ML17202G776

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Core Operating Limits Rept,Dresden Station Unit 2,Cycle 12,Rev 0.
ML17202G776
Person / Time
Site: Dresden Constellation icon.png
Issue date: 12/31/1989
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML17202G775 List:
References
NUDOCS 9002130057
Download: ML17202G776 (43)
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Text

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  • Core Operating Limits Report Dresden Station Unit 2 Cycle 12 Revision O December 1989
  • /
  • Affected Section Affected Paaes Issuance of Changes Su111T1ary Su111T1arv of Channes Date All -

All Oriainal Issue 12/89

  • Dresden Unit 2 December 1989

{

I Table of Contents Page References ........................**.......... ~ . . . . . . . . . . . . . . . i ; i List of Figures ............................................... iv List of Tables ................................................ v 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 (3/4.5.1) ..... 2-1 2.1 Technical Specification Reference ................... 2-1 2.2 Description ........................................ : 2-1 2.3 MAPLHGR Multipliers ................................. 2-1 3.0 .Local Steady State LHGR (3/4.S.J) ........................ 3-1 3.1 Technical Specification Reference ................... 3-1 3.2 Description ......................................... 3-1

  • 4.0 Local Transient LHGR (3/4.5.K) ........................... 4-1 4.1 4.2 Technical Specification Reference ................... 4-1 Description ......................................... 4-1 5.0 Minimum Critical Power Ratio Operating Limit (3/4.5.L) ... 5-1 5il Technical Sµ~Llrl~d~lu~ ReferencA ... ,, .............. 5-1
  • 5.2 *Description ......................................... 5-1 Dresden Unit 2 ii December 1989
  • 1.

References Co111110nwealth Edison Company Docket No. 50-249, Dresden Nuclear Power Station, Unit 2, Facility Operating License DPR-19.

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 .
  • Dresden Unit 2 iii December 1989

. r, List of Figures Figure Title/Description Page 2.2-1 MAPLHGR Limit versus Bundle Average Ex~osure - 2-2 ANF 8x8 Fuel 2.2-2 MAPLHGR Limit versus Bundle Average Exposure - 2-3 ANF 9x9 Fuel 2.2-3 MAPLHGR Limit versus Average Planar Exposure - 2-4 GE BXS LTAs 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 SxS 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 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 Dresden Unit 2 iv December 1989

/

  • Table 1.2-1 list of Tables Title/Description Control Rod Withdrawal Block Instrumentation Setpoints Page 1-2 2.3-1 MAPLHGR Multipliers 2-5
  • Dresden Unit 2 / v December 1989
  • 1.0 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION 1.1 Technical Specification Reference Technical Specification 3.2.C - Control .Rod Block Actuation 1.2 Description The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown in Table 1.2-1 .
  • Dresden Unit 2 1-1 December 1989
  • Trip Function Rod Block Monitor Upscale Table 1.2-1 Control Rod Withdrawal Block Instrumentation Setpoints T~ip Level Setting (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 .

  • Dresden Unit 2 1-2 December 1989

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  • 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 2.1 Technical Soecification References Section 2.2: Technical Specification 3.5.I-- Average Planar LHGR Section 2.3: See Table 2.3-1 2.2 Description The Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Bundle Average Exposure for ANF 8x8 fuel is determined from Figure 2.2-1.

The Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Bundle Average Exposure for ANF 9x9 fuel is determined from Figure 2.2-2.

The Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Average Planar Exposure for the GE BXS LTAs is determined from Figure 2.2-3.

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

  • Dresden Unit 2 2-1 December 1989

Figure 2.2-1 MAPLHGR Limit vs. Bundle Average Exposure ANF 8x8 Fuel r1s:--____________..,__

~ ~~............_~

1QJ;---------!o-----+---_...----~--_...-----;---~

s ,0 ,5 . 20 : 25 - 30:

Bmlie Average Upcmn (Gld/MTU)

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

Bundle Average MAPLHGR Exoosure (GWd/MTUl Limit. Kw/ft 0 13.00 10 13.00 15 13.00 18 12.85 20 12.60 25 11. 95 30 11.20 35 10.45 Dresden Unit 2 2-2 December 1989

