ML20084E596
| ML20084E596 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/24/1995 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20084E507 | List: |
| References | |
| NUDOCS 9506010457 | |
| Download: ML20084E596 (20) | |
Text
.
CALVERT CLIFFS NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT for
~
UNIT 2, CYCLE 11 REVISION 1 l
9506010457 950524 PDR ADOCK 05000318 P
PDR Calvert Cliffs 2, Cycle 11 COLR Page 1 of 20 Rev.1
+,
CORE OPERATING LIMITS REPORT CALVERT CLIFFS UNIT 2, CYCLE 11 The following limits are included in this Core Operating Limits Report:
r
' Soecification Title Eags Introd u cti o n.............................................................................. m..... 3 2.2.1 Reactor Trip Setpoin ts....................................................................... 4 3.1.1.1 Shu td own M argin - Tavg > 2 00
- F...................................................... 4 3.1.1.2 Shu td own Margin - Tavg < 2 00 'F...................................................... 4 3.1.1.4 Moderator Temperature Coefficient.................................................... 4 3.1.3.1 C EA Po sitio n..................................................................................... 4 3.1.3.6 Regulating CEA Insertion Limits........................................................ 4 3.2.1 Lin e ar H e a t R a te.............................................................................. 4 3.2.2.1 Total Planar Radial Peaking Factor.................................................... 5 3.2.3 Total Integrated Radial Peaking Factor............................................... 5 3.2.5 D N B Param e te rs................................................................................ 5 i
3.9.1 B oro n Co n centration......................................................................... 5 i
List of Ap p rove d Me thod ologie s........................................................ 18 The following figures are included in this Core Operating Limits Report:
Number Title Page Figure 2.2-1 Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power.6 Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint - Part 1.................... 7 Figure 2.2-3 Thermal Margin / Low Pressure Trip Setpoint - Part 2.................... 8 Figure 3.1.1-1 Shutdown Margin vs. Time in Cycle............................................. 9 Figure 3.1.3-1 Allowable Time To Realign CEA vs.
Initial Total Integrated Radial Peaking Factor.............................10 Figure 3.1.3-2 CEA Oroup Insertion Limits vs. Fraction of Rated Thermal Power 11 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time In Cycle.....................12 Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits......................13 T
Figure 3.2.1-3 Total Planar Radial Peaking Factor /Fxy v3, Maximum Allowable Fraction of Rated Thermal Power................14 Figure 3.2.2-1 Total Planar Radial Peaking Factor vs.
Allowable Fraction of Rated Thermal Power................................15 Figure 3.2.3-1 Total Integrated Radial Peaking Factor vs.
Allowable Fraction of Rated Thermal Power................................16 Figure 3.2.3-2 DNB Axial Flux Offset Control Limits.........................................17 Calvert Cliffs 2, Cycle 11 COLR Page 2 of 20 Rev.O
INTRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 2, Cycle 11. It contains 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 i
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. If any of the limits contained in this report are exceeded, corrective action will be taken as defined in the Technical Specifications.
This report has been prepared in accordance with the requirements of Technical Specification 6.9.1.9. The cycle specific limits have been developed using the NRC-approved methodologies given in the " List of Approved Methodologies" section of this report and in Section 6.9.1.9 of the Technical Specifications.
Calvert Cliffs 2, Cycle 11 COLR Page 3 of 20 Rev.0
CYCLE SPECIFIC LIMITS FOR UNIT 2 CYCLE 11 2.2.1 Reactor Trip Setpoints The Axial Fitix Offset trip setpoint and allowable values are given in COLR Figure 2.2-1.
The Thermal 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 thn the larger of (1) 1875 psia or (2) the value calculated from COLR Figures 2.2-2 and 2.2-S.
3.1.1.1 Shutdown Margin - Tavg > 200 *F l
The shutdown margin shall be equal to or greater than the limit line of COLR Figure l
l 3.1.1 - 1.
"l 3.1.1.2 Shutdown Margin - Tavg s 200 'F 1
The shutdown margin shall be 2 3.0% delta K/K.
