ML20006D352

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Core Operating Limits Rept,Dresden Station,Unit 3,Cycle 12,Rev 0.
ML20006D352
Person / Time
Site: Dresden  Constellation icon.png
Issue date: 12/31/1989
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML17202G775 List:
References
NUDOCS 9002130062
Download: ML20006D352 (21)


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Core Operating Limits Report .

Dresden Station Unit 3 Cycle 12 4

Revision 0 .

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.: .4 b g ti Issuance of Changes Sumary Affected Affected .

Section Paaes Sumary of Chana'es Date All

  • All Oriainal Issue 12/89 a,

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Dresden Unit 3 i December 1989

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Table of Contents Page Re f e r e n c e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i i i L i s t o f , F i g u re s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i v List of Tables................................................ v-L 1.0 Control Rod Withdrawal Block Instrumentation- (3/4.2.C).. 1-1 1.1 Technical Specification Reference... 1-1 -!

1.2 Description........................................ ............... 1-1  :

2.0 Average Planar Linear Heat Generation Rate (3/4.5.I).... 2-1 .

2.1 Technical Specification Reference......... 2-1 2.2 Description.............-........................... ..... ... 2-1 i

2.3 MAPLHGR Multipliers............................ ... 2-1 3.0 Local Steady State LHGR- (3/4.5.J) . . . . . . . . . . . . . .'. . . . . . . . '

. 3-1 3.1 Technical Specification Reference....... 3-1 +

3.2 Description......................................... ........... 3-l' 4,0 Local - Transient LHGR (3/4. 5.K) . . . . . . . . . . . . . . . . . . . . . . . . . . 4-1 4.1 Technical Speci fication Reference. . . . . . . . . . 4-1 4.2 Description........................................ ........ 4-1 5.0 Minimum. Critical Power Ratio Operating Limit (3/4.5.L).. 5-1 5.1 Technical Speci fication Reference. . . . . . . . . . . . . . . . 5-1 5.2 De s c r i p t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..

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p i -Dresden Unit 3 11 December 1989 1

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References 1

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1. Commonwealth Edison Company Docket No. 50-237, Dresden Nuclear Power Station, Unit 3, facility Operating License DPR-25. j
2. Letter from D. M.'Crutchfield to All Power Reactor Licensees and Applicants, Generic Letter 88-16;. Concerning the Removal of Cycle-Specific Parameter Limits from Technical Specifications.

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f Dresden Unit 3 iii December 1989

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4 List of Figures Fiaure Title /Descriotion Pace ,

2.2-1 MAPLHGR Limit versus Bundle Average Exposure - 2-2

  • ANF 8x8 Fuel 2.2-2 MAplHGR Limit versus Bundle Average Exposure - 2-3

'ANF 9x9 Fuel 3.2-1 Steady State Linear Heat Generation Rate 3-2 (SLHGR) Limit vs. Planar Exposure 4 ~. 2- 1 Transient Linear Heat Generation Rate (TLHGR) 4-2 Limit vs. Planar Exposure for ANF'8x8 Fuel 4.2-2 Transient Linear Heat Generation Rate (TLHGR) 4-3 Limit vs. Planar Exposure for ANF 9x9 Fuel  !

5.2-1 MCPR Limit vs Measured Scram Time to 90% 5-2 'i insertion - Rated Flow Conditions 5.2-2 MCPR Operating Limit for Manual Flow Control 5-3 .

5.2-3 MCPR Operating Limit for Automatic Flow Control 5-4 ,

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j -' *,. ' s List of Tables "D

Table- Title /Descriotion-- Pace

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1,2-1 Control Rod Withdrawal Block Instrumentation 1  ;

Setpoints= '

2,3-1 MAPLHGR Multipliers 2-4 l h

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Dresden Unit'3 v . December 1989 l.

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1.0 CONTROL- ROD WITHDRAWAL BLOCK INSTRUMENTATION 1.- l Technical Soecification Reference

,. Technical Specification 3.2.C - Control Rod Block Actuation l.2 -Descriotion The Rod Block Monitor Upscale Instrumentation Setpcints' are determined from the relationships shown in -Table 1.2-1.