  • Figure 2.2-2 MAPLHGR Limit vs. Bundle Average Exposure ANF 9x9 Fuel 5 10 15 20 25 30 35 40 Bundle Average Exposure (GWd/MTU),,

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

Bundle Average MAPLHGR Exoosure lGWD/MTUl Limit. Kw/ft 0 11.40 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 2 / 2-3 December 1989

  • Figure 2.2-3 MAPLHGR Limit vs. Average Planar Exposure GE axa LTAs 12 I

.~- -~

~

-="11

-=-* .. ""'

I I

~

7 . ~

0 5 10 15 20 25 30 35 40 45 Average Planer Exposure (GWd/St) Ill The above graph is based on the following MAPLHGR summary for the GE LTA fuel desiqn.

Average Planar MAPLHGR Exposure CGWD/STU) Limit. Kw/ft 0.2 11. 5 1.0 11.6 5.0 11. 9 10.0 12.l 15.0 12.l 20.0 11. 9 25.0 11.3 30.0 10.7 35.0 10.2 41.6 8.8 Dresden Unit 2 2-4 December 1989

  • Specification Title of TS Table 2.3-1 MAPLHGR Multipliers Scenar1o Multiol icative Factors 8xB 9x9 3.5.D.2 *Automatic Pressure One Relief 0.89 0.76 Relief Subsystems Valve Out of Service.

3.5.I and Average Planar LHGR Single Loop 0.91 0.91 3.6.H.3.f Recirc Pump Flow Operation limitations 3.5.I and Average Planar LHGR Single Loop 0.89 0.76 3.6.H.3.f Recirc Pump Flow Operation and limitations One Relief Valve Out of Service .

  • Dresden Unit 2 2-5 December 1989
  • 3.0 LOCAL STEADY STATE LHGR 3.1 Technical Specification Reference Technical Specification 3.5.J - Local S~eady State LHGR 3.2 Description The Local Steady State LHGR (SLHGR) limit versus Average Planar Exposure for all resident fuel is determined from Figure 3.2-1 .

Dresden Unit 2 3-1 December 1989

  • F;gure 3.2-1 Steady State Linear Heat Generation Rate (SLHGR) Limit vs. Planar Exposure
  • w ~ ~- ~

Planar Exposure (GWd/MTU)

~ ~ ~ ~

GE axa Fuel ANF 8x8 Fuel ANF 9x9 Fuel Exposure LHGR Exposure LHGR Exposure LHGR 0.0 13.4 0.0 16.0 0.0 14.5 45.8 13.4 25.4 14.1 5.0 14.5 42.0 9.3 25.2 10.8 48.0 7.2 Dresden Unit 2 3-2 December 1989

4.0 LOCAL TRANSIENT LHGR 4.1 Technical Specification Reference Technical Specification 3.5.K - Local Transient LHGR 4.2 Descrjption The Local Transient LHGR (TLHGR) limit versus Average Planar Exposure for ANF 8x8 fuel is determined from Figure 4.2-1.

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

For core modeling purposes, the TLHGR limit versus Average Planar Exposure for the GE BXS LTAs is 1.2 * (SLHGR Limit). The SLHGR limit is determined from Figure 3.2-1 Dresden Unit 2 / 4-1 December 1989

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  • Figure 4.2-1 Transient Linear Heat Generation Rate (TLHGR) Limit vs. Planar Exposure for ANF 8x8 Fuel
  • ~~~~~~~~.u..&~U..~.u..1~.u..L.u..a..U..i..u.~-

15 . 20. 25 - .30 - 35_.

