ML20069F278

Rev 1 to Ccnpp COLR for Unit 2,Cycle 10

ML20069F278
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 9406080189
Download: ML20069F278 (21)

Text

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CALVERT CLIFFS NUCLEAR POWER PLANT CORE OPERATING LIMITS REPORT for UNIT 2, CYCLE 10 REVISION 1 1

DR D 05 0 17 P PDR Calvert Clifts 2, Cycle 10 COLR l' age 1 of 21 Rev.1

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1 CORE OPERATING LIMITS REPORT l CALVERT CLIITS UNIT 2, CYCLE 10 The following limits are included in this Core Operating Limits Report:

Specification Title Pace Introduction . . .. . . . .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 5 200 F. . ... . .4 3.1.1.4 Moderator Temperature Coefficient . ... . .. . . ..4 3.1.3.1 CEA Position . . .. .. ... . . . . .. . .....4 3.1.3.6 Regulating CEA Insertion Limits .. . . .. .. . . . . .4 3.2.1 Linear lieat Rate . . .. . . . . . . ...4 3.2.2.1 Total Planar Radial Peaking Factor. . ..5 3.2.3 Total Integrated Radial Peaking Factor . . . . . . .. 5 3.2.5 DNB Parameters .. . . . . .. . . . .. . . .5 3.9.1 Boron Concentration.. . . . .. .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 Thennal 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 Group lasertion Limits vs. Fraction of Rated Thermal Power . . 11 Figure 3.2.1-1 Allowable Peak Linear lieat Rate vs. Time In Cycle. . . . .. 12 Figure 3.2.1-2 Linear lleat Rate Axial Flux Offset Corgrol Limits . 13 Figure 3.2.1-3 Total Planar Radial Peaking Factor /Fxy vs.

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 10 COLR Page 2 of 21 Rev.1 l

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IN'IRODUCTION This report provides the cycle-specific limits for operation of Calvert Cliffs Unit 2. Cycle 10. -

It contains the limits for:

Reactor Trip Setpoints .

Shutdown Margin Moderator Temperature Coefficient CEA Position Regulating CEA Insertion Limits Linear IIcat Rate Total Planar Radial Peaking Factor  :

Total Integrated Radial Peaking Factor i DNB Parameters Refueling Baron 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. .

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Calvert Cliffs 2, Cycle 10 COLR Page 3 of 21 Rev.1 ,

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CYCLE SPECIFIC LIh1ITS FOR UNIT 2, CYCLE 10  !

2.2.1 Reactor Trip Setpoints ,

The Axial Flux Jffset trip setpoint and allowable values are given in COLR Figure 2.2-1.

I The Thermal '.iargin/lmw Pressure trip setpoint is given in COLR Figures 2.2-2 and 2.2-3. The allowable va'ues are to be not less than the larger of (1) 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 ,

Tice 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.;> 3.0% delta K/K.

3.1.1.4 Moderator Temperature Coefficient 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 1.1.3-2.

3.2.1 Linear IIcat 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 usine the excore detector monitorine system (SR 4.2.1.3):

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 usine the incore detector monitorine system (SR 4.2.1.4):

The alarm setpoints are set to protect the Linear Heat Rate limits shown on COLR Figure 3.2.1-1.

Calvert Cliffs 2, Cycle 10 COLR Page 4 of 21 Rev.1

CYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 10 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 thermal power measurement uncertainty factor of 1.02.

3.2.2.1 Total Planar Radial Peaking Factor T

The calculated value of Fxy shall be limited to ,< l.59.

T The allowable combination of thermal po ver and Fxy are shown on COLR Figure 3.2.2-1.

3.2.3 Total Integrated Radial Peaking Factor T

The calculated value of Fr shall be limited to .<., 1.59.

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 insenions of the lead bank of < 55% when BASSS is operable, or within the limits of COLR Figure 3.2.3-2 for CEA IIisertions 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 .;> 2300 ppm.

Calvert Cliffs 2, Cycle 10 COLR Page 5 of 21 Rev.I

1.3 i , , , , , , -

o (0.0,1.17) 1.2 -

UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION REGION REGION g , ,

5 1.0 -

(-0.18.1.00) (0.2,1.00) - i 3

O i

n. ,

0.9 - -

1 e

to 0.8 - -

i N

Pu -

ACCEPTABLE _  !

{0'7 OPERATION REGION O 0.6 - -

z O  !

5 0.5 - -  ;

O.4 -

( (-0.6,0.40) (0.6,0.40) > -

0.3 - -

0.2 -

O.15 i i i i i

-0.8 -0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 0.8 '

PERIPHERAL AXIALSHAPEINDEX,Yi t

Figure 2.2-1  ;

Peripheral Axial Shape Index vs. Fraction of Rated Thermal Power Calvert Cliffs 2, Cycle 10 COLR Page 6 of 21 Rev.1

\ :

t i

l 1.6 1.5 TRIP P = 2892 x(Ay x(0R3 ) + 17.16 xT in -10682

' (-0.ti,1.4) VAR 1'4

\ 0 DNB

= Aj x 0R i

1.3 A=+

j ].5xASl + 0. 30 A) j \ N (+0.6,1.2)

(-0..2,1.2) h \\ [

> \ . / '

/ \ \['(+0.4,1.1)  ;

1.0 A, = - ).5xAsi + 1. !0

/

(+0.2, 1.0) 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 L

Figure 2.2-2 .

