties Methodology Part 2: Combination of System Parameter Uncedainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2,"
January 1980 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
(4)
CEN-124(B)-P, " Statistical Combination of Uncertainties Methodology Part 3: C-E Calculated Departure from Nucleate Boiling and Linear Heat Rate Limiting Conditions for Operation for Calvert Cliffs Units I and 2," March 1980 (Methodology for Specifications 3.1.3.6,3.2.1, 3.2.2.1, 3.2.3, 3.2.5)
(5)
CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units 1 and 2," December 1981 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
(6)
Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24,1982, Unit I Cycle 6 License Approval (Amendment No. 71 to DPR-53 and SER)[ Approval to CEN-124(B)-P (three parts) and CEN-191(B)-P)]
(7)
CEN-348(B)-P, " Extended Statistical Combination of Ur. certainties," January 1987 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
(8)_
Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated October 21,1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-348(B)-P, Extended Statistical Combination of Uncertainties" (9)
CENPD-161-P-A, " TORC Code, A Computer Code for Determining the Thermal Margin of a Reactor Core," April 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
(10)
CENPD-162-P-A, " Critical Heat Flux Correlation of C-E Fuel Assemblies with Standard Spacer Grids Part 1. Uniform Axial Power Distribution," April 1975 (Methodology for Specifications i
2.2.1, 3.1.3.6, 3.2.3, 3.2.5)
~(11)
CENPD-207-P-A, " Critical Heat Flux Correlation for C-E Fuel Assemblies with Standard Spacer Grids Part 2, Non-uniform Axial Power Distribution," December 1984 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
(12) - CENPD-206-P-A, " TORC Code, Verification and Simplified Modeling Methods," June 1981 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.3,3.2.5)
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(13)-
CENPD-225-P-A, " Fuel and Poison Rod Bowing," June 1983 (Methodology for Specifications 2.2.1,3.1.3.6,3.23,3.2.5) r Calven Cliffs 1 Cycle 14 COLR Page 19 of 22 Rev.0
__.-._____.-__m_______.-----_--.---
(14). CENPD-266-P-A, "The ROCS and DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specificatica 2.2.1,3.* 3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
- (15)' CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable l
Absorbers," May 1988 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
~ (16)
CENPD-382-P-A, " Methodology for Core Designs Containing Erbium Bumable Absorbers," August 1993 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2d 3.2.3, 3.2.5) l (17)
CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 1974 l
- (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)
(18)
CEN-161-(B)-P-A, "I rovements to Fuel Evaluation Model," August 1989
' (Methodology for SpeInfications 2.2.1,3.1.3.6,3.2.1,3.2.2.1)
(19)
CEN-161-(B)-P, Supplement 1-P, " Improvements to Fuel Evaluation Model," April 1986 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1) l.
(20)
Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tieman (BG&E), dated February 4, l
1987, Docket Nos. 50-317 and 50-318,'" Safety Evaluation ofTopical Report CEN-161-
. (B)-P, Supplement 1-P, Improvements to Fuel Evaluation Model" (Approval of CEN-161(B), Supplement 1-P) t (21)
CEN-372-P-A, " Fuel Rod Maximum Allowable Gas Pressure," May 1990 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1) l (22). Letter from Mr. A. E. Scherer (CE) to Mr. J. R. Miller (NRC) dated December 15,1981, LD-81-095, Enclosure 1-P, "C-E ECCS Evaluation Model Flow Blockage Analysis" (Methodology for Specifications 3.2.1,3.2.2.1)
(23)
CENPD-132, Supplement 3-P-A, " Calculative Methods for the C-E Large Break LOCA Evaluation Model for the Analysis of C-E and E Designed NSSS," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1 and approval of Letter LD-81-095, dated December 15,1981)
(24)
CENPD-133, Sup )lement 5, "CEFLASH-4A, a FORTRAN 77 Digital Computer Program for Reactor Blowc.own Analysis," June 1985 (Methodology for Specifications 3.2.1, 3.2.2.1)
'(25)' CENPD-134, Supplen ent 2, "COMPERC-II, A Program for Emergency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1)