Pfcinar Elpcsure (Gld/MTU) 40 45 50 -

Exoosure LHGR 0.0 19.2 25.4 16.9 43.2 10.8 48.0 10.0

  • Dresden Unit 2 4-2 December 1989
  • Figure 4.2-2 Transient Linear Heat Generation Rate (TLHGR) Limit vs. Planar Exposure for ANF 9x9 Fuel 5 10 15 20 25 30 35 40 50 Planar Exposure (GWd/MTIJ) 111 Excosure LHGR 0.0 19.2 25.4 16.9 43.2 10.8 48.0 10.0
  • Dresden Unit 2 4-3 December 1989
  • 5.0 MINIMUM CRITICAL POWER RATIO OPERATING LIMIT 5.1 Technical Soecification References Technical Specification 3.5.L - Minimum_C~tical Power Ratio (MCPR) 5;2 Description
a. The MCPR Operating Limit at rated flow versus measured scram time is shown in Figure 5.2-1. The MCPR Operating Limit is 1.39 or greater whenever the measured 90% insertion time is 3.50 seconds or less.
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 ii. The rated flow MCPR Operating Limit determined via Figure 5.2-1, whichever is greater.
c. During Automatic Flow Control, the MCPR Operating limit at 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. Line~r interpolation between the curves on Figure 5.2-3 is permissible .
  • Dresden Un;t 2 5-1 December 1989

Figure 5.2-1 MCPR Limit vs. Measured Scram Time to 901 Insertion Rated Flow Conditions 1.450

= 1400 UCP1 LCD
  • 1.J9 I

~* I

~

~..... .

cu Q,,

0 a:

~ 1.350

, *.300 2.70 2.80 2.90 3.00 3.10 3.20 3.30 140 3.50 Measured Scram iime to 90% Insertion (setends)

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 = 1.39 Note that the MCPR Operating Limit is not a function of scram time assuming the Technical Specification scram time limit of 3.50 seconds to 90% insertion (3.3.C) is met .

  • Dresden Unit 2

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5-2 December 1989

  • Figure 5.2-2 MCPR Operating Limit for Manual Flow Control 1.70 -

~

1.50

~ 1.50 ~

Iri t.40 ~

luo

~

I 1.20

"' ~ i'o.....

~~

1.1 0

  • 60 70 ,, 80 90 100 The above curve is based on the following MCPR operating limit su11111ary for Manual Flow Control and all fuel types:

Total Core Flow

(% Rated) MCPR Ooeratinq Limit 100 . 1.10 90 1.16 80 1.23 70 1.30 60 1.39 50 1.51 40 1.65 Dresden Unit 2 / 5-3 December 1989

  • Figure 5.2-3 MCPR Operating Limit for Automatic Flow Control 2.001,-----,------r----.-----r-----~--~-----

1.90

--~~--+-----i--:i} llOl~lili* t't11----I---~

= -

1 m1*11 Cmrljrpg I

~ .,.80 2) llOl~lili* 1.J!

aa.!Cmijn I *---+--__.

I5 1.70.....---~__...,;:i~~~-4---

tso1r---t----+~~~~-...b----+---l----1 ll 11111 U.. lili * '.J5

<<laid l)inrilis I 1.SCr----r---+---+-..;;::::=i.~;::::::........;i;:::=.-....~--...J

~ 1.40.,__---t---+----+----I----+--=======...+...;;;;;:::::~

I ,.. S.til Selllir 11.30 S.11111 1~.-------t-----1-------i------+------t-----+-----J 1.1~~~~--t:::---=--~-~~-...L.--....l

~ 00 m r980 ~ 100 TlJDL CORE Fl.DI (I ~ 98 llB/HR)

The above curve is based on the following MCPR operating limit su11111ary for Automatic Flow Control and all fuel types:

Total Core Fl ow MCPR Operating Limit*

(% Rated) 1.35 1.39 1.43 100 1.35 1.39 1.43 90 1.40 1.44 1.48 80 1.44 1.48 1.52 70 1.50 1.54 1.59 60 1.56 1.61 1.65 50 1.66 1.70 1.75 40 1.81 1.86 1.92

  • Column Headers are MCPR operating limits at rated flow.

Dresden Unit 2 5-4 December 1989

\_*~*

  • Core Operating Limits Report Dresden Station Unit 3 Cycle 12 Revision 0 December 1989

e Issuance of Changes Summary Affected Affected -

Section Paoes Summarv of Chanaes Date All All Oriainal Issue 12189

  • Dresden Unit 3 December 1989
  • Table of Contents Page References. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i i i List of Figures ............................................... iv List of Tables ................................................ v 1.0 Control Rod Withdrawal Block Instrumentation (3/4.2.C) ... I-1 I.I 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 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 ......................................... 3-1
  • 4.0 Local Transient LHGR (3/4.5.K) ........................... 4-1 4.1 4.2 Technical Specification Reference ................... 4-1 Description ......................................... 4-1 5.0 Minimum Critical Power Ratio Operating Limit (3/4.5.L) ... 5-1 5.1 Technical Specific~tion Reference ................... 5-1 5.2 Description ......................................... 5-1 Dresden Unit 3 ii December 1989
  • References
1. Commonwealth Edison Company Docket No. 50-237, Dresden Nuclear Power Station, Unit 3, Facility Operating License. DPR-25.
2. Letter (rom 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 .
  • Dresden Unit 3 iii December 1989