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l Dresden Unit 3 1-1 December 1989

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Table 1.2-1 [

' Control Rod Withdrawal Block Instrumentation Setpoints -

Trio Function- Trio level Settina Rod Block Monitor Upscale '

(Flow Bias)'

Dual loop Operation Less than or equal to (0.65 Wd plus 45)

(See Note) ,

Single Loop Operation Less than or equal to ,

(0.65 Wd plus 41)

(See Note)

Note: -Wd - percent of drive flow required to produce a rated core flow of 98 Mlb/hr.

c Dresden Unit 3 1-2 December 1989 l-l'

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2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 2,1 'lechnical Soecification References Section 2.2: Technical Specification 3.5.1 -Average Planar LHGR Section 2.3: See Table 2.3-1 2.2- Descriotion.

The Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) versus Bundle Average Exposure for ANF 8x8 fuel is determined from.

Figure 2.2-1.

The Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) versus Bundle Average Exposure for ANF 9x9 fuel is determined from .,

Figure 2.2-2.

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2.3 MAPLHGR Multioliers The appropriate multiplicative factors to apply to the base MAPLHGR limits specified in Section 2.2 are shown in Table'2.3-1.

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Dresden Unit 3 2-1 December 1989

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  • Figure 2.2-1 MAPLHGR Limit vs. Bundle Average Exposure ANF 8x8 Fuel 1

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0 5 10 15 20 . 25 ~ 30 5 40 BedieW Exposwa(GWd@) '

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The above graph 'is based on the following MAPLHGR summary for ANF 8x8 fuel design.

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Bundle' Average MAPLHGR Exoosure (GWd/MTU) Limit. Kw/ft 0 13.00 10 13.00 L 15 13.00 18 12.85 l

20 12.60 25 11.95 I

30 11.20 1

35 10.45 l 1

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Figure 2.2-2 MAPLHGR Limit vs. Bundle Average Exposure '

ANF 9x9 Fuel .

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6 5 10- 15 20 ' 25 30 35.- 40 Bade % Egers(Q) .t i

The.above graph is based on the following MAPLHGR summary for ANF 9x9 fuel design.

l- Bundle Average. MAPLHGR

. Exoosure (GWD/MTU) Limit. Kw/ft l 'O 11.40-t 5 11.75 10 11.40 15 10.55 20 9.70 25 8.85 30 8.00 35 7.15 40 6.30 Dresden Unit 3 2-3 December 1989

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l~ .,a Table 2.3 '

MAPLHGR Multipliers Soecification Multiolicative Factors Title of TS Scenario' 8x8 9x9 ,

3.5.D.2 Automatic Pressure One Relief 0.89 0.76 Relief Subsystems Valve Out of f

-Service. t 3.5.1 and Average-Planar LHGR Single Loop 0.91 0.91 3.6.H.3.f Recirc Pump Flow- Operation Limitations 3.5.1 and Average Planar LHGR Single Loop 0.89 0.76 3.6.H.3.f Recire Pump Flow Operation and Limitations One Relief Valve Out of-Service. "

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l Dresden Unit 3 2-4 December 1989

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3.0 LOCAL STEADY STATE LHGR 3.1 Technical Snecification Reference I Technical Specification.3.5;J - Local. Steady State LHGR l

3.2' Descriotion l The Local Steady State LHGR (SLHGR) limit versus Average Planar- <

Exposure for all resident fuel is determined from Figure 3.2-1. . j

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Steady State linear Heat Generation Rate (SLHGR)' Limit vs. Planar Exposure j

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ANF 8x8 Fuel ANF 9x9 Fuel-Exoosure LHGR Exoosure LHGR-0.0 16.0 0.0 14.5 25.4 14.1 5.0 14.5 42.0- 9.3 25.2 10.8 48.0 7.2 Dresden Unit 3 3-2 December 1989

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4.0~ LOCAL' TRANSIENT lig i

' 4.1 Technical Soecification Reference q a

Technical- Specification 3.i.K - Local Transient LHGR  ;

4.2l Descriotion. -

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The Local Transient-LHGR (TLHGR). limit versus= Average Planar Exposure  !

for ANF 8x8 fuel is determined from Figure 4.2-l' .

