ML20077E342

Revised COLR for Quad-Cities Unit 2 Cycle 13

ML20077E342
Person / Time
Site:	Quad Cities
Issue date:	12/06/1994
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20077E341	List: ML20077E335 ML20077E342
References
NUDOCS 9412120244
Download: ML20077E342 (33)

Text

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3-ATTACHMENT A Revised COLR for Quad Cities Unit 2 Cycle 13 9412120244 941206 f;DR ADOCK 05000265 PDR

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, Cora Operating Limits Report ISSUANCE OF CHANGES

SUMMARY

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i Affected Affected  !

Section Pages Summary of Changes Date All All Original issue (Cycle 11) 10/89 l

4 All All Original issue (Cycle 12) 11/91 Reissue 2/92 All All Original Issue (Cycle 13) 2/93 2 2 Added Section 2.3 on SLO 3/93 References, 111,4 & S Revised References and Section 4.2 and 4/94 4.2 & 5 added Section 5.0 on Analytical Methods References, 111,4 Revised References and Section 4.2, 12/94 4.2 OLMCPR change I

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Quad Cities Unit 2 Cycle 13 l

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, Core Opsrating Limits Report TABLE OF CONTENTS  !

R EF ER E N C ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

LI ST O F TA B L ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

LI ST O F F I G U R ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

1.0 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATidN ...................1 1.1. TECHNICAL SPECIFICATION

REFERENCE:

.......................................1 1 . 2. D ES C R I PT I O N : . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)............ 2 2.1 TECH NICAL SPECIFICATION

REFERENCE:

....................................... 2

2. 2 D ES C R I PTI O N : .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .. . . . .. . . . . . . . . . . 2 2.3 SING LE LOOP OPERATIO N M U LTIPLIER: ......................................... 2 3.0 LIN EAR H EAT G EN ERATION RATE (LHGR) ............................................. 3 3.1 TECHNICAL SPECIFICATION

REFERENCE:

...................................... 3 3 . 2 D ES C R l PTI O N : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

4.0 MINIMUM CRITICAL POWER RATIO (MCPR)............................................ 4 4.1 TECHNICAL SPECIFICATION

REFERENCE:

....................................... 4 4.2 D ES C R I PTI O N : . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 S.0 A N A LYTI CA L M ET H O D S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . S l

il Quad Cities Unit 2 Cycle 13 1

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T Core Operating Limits R: pert n.

REFERENCES

1. Commonwealth Edison Company and lowa Illinois Gas and Electric Company Docket No. 50-265, Quad Cities Station, Unit 2 Facility Operating License, d

License No. DPR 30,

2. Letter from D. M. Crutchfield to All . Power Reactor Licenses and Applicants, Generic Letter 8816; Concerning the Removal of Cycle Specific Parameter - '

Limits from Technical Specifications. -

b 3. Supplemental Reload Licensing Report for Quad Cities Nuclear Power Station,

. Unit 2 Reload 12 Cycle 13,23A7197, Revision 0, Class I, November _1992.

4. Quad Cities Nuclear Power Station, Units 1 and 2, SAFER /GESTR LOCA Loss-of-Coolant Accident Analysis, NEDC 3134CP, Ravision 2, Class Ill, July 1989 (as amended).

5. Extended Operating Domain and Equipment Out-Of Service for Quad Cities Nuclear Power Station Units 1 and 2, NEDC-31449, Revision 1, Class ll, April 1992.

6. GE document GENE-637 037-1193, Class li," Analysis of End of Full Power Capability Coastdown with Load Following for Quad Cities 1 and 2, dated November,1993.

7. GE letter REK:94 079," Bounding Estimate of Operating Limit MCPR for Turbine Bypass Valves Inoperative, dated September,1994.

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W 111 Quad Cities Unit 2 Cycle 13

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Core Operating Limits Report A

LIST OF TABLES Table Title Page Maximum Average Planar Linear Heat Generation 2-1 Rate (MAPLHGR) vs. Average Planar Exposure for 21 GE78 P8DRB299 7G3.0 80M 145 T.

Maximum Average Planar Linear Heat Generation 22 Rate (MAPLHGR) vs. Average Planar Exposure for 22 GE78 P8DRB299-7G4.0-80M 145-T.

