ML19323G991

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Proposed Amend to Ol,Extending Licensed Coastdown Limit from 70% to 40% Reactor Power.Forwards Supporting Documentation
ML19323G991
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 06/06/1980
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML19323G986 List:
References
NUDOCS 8006090363
Download: ML19323G991 (18)
v • d • e


Text

.

DPR-29 Attachmcnt 1 4-to the shall be deemed to contain and in auNjcet fellowing ces-cie sten regulations 3.

This license the conditions specified in

70. Section M.3t. of rart 30 b

in lo CFR Chaptar 1: Part 50, co. Secclens So.5t. and 50.51 nf rart Section /.0.41 of :' ort 70; is subjecc to all epplicable and section 70.32 of rartand to the rules regulations and orders provisione af the Act and te subject to of the comission riow or hereaf ter in ef fect; the additional condition, specified or incorporated below; A.

gimm Pnver f. eve'.

Comonwraith rdtson is authorited to rperate Quu'.Citic9 of 2511 singswatts t v. c. c es s t! nit No 1 at power levela not (therral).

B, Technical _ Specifications _

The Technical Specifications centained in Aoper. dices A and II. as revised throu'Jh Amendment fioS't. are The alc"nsee hereby incorporate 1 in the license.

shall operate the facility in accordance with the Technical Specifications.

C. Restrictions Reactor power level shall be limited to maintain pressure margin to the safety valve set points during the worst case pressurization transient.

The magnitude of the power limitation, if any, and the point in the cycle at which it shall be applied is specified in the Reload fio. 4 licensing submittal for 'Juad Cities Unit flo.1 (flE00 24145).

Plant operation shall be limited to the operating plan described therein. Subsequent operation in l

the coastdown mode is permitted to 40% power.

D. Equattrar Va'.ve Restrtetton Arn. 25 The valves in the equalizer piping b-tween the recirculation 3/12/76 loops shall be closed at all tir.os during reactor cperation.

E. Se_curi t_y Plar>

The licensee shall maintain in effect and fully implement all provisions of the Commission-approved physical security plan.

Am. 51 including amendments and changes made pursuant to the authority t

2/23/79 of 10 CFR 50.54(p). The approved security plan consists of docunents withheld from public disclosure pursuant to 10 CFR 2.790(d), referred to as Quad Cities fiuclear Power Station Units tios. I and 2 Physical Security Plan dated as follows:

Plan - tbvember 18, 1977 Revision 1 - May 19,1978 Revision 2 - May 27, 1978 Revision 3 - July 28,1978 i

800609 07g

~

, s.

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QUAD CITIES 2 CYCLE 2A EXTENDED CYCLE OPEP.ATION NRC DOCKET NO 50 2G5 I.

INTRODUCTION Analyses have ueen completed in support of Guad Cities 2, EOC 2A, extended cycle operation.

The operating plan is shown in Figure 1.

The analyses have verified that application of previous operating limits to operation of the plant as shown in Figure 1 is conservative.

The rnalyses consist of the Turbine Trip Without Bypass, trip scram, for the all rods out condition at 903, 80", and 703 of rated power.

II.

DISCUSSION The Turbine Trip Without Bypass transient has been analyzed for three specific cases.

These three cases cover the reduced power operation as shown in Figure 1.

Each analysis was done at a specific power and exposure point.

The three points are as follows:

1) 905 power at 12,593 mid/t, 2) 80% power at 13,041 igd /t. and 3) 70", power at 13,514 mwd /t.

The exposure values are cor'e average values. The 80C 2A core average exposure was 9157 Rid /t.

The analysis covering the 1005 power operation and i

the first coastdown have previously been submitted and are not changed.

The primary cycle-dependent input parameters for the transient analyses are given in the attached figures and tables.

Figure 2 shows the scram reactivity curves, Table I gives the dynamic void coefficient of reactivity, and Table 2 gives the Doppler coefficient.

The transient analysis results are given in Tables 3 and 4, and Figures 3, 4 and 5.

The pressure margin results given in Table 3 compare to the previous E0C margin of 39 psi.

The required margin is 25 psi.

Thus, the pressure margin is larger for the three cases than for the original analysis resulting in a more conservative operating basis. The operating

. limit MCPR values for the three cases are aiven in Table 4.

The previously calculated, current value, MCPR's for the fuel are 1.29/1.35 (7x7/8x8).

Since these are minimum allowable operating values, any values calculated to be lower would be conservative.

Thus, operation with the current values for the new plan is conservative. The system transient responses for the three cases are shown in Figures 3, 4 and 5.

III.