3.1.1.4 Moderator Temperature Coefficient j
1 The moderator temperature coefficient (MTC) shall be less negative than -2.7 x 10-4 delta K/K/*F at rated thermal power.
3.1.3.1 CEA Position 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 COLR 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 l
The axial shape index alarm setpoints are shown on COLR Figure 3.2.1-2.
T The maximum allowable fraction of rated thermal power vs. Fxy is shown in COLR Figure 3.2.1-3.
When usino the incore detector monitorine system ISR 4 2.1.4h
)
l The alann setpoints are set to protect the Linear Heat Rate limits shown on COLR Figure 3.2. I-1.
Calvert Cliffs 2. Cycle 11 COLR Page 4 of 20 Rev.O
l CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 11 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 j
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 The calculated value of FxyT shall be limited to s 1.64.
The allowable combination of thermal power and FxyT are shown on COLR Figure 3.2.2-1.
1 3.2.3 Total Integrated Radial Peaking Factor The calculated value of FrT shall be limited to 51.64.
The allowable combinations of thermal power and FrT are shown on COLR Figure 3.2.3-1.
The DNB axial flux controllimits 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 within 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 sufIicient to ensure that the boron concentration is > 2337 ppm.
Calvert Cliffs 2, Cycle 11 COLR Page 5 of 20 Rev.1
1.3 i
i
("M*ID 1.2 UNACCEPTABif UNACCEPTABLE OPERA 110N OPERATION 1.1 l1.0
(-e.is,im)
(o.2,tm) o n.
0.9 2e W
0.8 6
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i i
i i
-0.8 --0.6
-0.4 -0.2 0.0 0.2 0.4 0.6 0.8 PERIPHERALAX1Al.SHAPEINDEX,Yi f
Figure 2.2-1 Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power 1
Calvert Clifts 2. Cycle 11 COLR Page 6 of 20 Rev.O
1.6 i
j 1.5 y
= 2892x(A)x(QR )+17.16xT -10682 P
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=
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(+0 6,1.2) l 1.2
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-0.6 -0.5 -0.4 -0.3 -0.2 -0.1 0.0 0.1 0.2 0.3 0.4 0.5 0.6 ASI Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint - Part I (ASI vs. A )
1 i
Calvert Clifts 2. Cycle 11 COLR Page 7 of 20 Rev.0
i (1 41.2) 1.2
/
1.0 f
0.oJ.0) 0.9 j %.m) 08
/
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d 0'3 (88'80 Ph=2892xQg17.16xT. -10682 0.2 0.1 0.0 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 FRAC 110NOFRED1}ERM. POWER l
Figure 2.2-3 Thermal Margin / Low Pressure Trip Setpoint - Part 2 (Fraction of Rated Thermal Power vs QR )I L
i Calvert Clifts 2, Cycle 11 COLR Page 8 of 20 Rev.O
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l i
6 ACCEPUSE e
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M (EDC,4.5) d 54 My (800,3.5) 3 ISSAAdSMADOWMARGBl I
t#iACCEPIAIRE 2
opmWON M
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Figure 3.1.1-1 Shutdown Margin vs. Time in Cycle Calvert Cliffs 2, Cycle 11 COLR Page 9 of 20 Rev.O
A 70 (1.52,60) g n
T 50 972-600 F Z
R 3
d 40 U
Z O
30 E
h 20 W
Au0WEDREGON F
10 (1.62,0) 0 1.50 1.55 1.60 1.65 WDSURED PRE-WSAUGNED TOTM. WTEGRAE RADN.PEMONG FACTOR t
Figure 3.1.3-1 Allowable Time to Realign CEA Versus initial Total Integrated Radial Peaking Factor Calvert Clifts 2. Cycle 11 COLR Page 10 of 20 Rev.O
1.00 t aci5e 35%
l 0.90 e 0 x c>5035%
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0.75.005050%
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' c,p $ o $$g OperaMg Region Groupt 5
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0 20 40 60 80 100 0
20 40 60 80 100 0
20 40 60 80 100 1M 0 108 8 81 6 54 4 27.2 00 136.0 108 8 81 6 54 4 27 2 00 136 0 108.8 81.6 54.4 27.2 0.0 4
2 I
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20 40 60 80 100 0