Maximum Average Planar Linear Heat Generation 2-3 Rate (MAPLHGR) vs. Average Planar Exposure for 23 GE88-P8DQB300 9G3.0 80M-4WR-145-T.

Maximum Average Planar Linear Heat Generation 2-4 Rate (MAPLHCR) vs. Average Planar Exposure for 24 CE88 P8DQB316-7G4.0 80M 4WR-145 T.

Maximum Average Planar Linear Heat Generation 25 Rate (MAPLHGR) vs. Average Planar Exposure for 25 GE98 P8DWB310-9GZ 80M 145 T.

Maximum Average Planar Linear Heat Gener0 tion 2-6 Rate (MAPLHGR) vs. Average Planar Exposure tcr 26 GE98 P8DWB29911GZ 80M-145 T.

Maximum Average Planar Linear Heat Generation i 27 Rate (MAPLHGR) vs. Average Planar Exposure for 27  !

GE98 P8DWB286 7G3.0-80M 145 T.

Maximum Average Planar Linear Heat Generation J 2-8 Rate (MAPLHGR) vs. Average Planar. Exposure for 28 GE9B P8DWB286-9GZ 80M 145 T.

I Maximum Average Planar Linear Heat Generation 29 Rate (MAPLHCR) vs. Average Planar Exposure for 29 l GE98 P8DWB310 7G3.0-80M 145-T. ~l i

Maximum Average Planar Linear Heat Generation <

2-10 Rs.te (MAPLHCR) vs. Average Planar Exposure for 2-10 GE98-P8DWB30810GZ1 80M-145-T.

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1 Quad Cities Unit 2 Cycle 13

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, Core Opsrating Limits.Repsrt LIST OF FIGURES .

Figure Title Page 41 - Kf Factor vs. Core Flow %. 41

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Quad Cities Unit 2 Cycle 13 4

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. Cora Operating Limits Report 1.0 CONTROL ROD WITHDRAWAL BLOCK INSTRUMENTATION (3.2/4.2) 1.1. TECHNICAL SPECIFICATION

REFERENCE:

Technical Specification Table 3.2 3 and 3.6.H

1.2. DESCRIPTION

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The Rod Withdrawal Block Monitor Upscale Instrumentation Trip j Setpoint for two recirculation loop operation is determined from the '

following relationship:

s (0.65)Wd + 43% **

• • Clamped, with an allowable value not to exceed the allowable value I for recirculation loop drive flow (Wd) of 100%.

Wd is the percent of drive flow required to produce a rated core flow of 98 million ib/hr. Trip level setting is in percent of rated power .

(2S11 MWth).

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I Page1 Quad Cities Unit 2 Cycle 13

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.., . Core Operating Limits Repert 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) (3.5/4.5) 2.1 TECHNICAL SPECIFICATION

REFERENCE:

- Technical Specification 3.5.1

2.2 DECRIPTION

MAPLHGR versus Average Planar Exposure for GE78-P8DRB299 7G3.0-80M 145-T is determined from Table 21.

MAPLHGR versus Average Planar Exposure for GE78 P8DRB299 7G4.0-80M 145-T is determined from Table 2-2.

MAPLHGR versus Average Planar Exposure for GE88-P8DQB300 9G3.0-80M 4WR-145 T is determined from Table 2 3.

MAPLHGR versus Average Planar Exposure for GE88-P8DQB316-7G4.0-80M-4WR-145 T is determined from Table 2-4.

MAPLHGR versus Average Planar Exposure for GE98 P8DWB310-9GZ-80M 145-T is determined from Table 2 5.

MAPLHGR versus Average Planar Exposure for GE98 P8DWB29911GZ-80M 145-T is determined from Table 2 6.

MAPLHCR versus Average Planar Exposure for GE98 P8DWB286-7G3.0-80M 145-T is determined from Table 2 7.

MAPLHGR versus Average Planar Exposure for GE98-P8DWB286 9GZ-80M 145 T is determined from Table 2 8.

MAPLHGR versus Average Planar Exposure for GE98-P8DW8310-7G3.0-80M-145 T is determined from Table 2 9.