Thermal Margin / Low Pressure Trip Setpoint - Part 1 -

(ASI vs. A1 )

i Calvert Cliffs 2, Cycle 10 COLR Page 7 of 21 Rev.1

• ' i

'4 (1.2.1.2) <

1.2 1.1

/

1.0 / '

, / (1.0,1.0) 0.9 jf[85) 0.8  ;

/

0.7 /

QR 1

06 <

/

0.5 '

i 0'4

/ Q = A x 0R 3 $ __

/ DNB and TR1P l

'(0.0.0.:')

P AR= 2892 x 0DNg17.16xT in - 0682 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 FRACTION OFRATEDTHERMALPOWER i

Figure 2.2-3 ,

Thermal Margin /l>>w Pressure Trip Setpoint - Part 2 I' (Fraction of Rated Thermal Power vs QRj )

Calvert Cliffs 2, Cycle 10 COLR Page 8 of 21 Rev.1 ,

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6  !

b ACCEPTABLE  ?

(E00,5.0)

OPERATION 5 -

REGION  ;

o I

a:

54 -

d O

N y (B00,3.5) a3 -

MINIMUMSHUTDOWN MARGIN  :

1 o 2 - UNACCEPTABLE OPERADON g REGION z

m  :

- i 1

!e 0 l

+

B00 E00 BWEINCYCII F

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Figure 3.1.1-1 Shutdown Margin vs. Time in Cycle  !

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Calvert Cliffs 2, Cycle 10 COLR Page 9 of 21 Rev.1

t i

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

60 (1.57,60) _

8w I

50 - - t b 1002-600 F T

z R 3 40 - -

6 0 '

z 30 - -

O t

"~i h20 - -

O F-j y 10 -

ALLOWED REGION t

F 0 -

(1.67,0) t t i i f i f I i f f f t i 1.55 1.60 1.65 1.70 MEASURED PRE-MISALIGNED TOTAL INTEGRATED RADIAL PEAKING FACTOR Figure 3.1.3-1 Allowable Time to Realign CEA Versus Initial Total Integrated Radial Peaking Factor Calvert Cliffs 2, Cycle 10 COLR Page 10 of 21 Rev.I

L 1.00 -

1.m aise m -

l 0.90 5  ! e\(o.so.9,ssa l

l 3 0.80 .

o i

n. l on.op! esu opsels

{ 0.70 l  ;,

L 5

g 0.60 l

l l

l K595'" ,

g 0 m op' ea l

@ 0.50 l ,

a t i o

{ 0.40 i\

l3 l

\g ,

b llangTerm Shutfrm ,

o insadymate needyitsis t z 0.30 lertion ._ ;:. ..

o lumit i twt

@ jor,som orp4s a 0.20

, ,o.m op3eim i  ;

0.10 l

l 0.00 " o. map 3eis maaidenss j g,,ses or ==tlas

• ome 5 3 1 ,

o a e so ao too 0 10 40 so so too o 20 e is so too 138.0 10BJ B1A 54.4 DJ D.0 138.D 10LB B1.8 54.4 DJ 0.0 13ED 108A 81A 54.4 U.2 0.0 4 2 0 2D 40 10 80 100 0 2D 40 80 00 100 130.0 10BJ 81.5 54.4 U.2 0.0 135.0 108.8 81.8 54.4 D.2 0.0

%CEANSElm0N NCHESCEAWmiDRAW Figure 3.1.3-2 CEA Group Insertion Limits vs. Fraction of Rated Thermal Power Calvert Cliffs 2, Cycle 10 COLR Page 11 of 21 Rev.I

~ ~~

~

k k$'

W3 gw ,

UNA:CEPTABLEOPERATION  :

b015.2 ACCEPTABLE 0PERATION I + 15 EO 65 zo

]+

Y.J 6W d

gv 14 m

Io d

l3 B0C E00 i TIMEIN CYCLE f

Figure 3.2.1-1 Allowable Peak Linear IIeat Rate vs. Time in Cycle Calvert Cliffs 2, Cycle 10 COLR Page 12 of 21 Rev.I

1.1 i i i i i 1.0 -

(-08.12) ^ ^(01118) -

UNACCEPTABLE UNACCEPTABLE g 0.9 -

OPERATION OPERATION -

I w REGION REGION 3

S 0.8 - -

.J 2

$ 0.7 -

(-o.s.o.70) ( )(o.s o.70) h W

d 0.6 - -

ACCEPTABLE g

o OPERATION

-j 0.5 -

(-o.3,o.so) ) REGION b.