CONCLUSION The planned operation is to ocerate the plant at 1003 power out to the "B" curve at an approximate core average exposure of 11,450 M.ld/t; locking the control rods in position at this exposure and coasting down in power to a power level of 90% of rated; then pulling control rods to

' maintain 90*; power until the all rods out condition is achieved at a calculated core average exposure of 12,593 t'Wd/t. and finally. a coastdown with all rods out to 705 power at a calculated core average exposure of 13.514IWd/t. All coastdowns are to be done at 100% of rated core flow. '

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NRC DOCKET NO 50 265 i

I QC-2 CYCLE 2A i

8 i

VOID COEFFICIEfli POWER CORE AVERAGE VOID COEFFICIErli USED Ill TPAtlS.

.'j LEVEL, %

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LEVEL, t EXPOSURE, tilD/T TEMPERATURE, F CALCULATED, d/ F AtlALYSIS, c/0F 0

'90 12,593 1090

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FLUX,%

PRESSURE, TO SV, LEVEL, %

PSIG PSI 90 260.5 104.0 1200 40 80 211.9 91.4 1173 67 70 178.0 79.0 1157 83 I

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_DRESDEl! 2 CYCLE 5 EXTEllDED CVCLE OPERATIO!!

/

I.

INTRODUCTION Analyses have been completed in support of Dresden 2. Cycle 5. ex+ ended cycle operation.

The operating plan is shown in Figure 1.

The analyses have veiifiTs'Hiat applicatien of previcus operating limits to operation of the plant as shown in Figure 1 is conservative. The analyses consist of the Turbine Trip Without Bypass, trip ; cram, for the all rods out condition at 90", 70%, 55%, and 403 of rated power.

II.

DISCUSSION The Turbine Trip Without Bypass transient has been analyzed for four specific cases.

These four cases cover the reduced power operation as shown in Figure 1.

Each analysis was done at a specific power and ex-posure poin.

The three points are as folicws:

1) 903 power at 4803 Kn'd/t, 2) 705 power at 5776 lL'd/t, 3) 555 power. at 6624 l"<!d/t, and 4) 40% power at 7481 M*.!d/t.

The exposure values are cycle increment values.

The analysis covering the 100'; power operation and the first coastdcwn i

have previously been. submitted and are not changed.

l The primary cycle-dependent inout carameters for the transient analyses are given in the attacned figures and tables.

Figure 2 she 3 the scram reactivity curves, Table 1 gives the dynamic void coefficient of react-g3 ivity, and Table 2 gives the Doppler coefficicat.

\\

The transient analysis results are given in Table 3 and Figures 3, 4, 5, and 6.

The pressure margin results given in Table 3 cnnpare to the previous EOC margin of 39 psi.

The reouired margin is 25 psi.

Thus, the pressure margin is larger for the four cases than the requir:d margin resulting in a conservative operating basis.

The previously calculated, current value, MCPR's for the fuel are 1.29/1.35 (7x7/8x8).

Since these are miniaum l

allowable operating values. any values calculated to be lower would be conservative.

The MCPR values for the icur cases have been evaluated and found to be less than or eoual to the current operating values.

Thus, operation with the current values for the new plan is conservative. The system transient responses for the three cases are shown in Figures 3, 4, 5 and 6.

III.

CONCLUSION j

The planned operation is to crerate the plant at 1005 power out to the "B" curve at an approxinate cycle exposure of 3750 M'.:d/t; locking the control rods in position at this exposure and coasting down in power to a power level of 905 of rated; then pulling control rods to maintain 901 power until the all rods out cmiition is acnieved at a calculated cycle l

exposure of 4S03 l".ld/t, and finally, a coastdown with all rods out to 40".

power at a calculated cycle excosure of 7aCl M.-ld/t.

All coastdowns are to be done at 1005 of rated core flew.

3

TABLE 1 VOID COEFFlC8ENT

/

f-VOID COEFFICIENT POWER CYCLE INCREMENTAL VOID COEFFICIENT USED IN TRANSIENT LEVEI., %

EXPOSURE, MWD /T _

CALCULATED, c/K ANALYSIS, c/%

90 4803

-5.938

-7.422 70 5776

-4.195

-5.243 55 6624

-3.060

-4.502

~

-3.491

'4 0 '

7481

-2.076

\\

I iABLE 2 C

DOPPLER COEFFICIEN 1 DOPPLER COEFFICIE

'OWER CYCLE INCREMENTAL AVERAGE FUEL DOPPLER COEFFICIENT USED IN TRANS,

EVEI,, %

EXPOSURE, MWD /T TEMPERATU RE,

  • F_

C ALCULATED, c/* F ANALYSIS, c/* F 90 4803 1053

-0.217

-0.206 70 5776 925

-0.261

-0.248 55 6624 836

-0.266

-0.253 40' 7481 751

-0.271

-0.256

  • /

L

/

/

TABLE 3 TRANSIENT ANALYSIS RESULTS LINE MARGIN NEUTRON POWER.

FLUX HEAT FLUX,

PRESSURE, TO SV, LEVEL, %

% OF INITIAI, a' OF INITDL PSIG PSI

~

90 261.8 104.1

'1204 36 7O 153.9 77.1 1161 79 99

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