MAPLHGR versus Average Planar Exposure for GE98 P8DWB30810GZ1-80M 145-T is determined from Table 2-10.

4 2.3 SINGLE LOOP OPERATION MULTIPLIER:

The tabulated values are multiplied by 0.85 whenever Quad Cities y

enters Single Loop Operation.  ;

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Quad Cities Unit 2 Cycle 13 .

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Core Operating Limits Report TABLE 2-1 MAPLHGR vs. AVERAGE PLANAR EXPOSURE '

FOR BUNDLE TYPE GE7B P8DRB299 7G3.0 80M 145 T 4

LATTICE 488 : P8DRLO71-NOG-80M-T LATTICE 494 : P8DRL319-7G3.0100M-T .

MAPLHGR LIMITS.

AVERAGE (KW/FT)

PLANAR  !

EXPOSURE 488 494 <

(GWd/ST) 0.20 11.00 11.00 1.00 11.00 11.00 5.00 11.60 11.60 10.00 12.20 12.20 15.00 12.10 12.10 20.00 12.00 12.00

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25.00 11.50 11.50 30.00 10.90 10.90 35.00 10.30 10.30 40.00 9.70 9.70 45.00 9.00 9.00 l

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', Cero Operating Limits Rep 3rt TABLE 2 2 MAPLHGR vs. AVERAGE PLANAR EXPOSURE FOR BUNDLE TYPE : GE78 P8DRB299-7G4.0-80M 145-T LATTICE 488 : P8DRLO71-NOG 80M T LATTICE 487 : P8DRL319-7G4.0-80M T MAPLHGR LIMITS AVERAGE (KW/FT)

PLANAR EXPOSURE 488 487 (GWd/ST) 0.20 10.90 10.90 1.00 11.00 11.00 5.00 11.50 11.50 10.00 12.10 12.10 15.00 12.10 12.10 20.00 11.90 11.90 25.00 11.50 11.50 30.00 11.00 11.00  ;

35.00 10.30 10.30 40.00 9.70 9.70 l 45.00 9.00 9.00 1

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. Core Operating Limits Report TABLE 2-3 MAPLHGR vs. AVERAGE PLANAR EXPOSURE FOR BUNDLE TYPE GE8B P8DQB300-9G3.0-80M 4WR-145 T  !

LATTICE 565 : P8DQLO71-NOG 80M-4WR-T LATTICE 671 : P8DQL320-9G3.0-80M 4WR-T LATTICE 686 : P8DQLO71-9GE2 80ht-4WR-T .>

AVERAGE MAPLHGR LIMITS (KW/FT)

PLANAR EXPOSURE 565 671 686 (GWd/ST) 0.00 11.57 11.39 11.57 0.20 11.50 11.42 11.50 1.00 11.30 11.50 11.30 2.00 11.28 11.75 11.28 l 3.00 11.33 12.08 11.33 4.00 11.40 12.47 11.40 5.00 11.48 12.80 11.48 1 6.00 11.55 13.01 11.55 I 7.00 11.61 13.16 11.61 8.00 11.66 13.29 11.66 9.00 11.69 13.39 11.69 10.00 11.72 13.44 11.72 12.50 11.44 13.34 11.44 15.00 11.07 12.96 11.07 20.00 10.29 12.19 10.29 25.00 9.50 11.46 9.50 35.00 7.93 10.08 7.93 43.30 4.66 -

4.66 45.00 -

8.46 -

50.00 -

6.14 -

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7 .. .mm r a Cere Oparating Limits Report TABLE 2 4 MAPLHGR vs. AVERAGE PLANAR EXPOSURE FOR BUNDLE TYPE GE8B P8DQB316 7G4.0 80M 4WR 145 T LATTICE 565 : P8DQLO71-NOG 80M 4WR-T LATTICE 679 : P8DQL337 7G4.0 80M 4WR T LATTICE 649 : P8DQLO71-7 gel 80M-4WR T AVERAGE MAPLHGR LIMITS (KW/FT)

