ML20069F274

Rev 1 to Ccnpp COLR for Unit 1,Cycle 12

ML20069F274
Person / Time
Site:	Calvert Cliffs
Issue date:	06/01/1994
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20069F269	List: ML20069F266 ML20069F274 ML20069F278
References
NUDOCS 9406080188
Download: ML20069F274 (21)

Text

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l CALVERT CLIFFS NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT ,

for ,

UNIT 1, CYCLE 12 REVISION 1 ,

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i 9406080188 940601 PDR ADDCK 05000317 P PDR Calvert Cliffs 1, Cycle 12 COLR Page 1 of 21 Rev.1 i

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g 1 CORE OPERATING LBIITS REPORT i CALVERT CLIFFS UNIT 1, CYCLE 12 The following limits are included in this Core Operating Limits Report:

Specification Iith Page Introductio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.2.1 Reactor Trip Setpoints . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.1.1.1 Shutdown Margin - Tavg > 200 F . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ~. . . . . . . . . . . . 4 3.1.1.2 Shutdown Margin - Tavg .<;. 200 F . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.1.1.4 Moderator Temperature Coefficient . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.1.3.1 C EA Position . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 3.1.3.6 Regulating CEA Insertion Limits ..... ......... ........... ................. ... 4 3.2.1 Linear Heat Rate . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........ 4 3.2.2.1 Total Planar Radial Peaking Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3.2.3 Total Integrated Radial Peaking Factor . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3.2.5 D NB Parame ters . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3.9.1 Bo ro n Conce ntra tio n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 List of Approved Methodologies. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 The following figures are included in this Core Operating Limits Report:

Number Title Pace 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 - Pan 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 Group 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 Corpol Limits ... .. .... ...... ....13 Figure 3.2.1-3 Total Planar Radial Peaking Factor /Fxy vs.

Maximum Allowable Frac iot, 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 Pealing Factor vs. ,

Allowable Fraction o f Ra r.ed Thermal Power . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Figure 3. 2.3-2 D NB Axial Flux Offset Control Limits . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 Calvert Cliffs 1, Cycle 12 COLR Page 2 of 21 Rev.1

F INTRODUCTION I

This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 1, Cycle 12.

It contains the limits for:

Reactor Trip detpoints Shutdown Margin 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 L In addition, this report contains a number of figures which give limits on the parameten; 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.

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't Calvert Cliffs 1. Cycle 12 COLR Page 3 of 21 Rev.1- i

CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 12 ,

2.2.1 Reactor Trip Setpoints De Axial Flu,x Offset trip serpoint and a!!owable 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. He allowable values are to be not less than the larger of (1) 1875 psia or (2) the value calculated from COLR i 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 The shutdown margin shall be 2,3.0% delta K/K.

3.1.1.4 Moderator Temperature Coefficient 4

The moderator temperature coefficient (MTC) shall be less negative than -2.7 x 10 delta K/ld#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 3.2.12.

When using the excore detector monitorine system (SR 4.2.1.3h The axial shape index alarm setpoints are shown on COLR Figure 3.2.1-2.

T He maximum allowable fraction of rated thermal power vs. Fxy s shown in COLR Figure 3.2.1-3. ,

When usine the incore detector monitorine system (SR 4.2.1.4h ne alarm setpoints are set to protect the Linear Heat Rate limits shown on COLR Figure 3.2.1 1.

Calvert Cliffs 1. Cycle 12 COLR Page 4 of 21 Rev.1

, , , . - - - .. ., -- .- +- -

4 CYCLE SPECIFIC LIMITS FOR UNIT 1, CYCLE 12 The uncertainty factors for the incore detector monitoring system are: ,

1. A measurement-calculational uncertainty factor of 1.062,

2. An engineering uncenainty factor of 1.03,

3. A linear heat rate uncenainty factor of 1.002 due to axial fuel densification a'nd thermal  !

expansion. and  ;

4. A thermal power measurement uncenainty factor of 1.02.

3.2.2.1 Total Planar Radial Peaking Factor ,

T The calculated value of Fxy shall be limited to i 1.66 T

The allowable combination of thermal power and Fxy are shown on COLR Figure 3.2.2-1. l 3.2.3 Total Integrated Radial Peaking Factor ,

T The calculated value of Fr shall be limited to i 1.66.

T The allowable combinations of thermal power and Fr are shown on COLR Figure 3.2.3-1.