J The TLHGR limit versus Average Planar Exposure for ANF 9x9 fuel is determined-from Figure 4.2-2.

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Dresden Unit 3 4-1 December 1989

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Transient Linear Heat Generation Rate (TLHGR) Limit  !

vs. Planar Exposure for ANF 8x8 Fuel  ;

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Dresden Unit 3 4-2 December 1989

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Figure 4.2-2 Transient Linear Heat Generation Rate (TLHGR) Limit j vs. Planar Exposure for ANF 9x9 Fuel  !

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1 5 10 15 20. 25 30 . 35 - @ d M.

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5 Exoosure LHGR ,

0.0 19.2 25.4 16.9  !

43.2 10.8 48.0 10.0 i

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5.0 MINIMUM CRITICAL POWER RATIO OPERATING LIMIT f

5.1 Technical Soncification References  !

Technical Specification 3.5.L - Minimum Critical Power Ratio (MCPR)  ;

5.2 Descriotion

a. The MCPR Operating Limit at rated flow versus measured scram time i is shown in Figure 5.2-1. The MCPR Operating Limit is 1.34 or i greater whenever the measured 90% insertion time is 2.65 seconds '

or less. i

b. During Manual Flow Control, the MCPR Operating Limit at reduced  !

flow rates can be determined from: '

i. Figure 5.2-2 using the appropriate flow rate, or it. The rated flow MCPR Operating Limit determined via Figure 5.2-1, whichever is greater, i
c. During Automatic Flow Control, the MCPR Operating Limit at I reduced flow rates can be determined from Figure 5.2-3 using the appropriate flow rate and rated flow MCPR Operating Limit, which  !

is obtained.from Figure 5.2-1. Linear interpolation between the  !

curvas on Figure 5.2-3 is permissible.

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Dresden Unit 3 5-1 December 1989 l

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r Figure 5.2-1 MCPR Limit vs. Measured Scram Time to 90% Insertion '

Rated Flow Conditions j r

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f 1.30C 2.70 2.2 2.90 3.2 3.10 3.8 3.5 3.40 3.50 Womwed Scre Tas to 90t Inertion (senends) - ,

The above graph demonstrates the following dependence of the MCPR Operating Limit versus measured scram time to 90% insertion for all resident fuel types: -

MCPR LCO = 1.34 + (Tave - 2.65; *0.083 where Tave is the average insertion time to the 90% insertion point for all control rods in the core.

Dresden Unit 3 5-2 December 1989

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Figure 5.2-2

MCPR Operating Limit for Manual Flow Control 13 -

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2- 8: R. 8. 8. q, m enspunsaam The above curve is based on the following MCPR operating limit summary l l for Manual Flow Control and all fuel types:

Total Core Flott (X Rated) MCPR Onoratina limit 100 1.10 90 1.15 80 1.21 70 1.28 60 1.36 50 1.46 40 1.57

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Oresden Unit 3 5-3 December 1989 l

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i. Figure 5.2-3 MCPR Operating Limit for Automatic Flow Control

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Internspannime) l The above curve is based on the following MCPR operating limit sumary for Automatic Flow Control and all fuel types: '

Total Core Flow MCPR Operating Limit *

(% Rated) 1.34 1.39 1.43 100 1.34 1.39 1,43 90 1.38 1.43 1.47 80 1.41 1,46 1.50 70 1.45 1,51 1.55 60 1.51 1.57 1.61 50 1.53 1.64 1.68 40 1.72 1.78 1.84

  • Column Headers are MCPR operating limits at rated flow. >

Dresden Unit 3 5-4 December 1989 i

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