PLANAR EXPO 5URE 565 679 649 (GWd/ST) 0.00 11.57 11.70 11.57 0.20 11.50 11.69 11.50 1.00 11.30 11.74 11.30 2.00 11.28 11.86 11.28 3.00 11.33 12.01 11.33 4.00 11.40 12.18 11.40 5.00 11.48 12.38 11.48 6.00 11.55 12.59 11.55 7.00 11.61 12.81 11.61 8.00 11.66 12.99 11.66 9.00 11.69 13.06 11.69 10.00 11.72 13.08 11.72 12.50 11.44 13.01 11.44 15.00 11.07 12.66 11.07-20.00 10.29 11.97 10.29 25.00 9.50 11.31 9.50 35.00 7.93 10.05 7.93 43.30 4.66 -

4.66 45.00 -

8.45 -

50.00 -

5.99 -

Page 2-4 Quad Cities Unit 2 Cycle 13

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'. Core Operating Limits Repert -

TABLE 2 5 MAPLHGR vs. AVERAGE PLANAR EXPOSURE FOR BUNDLE TYPE : GE98 P8DWB310-9GZ 80M 145 T LATTICE 731 : P8DWLO71 NOG 80M-T LATTICE 847 : P8DWL334 7G3.0-80M T LATTICE 848 : P8DWL350-7G3.0 80M-T LATTICE 849 : P8DWL350 2G4.0/7G3.0 80M T LATTICE 846 : P8DWLO71 9CEl-80M T AVERAGE MAPLHCR LIMITS (KW/FT)

PLANAR EXPOSURE 731 847 848 849 846 (GWd/ST) l 0.00 11.64 12.25 11.78 11.31 11.64 0.20 11.57 12.32 11.85 11.39 11.57 1.00 11.38 12.46 11.99 11.55 11.38 2.00 11.36 12.62 12.19 11.78 11.36 3.00 11.41 12.79 12.36 12.02 11.41 4.00 11.49 12.96 -12.52 12.22 11.49 5.00 11.56 13.14 12.69 12.44 11.56  !

6.00 11.63 13.23 12.81 12.60 11.63 7.00 11.69 13.30 12.93 12.77 11.69 8.00 11.74 13.38 13.04 12.93 11.74 9.00 11.78 13.43 13.14 13.08 11.78 10.00 11.81 13.46 13.21 13.20 11.81-12.50 11.54 13.41 13.21 13.21 11.54 i 15.00 11.16 13.02 12.94 12.93 11.16 1 20.00 10.37 12.28 12.30 12.29 10.37 l 25.00 9.58 11.57 11.61 11.60 '9.58 l 35.00 8.01 10.27 10.29 10.27 8.01-l 43.70 4.71 - - -

4.71 l 45.00 -

9.02 8.98 8.92 -

l 51.1 0 - - -

5.90 -

l 51.20 -

5.96 5.90 - -

Page 2 5 Quad Cities Unit 2 Cycle 13

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~. ,m Cero Oputting Limits Rep:rt TABLE 2-6 i

MAPLHGR vs. AVERAGE PLANAR EXPOSURE

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FOR BUNDLE TYPE : GE98-P8DWB299-11GZ-80M-145 T LATTICE 731 : P8DWLO71-NOG 80M-T LATTICE 850 : P8DWL322-9G3.0-80M T LATTICE 851 : P8DWL337 9G3.0-80M-T LATTICE 852 : PSDWL337-2G4.0/9G3.0 80M T 1 LATTICE 853 : P8DWLO71 11GE-80M T AVERAGE MAPLHCR LIMITS (KW/FT)

PLANAR EXPOSURE 731 850 851 852 853 (GWd/ST) 0.00 11.64 11.49 11.31 10.87 11.64 0.20 11.57 11.52 11.38 10.96 11.57 1.00 11.38 11.62 11.56 11.14 11.38 2.00 11.36 11.87 11.84 11.44 11.36 3.00 11.41 12.19 12.05 11.70 11.41 4.00 11.49 12.57 12.21 11.88 11.49 5.00 11.56 12.94 12.37 12.07 11.56 6.00 11.63 13.04 12.54 12.27 11.63 -