(26)- Letter from Mr. D. M. Crutchfield (NRC) to Mr. A. E. Scherer (CE), dated July 31,1986,
" Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model and Acceptance fcr Rewrencing of Related Licensmg Topical Reports (Approval of CENPD- -
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133, Supplement 5 and CENPD-134, Supplement 2)
(27)
CENPD-135, Supplemer$ 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1977 (Methodology for Specifications 3.2.1,3.2.2.1) l l~
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L-P (28) - Letter from Mr. R. L. Baer (NRC) to Mr. A. E. Scherer (CE) dated September 6,1978,
" Evaluation of Topical Report CENPD-135, Supplement 5" (29)
CENPD-137, Supplement 1-P, " Calculative Methods for the C-E Small Break LOCA Evaluation Model," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
(30) CENPD-133, Supplement 3-P, "CEFLASH-4AS, "A Computer Program for the Reactor Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
(31)
Letter from Mr. K. Kniel (NRC) to Mr. A. E. Scherer (CE), dated September 27,1977,
" Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P" (32)
CENPD-138, Supplement 2-P, " PARCH, A FORTRAN-IV Digital Program to Evaluate Pool Boiling, Axial Rod and Coolant Heatup," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
-(33)' Letter from Mr. C. Aniel (NRC) to Mr. A. E. Scherer (CE), April 10,1978. " Evaluation of Topical Report CENPD-138, Supplement 2-P"
~ (34)
Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. J. R. Miller (NRC), dated February 22,1985, "Calvert Cliffs Nuclear Power Plant Unit 1, Docket No. 50-317.- Amendment to Operating License DPR-53, Eighth Cycle License Application" (Section 7.3.2 contains Methodology for Specifications 3.1.1.1 and 3.1.1.4 and 3.1.3.6)
(35)
Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated May 20, 1985, Safety Evaluation Report Approving Unit 1 Cycle 8 License Application (36)
Letter from Mr. A. E. Lundvall, Jr. (BG&E) to Mr. R. A. Clark (NRC), dated September 22,1980, " Amendment to Operating License No. 50-317, Fife Cycle License Application (Section 7.1.2 contains Methodology for Specifications 3.1.1.2,3.9.1)
(37)
Letter from Mr. R. A. Clark (NRC) to Mr. A. E. Lundvall, Jr (BG&E), dated December 12,1980, " Safety Evaluation Report Approving Unit 1, Cycle 5 License Application" (38)
Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1, 1986, "Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docket Nos. 50-317 and 50-318, Request for Amendment" (Methodology for Specifications 3.1.3.1) i i
(39) ' Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tieman (BG&E), dated July 7,1987, Docket Nos. 50-317 and 50-318, Approval of Amendments 127 (Unit 1) and 109 (Unit 2)
. (Support for Specification 3.1.3.1)
(40)
CENPD-188-A, "HERMITE: A Multi-Dimensional Space - Time Kinetics Code for PWR Transients," July 1976 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1, l
3.2.2.1, 3.2.3, 3.2.5)
Calvert Cliffs I, Cycle 14 COLR Page 21 of 22 Rev.0
e e s k (41)
The Full Core Power Distribution Monitoring System referenced in Specifications 3.1.3.1,3.2.2.1,3.2.3, and the BASES is described in the following documents:
(a)
CENPD-153-P, Revision 1-P-A, " Evaluation of Uncertainty in the Nuclear Power Peaking Measured by the Self-Powered, Fixed Incore Detector System," May 1980 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
(b)
CEN-119(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit I and Unit 2," November 1979 (Referenced in Appendix B of Unit 2 Cycle 9 License Application)
(c).
Letter from Mr. G. C. Creel (BG&E) to NRC Document Control Desk, dated February 7,1989, "Calvert Cliffs Nuclear Power Plant Unit No. 2; Docket No. 50-318. Request for Amendment, Unit 2 Ninth Cycle License Application" (Appendix B contains Methodologies for Specifications 3.1.3.1,3.2.2.1,3.2.3, 3.2.5)
(d)
Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. G. C. Creel (BG&E), dated January 10,1990, " Safety Evaluation Report Approving Unit 2 Cycle 9 License Application" (42)
Letter from Mr. D. G. Mcdonald, Jr. (NRC) to Mr. R. E. Denton (BGE), dated May 11, 1995," Approval to Use Convolution Technique in Main Steam Line Break Analysis -
Calvert Chffs Nuclear Power Plant, Unit Nos. I and 2 (TAC Nos. M90897 and M90898) f Calvert Cliffs 1, Cycle 14 COLR Page 22 of 22 Rev.O