The DNB axial flux controllimits are show'n on COLR Figure 3.2.3-2.

t 3.2.5 DNB Parameters i

i The axial shape index, thermal power shall be maintained within the limits established by the Better Axial Shape Selection System (BASSS) for CEA insenions of the lead bank of < 55 % when BASSS is operable, or within the limits of COLR Figure 3.2.3-2 for CEA insenions specified by COLR Figure l 3.1.3-2. j 3.9.1 Boron Concentration r

The refueling boron concentration shall be maintained uniform and sufficient to ensure that the boron concentration is 12370 ppm. t i

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Calvert Cliffs 1. Cycle 12 COLR Page 5 of 21 Rev.1 1

r

• /

1.3 i i i i i i i (0.0,1.n) -

1.2 -

UNACCEPTABLE UNACCEPTABLE OPERATION OPERADON REGION REGION _

g ,) _

E 1.0 - (-0.18,1.00) (0.2,1.00) -

3 o

0 '

_; 0.9 -

2 x

W 0.8 - -

i 3

0 0.7 -

KCWABW _

g OPERATION REGION o 0.6 - .,

z o '

5 0.5 -

l

$ (0.6,0.40) >

( (-0,6,0.40) 0.4 -

)

0.3 -

r 0.2 -

i i i o i 0.15

-0.8 -0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 PERIPHERALAXIALSHAPEINDEX,Y l

Figure 2.2-1 Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power l Calvert Cliffs 1, Cycle 12 COLR- Page 6 of 21 Rev.1 l

1.6 1.5 gp P

VAR

= 2892 x (A) x (OR)) + 17.16 n xT. -10682

'(-0.6,1.4) 1'4

\ Q DNB

=A)x0R) h A) = +).5xA31 + 0.

30 A

7 \ N (+0,6,1.2)

(-0.2,1.2)h \\ [

, \ , /

/

).5xA3l+1. l0

\ \/'(+0.4,1,1)

A) = -

(+0.2, I.0) 0.9

-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 ,

i 1

Figure 2.2-2 Thermal Margin / Low Pressure Trip Setpoint - Part 1 (ASI vs. A3 ) _

Calvert Cliffs 1. Cycle 12 COLR Page 7 of 21 Rev.1

f L

l 1

l (1.2.1.2) 1.2 .

1.1 1.0 f

- # (1.0,1.0) 0.9 -

0.8

)PTok 185) 7 j . .

0.7 ,

Q R) 0.6 -

/

0.5

/ -

0.4

/- 0 DNB

= Aj x0R; -

/

/ and 10.0,0) P - 10682

= 2892 x Q DNk* in 0.2 1

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 ,

FRACT10N OFRATEDTHERMALPOWER Figure 2.2-3 Thermal Margin / Low Pressure Trip Setpoint - Part 2 i (Fraction of Rated Thermal Power vs. QRi )

l l

l Calvert Cliffs 1, Cycle 12 COLR Page 8 of 21 Rev.1-  !

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3 6

ACCEPTABLE OPERATION 5 -

. ON (E00,4.5) m 8

x >

$4 -

a N

y (B00,3.5) c 3 -

WIN 1WUM SHUTDOWN WARGN g

o - IJNACCEPTABLE OPERATION

@2 g REGON m

1 0

BOC OC TlWEINCYCLE i

Figure 3.1.1-1 Shutdown Margin vs. Time in Cycle Calvert Cliffs 1, Cycle 12 COLR Page 9 of 21 Rev.1

70 . . . . . . . . . . . . .. .

(1.57,60) _

60 E -

W 50 -

3 1002-600 F Z R 3 40 -

6 ,

0 z

30 -

o i

h20 - .

O F

y 10 -

ALLOWED REGION F

0 -

(1.67,0) 1.55 1.60 1.65 1.70 MEASURED PRE-MISAUGNED TOTAL INTEGRATED RADML PEAKING FACTOR ,

. i Figure 3.1.3-1 ]

Allowable Time to Realign CEA Versus l Initial Total Integrated Radial Peaking Factor i l

Calvert Cliffs 1, Cycle 12 COLR Page 10 of 21 Rev.1 l l

1.co.c,ss a 1.00 3 1

0.90  ! e uo,oissa lA 5

3 0.80 l (

2 ,

es,wusu 0.70 ,0. ap5su

{ l f " l 6 __

l l l 0.50 ,

E  ;

oJa.op4sm u i l 3 i e i

0.50 l l l

, I r

s 0 .@

.\

l3 ;l \g i

u. ltangTem satim O ISteadyShis SisodyRats z 0.30 m '

L o lure s u

{ 0.20 jQrp58252 Grp41 208

' o.20,co 3 8 u g  ;

I 0.10 -

• \

l l

' ' om,opsea 0.00 s m aAsss orpsesst op=*s

• me 5 3 1 e e so too o 20 e a e too o 20 e e ao too i

a 2a 12 toBJ BtJ 54.4 DJ 04 IM ioM 81J 54.4 U.2 M 138.0 1DEJ 81J 54.4 U.2 a.o j 4 2 i l

i o 2a e e m 100 o 20 e so ao too 13La loBJ 81J R4 U.2 04 138.D 108J 81J S4.4 27.2 DJ f 3EANSER110N INCHSEAMiHDRAWN Figure 3.1.3-2  ;

CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Calvert Cliffs 1, Cycle 12 COLR Page 11 of 21 Rev.1 )

.I

n e

16 t

k

• 2O '

3 '

f8

S 15

$+

UNA:CEPTABLEOPEMT10N z$

2 014.5 8a Q. W ACCEPTABLE 0PERA110N b14 .