7.00 11.69 13.14 12.73 12.50 11.69 8.00 11.74 13.21 12.90 12.72 11.74 9.00 11.78 13.26 13.03 12.92 11.78 10.00 11.81 13.28 13.11 13.07 11.81 12.50 11.54 13.21 13.07 13.06 11.54 15.00 11.16 12.82 1 2.81 12.81 11.16 20.00 10.37 12.07 12.30 12.30 10.37 25.00 9.58 11.36 11.66 11.64 9.58 35.00 8.01 10.07 10.29 10.27 8.01 43.70 4.71 - - -

4.71 45.00 -

8.61 8.85 8.82 -

50.60 5.89 - - -

51.00 - - -

5.84 -

51.20 - -

5.81 - -

Page 2-6 Quad Cities Unit 2 Cycle 13

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. Ccra Oparating Limits Report TABLE 2-7 MAPLHGR vs. AVERAGE PLANAR EXPOSURE FOR BUNDLE TYPE : GE98-P8DW8286 7G3.0-80M 145-T LATTICE 731 : P8DWLO71-NOG-80M T LATTICE 1059 : P8DWL306-7G3.0-80M T 4 LATTICE 1060 : P8DWL324 7G3.0-80M-T LATTICE 1061': P8DWLO71-7CEl 80M T j AVERAGE MAPLHGR LIMITS (KW/FT)

PLANAR EXPOSURE- 731 1059 1060 1061 (GWd/ST) <

0.00 11.64 12.38 11.95 11.64 ,

0.20 11.57 12.45 12.03 11.57 1.00 11.38 12.54 12.11 11.38 2.00 11.36 12.65 12.30 11.36 3.00 11.41 12.75 12.57 11.41 4.00 11.49 12.85 12.88 11.49 5.00 11.56 12.94 12.97 11.56 6.00 11.63 12.95 13.01 11.63 7.00 11.69 12.97 13.09 11.69 8.00 11.74 13.01 13.17 11.74 9.00 11.78 13.05 13.21 11.78 10.00 11.81 13.09 13.23 11.81 12.50 11.54 13.04 13.16 11.54 15.00 11.16 12.71 12.79 11.16 20.00 10.37 12.06 12.06 10.37 25.00 9.58 11.43 11.37 9.58 35.00 8.01 10.04 10.12 8.01 1 43.66 4.71 -

4.71 45.00 -

8.60 8.68 -

50.66 -

5.84 - -

50.75 - -

5.91 - i l

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Quad Cities Unit 2 Cycle 13

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Core OpGroting Limits RGport

. TABLE 2 8 MAPLHGR vs. AVERAGE PLANAR EXPOSURE FOR BUNDLE TYPE GE98-P8DW8286 9GZ 80M-145-T l.ATTICE 731 : P8DWLO71-NOG 80M-T LATTICE 1059 : P8DWL306-7G3.0-80M-T LA'ITICE 1060 : P8DWL324-7G3.0-80M T '

' LATTICE 1000 : P8DWL324 2G4.0/7G3.0 80M-T LATTICE 1001 : P80WLO71-9CE-80M-T AVERAGE MAPLHGR LIMITS (KW/FT)

PLANAR EXPO 5URE 731 1059 1060 1000 1001 (GWd/5T)

O.00 11.64 12.38 11.95 11.42 11.64 0.20 11.57 12.45 12.03 -11.51 11.57 1.00 11.38 12.54 12.11 11.59 11.38 2.00 11.36 12.65 12.30 11.82 11.36-3.00 11.41 12.75 12.57 12.13 11.41 4.00 11.49 12.85 12.S8 12.51 11.49 5.00 11.56 12.94 12.97 12.69 11.56 6.00 11.63 12.95 13.01 12.80- 11.63 7.00 11.69 12.97 13.09 12.92 11.69 8.00 11.74 13.01 13.17 13.04 11.74 9.00 11.78 13.05 13.21 -13.14 11.78 10.00 11.81 13.09 13.23 13.20 11.81 12.50 11.54 13.04 13.16 13.14 11.54 15.00 11.16 1 2.71 12.79 12.77 11.16 20.00 10.37 12.06 12.06 12.04 10.37 25.00 9.58 11.43 11.37 11.36 9.58 35.00 8.01 10.04 10.12 10.11 8.01 i 43.66 4.71 - - -