List of Figures Figure Title/Descriotion Page

2. 2-1 MAPLHGR Limit versus Bundle Averag_e 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 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 Dresden Unit 3 iv December 1989

/

List of Tables Table Title/Description Page 1.2-1 Control Rod Withdrawal Block Instrumentation 1-2 Setpoints 2.3-1 MAPLHGR Multipliers 2-4 Dresden Unit 3 v December 1989

.I 1.0 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION 1.1 Technical Specification Reference

/

Technical Specification 3.2.C - Control Rorl Block Actuation

1. 2 Descrip_tion The Rod Block Monitor Upscale Instrumentation Setpoints are determined from the relationships shown in Table 1.2-1.

Dresden Unit 3 1-1 December 1989

Table 1.2-1 Control Rod Withdrawal Block Instrumentation Setpoints Trip Function Trip Level Setting Rod Block Monitor Upscale (Fl ow Bi as) -

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

(See Note)

Single Loop Operation Less than or equal tG (0.65 Wd plus 41)

(See Note)

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

Dresden Un it 3 1-2 December 1989

. I 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE 2.1 Technical Specification References Section 2.2: Technical Specification 3.. 5.l --Average Planar LHGR Sectio~ 2.3: See Table 2.3-1 2.2 Description 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.

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

Dresden Un it 3 2-1 December 1989

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

'- ~-

3*

--.:::::.- ....-* ~

--*e**--- ..*-*---*

  • *1 2 -

.ll&

~..:

~1 . 1:

"'" ~ '

~- ...

I:

1a=.**

  • -a 9**-*-. - . -- - -.

5 10 15 20 . 25 - 30. 40 Bundle Average Exposure (GWd/MTU)

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

Bundle Average MAPLHGR Exposure {GWd/MTUl Limit, Kw/ft 0 13.00 10 13.00 15 13.00 18 12.85 20 12.60 25 11. 95 30 11.20 35 10.45

  • Dresden Unit 3

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2-2 December 1989

  • Figure 2.2-2 MAPLHGR Limit vs. Bundle Average Exposure ANF 9x9 Fuel The above graph is based on the following MAPLHGR summary for ANF 9x9 fuel design.

Bundle Average MAPLHGR Exposure (GWD/MTU) Limit. Kw/ft 0 11.40 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

  • SQecification Title of TS Table 2.3-1 MAPLHGR Multipliers Scenario Multiolicative Factors

-- , BxS 9x~

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

3.5.I and Average Planar LHGR Single Loop 0.91 0.91 3.6.H.3.f Recirc Pump Flow Operation Limitations 3.5.I and Average Planar LHGR Single Loop 0.89 0.76 3.6.H.3.f Recirc Pump Flow Operation and Limitations One Relief Valve Out of Service.

Dresden Unit 3 2-4 December 1989

3.0 LOCAL STEADY STATE LHGR 3.1 Technical Specification Reference Technical Specification 3.5.J - Local Steady State LHGR 3.2 Description The Local Steady State LHGR (SLHGR) limit versus Average Planar Exposure for all resident fuel is determined from Figure 3.2-1.

Dresden Unit 3 3-1 December 1989

  • Figure 3.2-1 Steady State Linear Heat Generation Rate (SLHGR) Limit vs. Planar Exposure NFh9 .......

so_ ss-20 25.- 30. 35.:. 45 Planar Exposure (GWd/MTU)

ANF 8x8 Fuel ANF 9x9 Fuel Exposure LHGR Exposure 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

4.0 LOCAL TRANSIENT LHGR 4.1 Technical Specification Reference Technical Specification 3.5.K - Local Transient LHGR 4.2 Description The Local Transient LHGR (TLHGR) limit versus Average Planar Exposure for ANF 8x8 fuel is determined from Figure 4.2-1.