1 13 T1 MEIN CYCLE l

e Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. Time in Cycle

{

Calvert Cliffs 1, Cycle 12 COLR Page 12 of 21 Rev.I

1 1.1 i i i i i i

~

1.0 -

(-o.08.1m) ^ (0 n,1m) -

UNACCEPTABLE UNACCEPTABLE 0.9 -

OPERADON OPERABON g -

w REGION REGION 3

o -

c. 0.8 -

s -

@ 0.7 -

(-o.s.o.x) ( )(0.3Ax) 3 w . -

d 0.6 -

ACCEPTABLE g

OPERATION o -

0.5 -

) REGION d (-o.s.o.50) tu o -

z 0.4 - -

o P

O -

g 0.3 -

tu 0.2 -

C

(-o.45A15) 0.1 0.05 t i t ' i

-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 PERPHERALAXlALSHAPEWDEX,Yl l I

I Figure 3.2.1-2 Linear Heat Rate Axial Flux Offset Control Limits ,

i i

Calvert Cliffs 1, Cycle 12 COLR Page 13 of 21 Rev.1

i i i i i i i ,

u I (1.50,1.00) -

g 1.nv o

E.

( 0.9 2

e 3

~

8 0.8 -

(1.785,0.80) a 8

ACCENABLEVAll)E 30.7 -

t '

E 3

.E 0.6 a

2 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 (Surveillance 4.2.1.3)

Calvert Cliffs 1. Cycle 12 COLR Page 14 of 21 Rev.1

)

/ . 1 I

)

4 (1.58,1.00) 1.0 j UNACCEPTABE i

CPERAVON '

5 REGON Fh UWITCURVE l0.9 q

2 l A O

(13' 2) l 0.3 gg l 8 OPERABCN REGON l

0.7 -

0.6 -

0.5 1.55 1.70 1.75 1.50 l

Figure 3.2.2-1 Total Planar Radial Pealcing Factor vs.

Allowable Fraction of Rated Thermal Power (ACTION 3.2.2.1.a.1) i Calvert Clifs 1. Cycle 12 COLR Page 15 of 21 Rev.1

F a

4 i ..

(1.ss,1.0) -

1.0 UNACCEPTABLE g CPERADON REGION o

j 0.9 - FJ UWTCURVE -

5 is . .

8 3 0.8 ACCEPTABLE (174 M) -

o CPERABCN REGION f

8 g 0.7 -

u.

d i

j 0.6 -

l 0.5 l 1.55 1.70 1.75 1.50 l F[

1 l

' j

\

Figure 3.2.3-1 Total Integrated Radial Peaking Factor vs.

Allowable Fraction of Rated Thermal Power Calvert C:iffs 1, Cyc!e 12 COLR Page 16 of 21 Rev.I

1 1.1 i i , i i E

1.0 - (-01.12) * (015.1 8) -

UNACCEPTABLE UNACCEPTABLE 0.9 -

OPERATION OPERATION d REGION REGION g ACCEPTABl.E 0.8 -

(-0A0.a0) ( OPERATION )(OAuo) -

g

, REGION 2 -

~

3 0.7 -

l -

E 0.6 -

R

!2 C-W8) )

0.5 -

u.

o 0,4 - .

5 8 -

su. 0.3 -

0.2 -

c (-0 e,0.15) 0.1 0.05 t t i f f

-0.6 -0.4 -0.2 0.0 0.2 0.4 0.5 PERIPHERALAX'ALSHAPEINDEX,Y; Figure 3.2.3-2 DNB Axial Flux Offset Control Limits 1

Calvert Cliffs 1. Cycle 12 COLR Page 17 of 21 Rev.1

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LIST OF APPROVED METHODOLOGIES l (1) CENPD-199-P, Rev 1-P-A, "C-E Setpoint Methodology: C-E Local Power Density and DNB LSSS and LCO Serpoint 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 Uncenainties Methodology Pan 1: C-E Calculated Local Power Density and Thermal Margin / Low Pressure LSSS for Calven 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 Uncertainties 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 1 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 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 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 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)

(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 DIT Computer Code for Nuclear Design," April 1983 (Methodology for Specifications 2.2.1, 3.I.3.6, 3.2.1, 3.2.2.1, 3.2.3, 3.2.5) 1 Calvert Cliffs 1, Cycle 12 COLR Page 18 of 21 Rev.1

4 (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,P4, " 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 Fuel Evaluation Model Topical Report," July 1974 (Methodology for Specifications 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)

(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 W 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, Supplement 5. "CEFLASH-4A, 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 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 Cornbustion Engineering ECCS Large Break Evaluation Model and Acceptance for Referencing of Related Licensing Topical Reports (Approval of CENPD-133, Supplement 5 and CENPD-134, Supplement 2)

(27) CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer '

Program," April 1977 (Methodology for Specifications 3.2.1,3.2.2.1)

(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" J (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) f 4

Calvert Cliffs 1 Cycle 12 COLR Page 19 of 21 Rev.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 >fr.' 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, Fifth 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 Unic Nos.1 & 2, Docket Nos. 50-317 and 50-318, Request for Amendment" (Methodology for Specifications 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 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, 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 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)

Calvert Cliffs 1, Cycle 12 COLR Page 20 of 21 Rev.1

(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' 1

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