4.71 45.00 -

8.60 8.68 8.65 -

50.66 -

5.84 -

5.92 -

50.75 - -

5.91 - -

Page 2-8 Quad Cities Unit 2 Cycle 13

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• - . j Cora Operating Limits'Rsp::rt .l l

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TABLE 2-9 MAPLHGR vs. AVERAGE PLANAR EXPOSURE FOR BUNDLE TYPE : GE98 P8DWB310-7G3.0-80M 145 T LATTICE 731 : P8DWLO71-NOG 80M T LATTICE 1644 : P8DWL334-7G3.040M T LATTICE 1645 : P8DWL350 7G3.0-80M-T LATTICE 1004 : P8DWLO717GE 80M-T AVERAGE MAPLHCR LIMITS (KW/FT)

PLANAR EXPOSURE 731 1644 1645 1004 (GWd/ST) 0.00 11.64 12.25 11.78 11.64 0.20 11.57 12.32 11.85 11.57 1.00 11.38 12.46 11.99 11.38 2.00 11.36 12.62 12.19 11.36 3.00 11.41 12.79 12.36 11.41 4.00 11.49 12.96 12.52 11.49.

5.00 11.56 13.14 12.69 11.56 6.00 11.63 13.23 12.81 11.63 7.00 11.69 13.30 12.93 11.69 8.00 11.74 13.38 13.04 11.74 9.00 11.78 13.43 13.14 11.78 10.00 11.81 13.46 13.21 11.81 12.50 11.54 13.41 13.22 11.54 15.00 11.16 13.03 12.95 11.16 20.00 10.37 12.29 12.31 10.37 25.00 9.58 11.58 11.62 9.58 35.00 8.01 10.28 10.31 8.01 43.66 4.71 - -

4.71 45.00 -

9.04 9.01 -

51.41 - -

5.88 -

51.43 -

5.94 - -

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. Core Operating Limits Repcrt  !

l TABLE 2-10

' t l MAPLHGR vs. AVERAGE PLANAR EXPOSURE.

FOR BUNDLE TYPE : GE98-P8DWB30810GZ 80M 145 T -

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LATTICE 731 : P8DWLO71 NOG 80M-T LATTICE 1642 : P8DWL332 8G4.0/2G3.0-80M T LATTICE 1669 : P8DWL348-8G4.0/2G3.0-80M T LATTICE 1188 : P8DWLO71-10GE 80M-T AVERAGE MAPLHCR LIMITS (KW/FT)

PLANAR EXPOSURE = 731 1642 1669 1188 (GWd/ST) 0.00 11.64 11.63 ~ 11.24 11.64 0.20 11.57 11.69 11.31 11.57 1.00 11.38 11.83 11.44 11.38 2.00 11.36 12.04 11.62 11.36 3.00 11.41 12.25 11.82 11.41 4.00 11.49 12.48 12.02 11.49 5.00 11.56 12.58 12.24 11.56 6.00 11.63 12.69 12.44 11.63 7.00 11.69 12.86 12.62 11.69 8.00 11.74 13.04 12.75 11.74 l 9.00 11.78 13.19 12.90 11.78 10.00 11.81 13.31 13.05 11.81 >

12.50 11.54 13.32 13.14 11.54 15.00 11.16 12.96 12.92 11.16 20.00 10.37 12.22 12.25 10.37 25.00 9.58 11.53 11.57 9.58 35.00 8.01 10.24 10.26 8.01 43.66 4.71 -

4.71 l 45.00 -

8.93 8.93 -

51.09 -

5.96 - -

51.1 5 - -

5.90 -

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Page 2-10 l

Quad Cities Unit 2 Cycle 13

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Core Op2 rating Limits Report-3.0 LINEAR HEAT GENERATION RATE (LHGR)(3.5/4.5)

. 3.1 TECHNICAL SPECIFICATION

REFERENCE:

Technical Specification 3.5J

3.2 DESCRIPTION

j A. The LHGR limit is 13.4 Kw/ft for fuel types:

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1. . GE78-BP8DRB299-7G3.0 80M-145-T