O z 0.4 - -

o b - -

g0.3 0.2 - -

( (-0.45,0.15) 0.1 0.05 i i ' ' '

-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 PERIPHERALAXIALSHAPEINDEX,Yl l

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

caivert clirrs 2. cycle 10 cotn Page 13 or 21 nev. i

k i i i i i i i io 1.0 (1.50,1.00) o.

I)

E 5 0.9 - -

E '

o x

o 8 0.8 - -

2 (1.785,0.80)

U E

I ACCEPTABl.EVALUE i 0.7 - -

o

t E

3

.E 0.6 a  !

2 1 i

0.5 l 1.45 1.50 1.55 1.60 1.65 1.70 1.75 1.80 Fh 1 I

l 1

l Figure 3.2.1-3 Total Planar Radial Peaking Factor /FxyT y3, )

Maximum Allowable Fraction of Rated Thermal Power .,

(Surveillance 4.2.1.3) l Calvert Cliffs 2, Cycle 10 COLR Page 14 of 21 Rev.I

.  : l l

1 1.0

(* I l UNACCEPTABLE OPERATION REGION 0.9 _ h mcm 1 5

0.8 -

ACCEPTABLE I*' #) '

8 OPERATION REGON I0.7 -

1 l0.6 -

t 1

0.5 1.55 1.60 1.65 1.70 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 2, Cycle 10 COLR Page 15 of 21 Rev.I

,. 7 i

I i 1 4 1.0

(* } -

UNACCEPTABLE OPERATION REGION o.

l 0.9

- GmCm _ ;

i 0.8 - (W, #) -

g ACCEPTABLE o OPERATION g REGION ,

l0.7 3

l - -

l0.6 0.5 1.55 1.60 1.65 1.70 i

Figure 3.2.3-1 Total Integrated Radial Peaking Factor vs. i Allowable Fraction of Rated Thermal Power l

l Calvert Cliffs 2, Cycle 10 COLR Page 16 of 21 Rev.I

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o 1.1 i i i i i t i

1.0 -

(-0.1.1.2) (0.15.1.2) -

UNACCEPTABLE UNACCEPTABLE 0.9 -

OPERATION OPERATION -

REGION REGION d ,

g ACCEPTABLE z 0.8 -

(-0.3.0.80) ( OPERATION )(0.3,0.ao) -

y REGION 2

tg 0.7 - -

h  :

0.6 - -

2- 0.5 -

(-0.3.0.m) ) -

u.

o 0.4 - - l 5

5 g 0.3 - -

0.2 - - -

( (-0.45,0.15) 0.1 0.05 ' ' ' ' '

-0.6 -0.4 -0.2 0.0 0.2 0.4 0.6 ,

PERIPHERALAXIALSHAPEINDEX,Yi Figure 3.2.3-2 DNB Axial Flux Offset Control Limits l

l Calvert Cliffs 2, Cycle 10 COLR Page 17 of 21 Rev.1 l

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i LIST OF APPROVED METHODOLOGIES (1) CENPD-199-P, Rev l-P-A, "C-E Setpoint Methodology: C-E L.ocal 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 in Thermal Margin Analyses for Calvert 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 lleat 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.11. 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 lleat 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, "Criticallleat 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 2.2.1,3.1.3.6,3.2.1,32.2.1,3.2.3,3.2.5) 1 Calvert Cliffs 2, Cycle 10 COLR Page 18 of 21 Rev.I

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J (15) CENPD-275-P-A, "C-E Methodology for Core Designs Containing Gadolinia - Urama i 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) l 1

(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 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, "CEFLASil-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) :o Mr. A. E. Scherer (CE), dated July 31,1986,

" Safety Evaluation of Combustion 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-ll, A Cylindrical Geometry Fuel Rod IIeat 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" (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)

Calvert Cliffs 2, Cycle 10 COLR Page 19 of 21 Rev.I

~~ . - - . _ - -__ - - - . - - - __ -_ - .

I.A Y

o.  :

1 (30) CENPD-133, Supplement 3-P, "CEFLASil-4AS, "A Computer Program for the Reactor ,

Blowdown Analysis of the Small Break Loss of Coolant Accident," January 1977 (Methodology l for Specifications 3.2.1,3.2.2.1)

(31) Letter from Mr. K. Kneil (NRC) to Mr. A. E. Scherer (CE), dated September 27,1977,

" Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement I-P" ,

(32) CENPD-138, Supplement 2-P, "PARCil, A FORTRAN-IV Digital Program to Evaluate Pool '

Boiling, Axial Rod and Coolant Ileatup " 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" l (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)

(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)

(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, "IIERMITE: 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) i (b) CEN-119(B)-P, "BASSS, Use of the Incore Detector System to Monitor the DNB-LCO on Calvert Cliffs Unit 1 and Unit 2," November 1979 (Referenced in Appendix B of ,

Unit 2 Cycle 9 License Application) ,

Calvert Cliffs 2, Cycle 10 COLR Page 20 of 21 Rev.I 1

o. 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 1 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" I

I Calvert Cliffs 2, Cycle 10 COLR Page 21 of 21 Rev.1 l

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