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

Dresden Unit 3 4-1 December 1989

/

  • Figure 4. 2-r Transient Linear Heat Generation Rate (TLHGR) Limit vs. Planar Exposure for ANF 8x8 Fuel w1~----~--..,.....--.,.---,........___,----i---....,...-----------

15 20. 25 35 . . 40 45 SQ_

Pfanar Exposure (GWd/YTU)

Exposure LHGR 0.0 19.2 25.4 16.9 43.2 10.8

48. 0 10. 0 Dresden Unit 3 4-2 December 1989

t' *. ' '

  • Figure 4.2-2 Transient Linear Heat Generation Rate (TLHGR) Limit vs. Planar Exposure for ANF 9x9 Fuel 20~* . --r--r----r--r-~--.,..-..,.---..,1"-----
15. 2Q_ 25 30. 35* 40 45 so:..

Planar Exposure (GWd/lltU)

Exposure LHGR 0.0 19.2 25.4 16.9

43. 2 10 .8 48 .0 10 .0 December 1989 Dresden Unit 3 4-3

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'- l

  • 5.0 MINIMUM CRITICAL POWER RATIO OPERATING LIMIT 5.1 Technical Specification References Technical Specification 3.5.L - Minimum Crttical Power Ratio (MCPR) 5.2 Description
a. The MCPR Operating Limit at rated flow versus measured scram time is shown in Figure 5.2-1. The MCPR Operating Limit is 1.34 or greater whenever the measured 90% insertion time is 2.65 seconds or less.
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 ii. The rated flow MCPR bperating Limit determined via Figure 5.2-1, whichever is greater.
c. During Automatic Flow Control, the MCPR Operating Limit at 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
  • curves on Figure 5.2-3 is permissible.

Dresden Unit 3 5-1 December 1989

'i L

  • Figure 5.2-1 MCPR Limit vs. Measured Scram Time to 90% Insertion Rated Flow Conditions 1.450r--.,..---r---i----,--.,......----------

!J.4001--t--t---t---+--+--+----1-~~~

cn-

!j_

eu .

8--

a:-

§l.1.JS01.,__,~~--+---+---4---l---+---1-----i 1300

  • 2.70 2.80 2.90 3.00 3.10 3.20 j.JO J.40 J.50 Measured Scram Time to 90J fnsertion (seconds)
  • 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
  • 1-Figure 5.2-2 MCPR Operating Limit for Manual Flow Control 1.70 -

1.60

~7:-

~

11~

ri !*40 I t.30 ' """ ~ .......

! ~-

I ~.20 ~

~

1.10 1~-

50 _ 60- -

70 - !L 100.

1Ull cm: flDI {I RAlEJ.98 llBt'R)

The above curve is based on the following MCPR operating limit summary for Manual Flow Control and all fuel types:

Total Core Flow

(% Rated) MCPR Operating Limit 100 1.10 90 1.15 80 1.21 70 1.28 60 1.36 50 1.46 40 1.57 Dresden Unit 3 5-3 December 1989

.f-f' Figure 5. 2 MCPR Operating Limit for Automatic Flow Control 2.001.------~-----r-----.......----.......------------.....------

Naa:

1.901.....---+----+----+--i) llUI Qmlilq lili* 1..~--+----'-

=.

"1.so <<llWOnfim-._ j

,.....--~~--+----+--2) llal~lili* 1.JS._--+-------'

<<IWmf'mfm* I I  :

1.70

&*-1.so1----+--~~~~~-4---4-----+----J J) 11Dlr.Dlltili*1~

It ... f)nijm i i.scr---r---r--r-==:;:::~::::::t~:::+::=-t-

~ 1.40t----t---t----i~---i====:::+-===~===~~-  ::

I UC  !'ali 1.2011--------t------"""l-----.....------i--------l'-------..._-------'

  • 1.1~--~-~~~---so'-~-- __10.___....._m~---'-90-___,_HXJ".

mm. an: FlOI ~ RA1EJ, 98 IU/HR)

The above curve is based on the following MCPR operating limit summary for Automatic Flow Control and all fuel types:

Tota 1 Core* Fl ow 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 so 1.58 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

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