2. GE78-BP8DRB299-7G4.0 80M 145-T I B. The LHGR limit is 14.4 Kw/ft for fuel types:

1. GE8B-P8DQB300 9G3.0-80M 4WR-145-T r

2. GE88 P8DQB316-7G4.0 80M 4WR-145 T

3. GE9B P8DWB310-9GZ 80M 145 T

4. GE98-P8DWB29911GZ 80M-145-T

5. GE98-P8DWB286-7G3.0 80M 145-T '

6. GE9B-P8DWB286 9GZ 80M-145 T

7. GE98-P8DWB310 7G3.0-80M-145-T

8. GE98-P8DWB30810GZ-80M 145-T l

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Quad Cities Unit 2 Cycle 13 I

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I. Coro Opsrtting Limits Report 4.0 MINIMUM CRITICAL POWER RATIO (MCPR) (3.5/4.5) 4.1 TECHNICAL SPECIFICATION

REFERENCE:

Technical Specifications 3.5.K and 3.6.H

4.2 DESCRIPTION

During steady-state operation at rated core flow, the Operating Limit MCPR (OLMCPR) shall be greater than or equal:

1.42 for tave s 0.711 seconds where tave - mean 20% scram insertion time for all surveillance data from Technical Specification 4.3.C which has been generated in the current cycle.

For core flows other than rated, these nominal values of OLMCPR shall be increased by a factor of Kf where Kfis as shown in Figure 4-1.

Unit Two has been approved for operating up to 15% (Reference 6) above equilibrium coastdown power level with multiple control rods  :

Inserted. At End of Full Power Capability (EFPC) a generic MCPR operating limit MCPR penalty of 0.06 must be added to the operating .

limit MCPR in order to exceed equilibrium coastdown power.

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Quad Cities Unit 2 Cycle 13 1

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FIGURE 4-1 i Kf FACTOR 1 1.5 1

s 4

1.4 :----s.

9 A. . . ...... . . . . . . . . . . . . . . . . . . . . . . . . . . . - . . . . . _ - . . . . . . . . . . . . . . . . . . . . - . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

2 1.2

\ "'~.

_':A N utornatic Flow Cont rol -

- - - - - -N q - - - - ' - - - - - - - - - - - - - - - - - - - - -

N -

N ___

N ~__

j,j . . . _ . . . . . . . . . . . . . . . . .

. . . . . _ _ .~. % _ . . _ _ _ . . ._ . . . . . . . . . . . _ . . . . . . . . -

Manual Flow Cont h N N

's_.

. . .(..1 '37%Max Flow) j . . . . . . . . . .. ... . . . _ . . . . . - . . . . . ..... . . - . . . . . _ . ._.. . _ . . . . .. . N. . ... ... . _

0.9 25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100105

% Core Flow Quad Cities Unit 2 Cycle 13  :

Core Operating Limits Report Page 4-1

.m g.- - _< m . .m 3 ...

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_ Core Operating Limits Repsrt 5.0 - Analytical Methods i The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in the latest approved revision or supplement of the topical reports describing the methodology. For Quad Cities Unit 2, the topical reports are:

(1) NEDE-24011-P A " General Electric Standard Application for Reactor Fuel,"

(latest approved revision).

(2) Commonwealth Edison Topical Report NFSR 0085," Benchmark of BWR Nuclear Design Methods,"(latest approved revision). l (3) Commonwealth Edison Topical Report NFSR 0085, Supplement 1, Quad Cities Gamma Scan Comparisons,"(latest approved revision). .

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(4) Commonwealth Edison Topical Report NFSR-0085, Supplement 2, Design Methods Neutronic Licensing Analyses,"(latest approved -

revision).

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Quad Cities Unit 2 Cycle 13 1 l

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ATTACHMENT B NFS 50.59 Evaluation

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l NFS:BSS:94-200 l 10CFR50.59 SAFETY EVALUATION

, 1. List the documents implementing the proposed change (Mod #, Temporary Alt #,

Procedure #, DCR#, NWR #, etc.) -

1. General Electric Letter from Rick Kingston to R. W. Tsai, " Bounding Estimate of Operating Limit MCPR for Turbine Bypass Valves Inoperative", September 27,1994, REK:94-079.