20 40 60 80 100 1M O 108 8 81 6 54 4 27.2 00 1360 108 8 81 6 54 4 27 2 00
% CEAINSER110N INCH [$ CEA W11HORAWN Figure 3.1.3-2 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Calvert Cliffs 2, Cycle 11 COLR Page 11 of 20 Rev.O
4 k
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$2 l
1 +9 4~,
AOC FT M 0POU TION l
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13 BOC E00 TIMEINCYCLE Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle Calvert Cliffs 2, Cycle 11 COLR Page 12 of 20 Rev.O
1.1 i
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^kirig 1.0 UNA00EPNLE UNACCEPTABLE OPEE110N OPERA 110N 1
l0.9 REGION REDION o
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-0.2 0.0 0.2 0.4 0.6 PERRERALAXESHAPEBIDEX,Yl Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits Calvert Clifts 2. Cycle 11 COLR Page 13 of 20 Rev.0
i i
i i
i i
h (1.50,1.00) g 1.0 o
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E o.g 1
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5 0.8 3
(1.785,0.80)
E mmaruut 30.7 t
1 i
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.E 0.6 i
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0.5 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 Figure 3.2.1-3 T
Total Planar Radial Peaking Factor /Fxy vs.
Maximum Allowable Fraction of Rated Thermal Power I
(Surveillance 4.2.1.3) 1 Calvert CiliTs 2. Cycle 11 COLR Page 14 of 20 Rev.O
UMW) 1.0
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IMCCEPTRE l
OPERGON l
g M
[0 rhturcumE,
g.9 E
h0.8 UM ACCEPIRE g
OPDMON REGON 0.7 0.6 i
OS 1.60 1.65 1 70 1.75 rg Figure 3.2.2-1 Total Planar Radial Peaking Factor vs.
Allowable Fraction of Rated Thennal Power (ACTION 3.2.2.1.a.1)
Calvert Cliffs 2. Cycle 11 COLR Page 15 of 20 Rev.O
3 i
i U"4 1.0 IMCCEPIAN.E OPDMON M
GlMCUME 0.9 E
Dia.m) 0.8 8
OPDMON neamN I0.7 I0.6 0.5 1.60 1.65 1.70 1.75
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Figure 3.2.3-1 Total Integrated Radial Peaking Factor vs.
Allowable Fraction of Rated Thermal Power Calvert ClilTs 2. Cycle 11 COLR Page 16 of 20 Rev.0
e.
4 4
l 1.1 i
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^ #141 4 UN40CEPNLE UNCCEPIARE OPERMION OPERUl0N
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-0.2 0.0 0.2 0.4 0.6 PERRERM.AXN.SHAPEBEEX,Y Figure 3.2.3-2 DNB Axial Flux Offset Control Limits Calvert Clifts 2. Cycle 11 COLR Page 17 of 20 Rev.O
LIST OF APPROVED METIIODOLOGIES (1)
CENPD 199-P, Rev I-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 Uncertainties Methodology Part 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calvert 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 Uncertainties Methodology Part 2: Combination of System Parameter Uncertainties in1hermal Margin Analyses for Calven Cliffs Units I 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 IIcat Rate Limiting Conditions for Operation for Calvert Cliffs Units 1 and 2," March 1980 (Methodology for Specificadons 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 I 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. II. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24,1982, Unit 1 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 Uncertainties," 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 Specificadons 2.2.1,3.1.3.6,3.2.3,3.2.5)
(10)
CENPD-162-P-A, "Cridcal lleat Flux Correlation of C-E Fuel Assemblics with Standard Spacer Grids Part 1, Uniform Axial Power Distribution," April 1975 (Methodology for Specificai.ons 2.2.1, 3.1.3.6, 3.2.3, 3.2.5)
(11)
CENPD-207-P-A, " Critical IIcat Flux Correlation for C-E Fuel Assemblics with Standard Spacer Grids Part 2, Non-uniform Axial Power Distribution," December 1984 (Methodology for Speellications 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)
(13)
CENPD-225-P-A, " Fuel and Poison Rod Bowing," June 1983 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.3, 3.2.5 )
(14)
CENPD 266-P-A,"The ROCS and DITComputer Code for Nuclear Design," April 1983 (Methodology for Specifications 2.2.1, 3.1.3.6, 3.2.1, 3.2.2.1, 3.2.3, 3.2.5 )
1 Calvert Cliffs 2, Cycle 11 COLR Page 18 of 20 Rev.O
1
~
j (15)
CENPD-275-P A, "C-E Methodology for Core Designs Containing Gadolinia - Urania Burnable 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 Burnable Absorbers,"
August 1993 (Methodology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
(17)
CENPD-139-P-A, "C-E Fuci Evaluation Model Topical Report," July 1974 (Methodology for Specificadons 2.2.1, 3.1.3.6, 3.2.1, 3.2.2.1)
(18)
CEN-161-(B)-P-A, " Improvements to Fuel Evaluation Model," August 1989 (Methodology for Specifications 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)
(20)
Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4,1987, Docket Nos. 50-317 and 50-318, " Safety Evaluation of Topical Report CEN-161-(B) P, Supplement 1-P, Improvements to Fuel Evaluation Model" (Approval of CEN-161(B),
Supplement 1 P)
(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 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 Specificadons 3.2.1,3.2.2.1 and approval of Letter LD-81-095, dated December 15,1981)
(24)
CENPD-133, Supplement 5, "CEFLASil-4 A, a FORTRAN 77 Digital Computer Program for Reactor Blowdown Analysis," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1)
(25)
CENPD-134, Supplement 2, "COMPERC-II, A Program for Emcigency Refill-Reflood of the Core," June 1985 (Methodology for Specifications 3.2.1,3.2.2.1)
(26)
Letter from Mr. D. M. Crutchlicld (NRC) to Mr. A. E. Scherer (CE), dated 'uly 31,1986, " Safety Evaluation of Combustion Engineering ECCS Large Break Evaluation Model ara: Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133 Suppement 5 and CENPD-134, Supplement 2) s (27)
CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod licat Transfer Program," April 1977 (Metodology for Specifications 3.2.1,3.2.2.1)
(28)
Letter from Mr. R. L. Bact (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, "CEFLASil-4AS,"A Computer Program for the Reactor Illowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 (Methodology for Specifications 3.2.1,3.2.2.1)
Calvert Clifts 2, Cycle 11 COLR Page 19 of 20 Rev.0
(31)
Letter from Mr. K. Knell (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, Supplernent 2-P, "PARCII, A FORTRAN-IV Digital Program to Evaluate Pool Boiling Axial Rod and Coolant IIcatup," 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. II. 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, Fifth Cycle License Application (Section 7.1.2 contains Methodology for Specifications 3.1.1.2,3.9.1) l 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" 1
(38)
Letter from Mr. J. A. Tiernan (BG&E) to Mr. A. C. Thadani (NRC), dated October 1,1986, l
"Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2, Docket Nos. 50-317 and 50-318, Request l
for Amendment"(Methodology for Specification 3.1.3.1)
(39)
Letter from S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (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 Speci0 cation 3.1.3.1)
(40)
CENPD-188-A, "llERMITE: A Multi-Dimensional Space - Time Kinctics Code for PWR Transients," July 1976 (Methmlology for Specifications 2.2.1,3.1.3.6,3.2.1,3.2.2.1,3.2.3,3.2.5)
(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 Dctcctor 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,"B ASSS, 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) l (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" l
Calvert Cliffs 2, Cycle 11 COLR Page 20 of 20 Rev.O