2. Edward A. McVey to E. D. Eenigenburg, et. al., " Recommendations for Dresden and Quad Cities Stations to Resolve Main Turbine Bypass Valve Opening Time Uncertainty," September 27,1994, NFS:BSS:94-166.

3. John M. Freeman to John Paczoit, " Temporary Recommended Quad Cities OLMCPR for Bypass Valves Out of Service," September 27,1994 NFS:RSA:94-126.

4. John M. Freeman to William Pierce, " Recommendation for Quad Cities Unit 2 to Resolve Main Turbine Bypass Opening Uncertainty, December, l 5,1994, NFS:RSA:94-179.

2. Describe the proposed change and the reasons for the change. l This proposed change increases the Operating Limit Minimum Critical '

Power Ratio (OLMCPR) in the Core Operating Limits Report (COLR) to 1.42 (Option B Scram time of 0.711 sec) Quad Cities Unit 2 Cycle 13. This increase incorporates the results of a bounding and conservative OLMCPR recommended by General Electric. The change ensures that adequate ,

margin to the Safety Limit MCPR is maintained during a feedwater controller failure (FWCF) transient assuming that the turbine bypass valves fall to open (Reference 1). The FWCF is the only transient mentioned in the Supplemental Reload Licensing Submittal that takes credit for bypass i valve opening time. This change is being initiated as a conservative corrective action identified by a continuing investigation into the failure of the bypass valves to meet the required opening time assumed in the  ;

transient analysis for FWCF. '

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NFS:BSS:94-200 - i i

10CFR50.59 SAFETY EVALUATION ]

3. Is the change: I i

[X]_ Permanent I

[] Temporary - Expected duration:

AND l Plant Mode (s) restrictions while installed: l (NONE if no plant mode restrictions apply) i 1

4. List the SAR sections which describe the affected systems, structures, or  !

components (SSCs) or activities. Also list the SAR accident analysis sections which discuss the affected SSCs or their operation. List any other controlling .l documents such as SERs, previous modifications or Safety Evaluations, etc.

FSAR Section 4.4.1.2, Design Criteria, Operating Basis, and Operating  !

Limits. I 1

FSAR Section 7.7.4, Pressure Regulator and Turbine-Generator Controls.

FSAR Section 15.0, Accident and Transient Analysis. i FSAR Section 15.1.2, Increase in Feedwater Flow.

Quad Cities Unit 2 Cycle 13 SER. j l

Quad Cities Unit 2 Cycle 13 OPL 3. i 1

5. Describe how the change will affect plant operation when the changed SSCs function as intended (i.e., focus on system operation / interactions in the absence of equipment failures). Consider all applicable operating modes. Include a discussion of any changed interactions with other SSCs.

The change will ensure that adequate margin to the Safety Limit Minimum l Critical Power Ratio (SLMCPR) is maintained. The proposed change I implements a conservative MCPR Operating Limit by assuming that the main turbine bypass valves fail to open. The change is conservative l because partial opening of the bypass valves is not considered. The OLMCPR change is not expected to impact normal plant operation due to the large CPR margin that Unit 2 Cycle 13 will operate with through the end of cycle operation.

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NFS:BSS:94-200 10CFR50.59 SAFETY EVALUATION

6. Describe how the change will affect ecuipment failures, in particular, describe any new failure modes and their impact during all applicable operating modes.

The proposed change will ensure fuel integrity by protecting the MCPR Safety Limit regardless of the main turbine bypass valves opening time.

The change will ensure that adequate margin to therSLMCPR is maintained.

The change will not affect equipment failures and will not introduce any new failure modes.

7. Identify each accident or anticipated transient (i.e., large/small break LOCA, loss of load, turbine missiles, fire, flooding) described in the SAR where any of the following is true:

The change alters the initial conditions used in the SAR analysis The changed SSC is explicitly or implicitly assumed to function during or after the accident Operation or failure of the changed SSC could lead to the accident ACCIDENT SAR SECTION l

increased Feedwater Flow 15.1.2 i

8. List each Technical Specification (Safety Limit, Limiting Safety System Setting or l Limiting Condition for Operation) where the requirement, associated action i items, associated surveillance's, or bases may be affected. To determine the factors affecting the specification, it is necessary to review the FSAR and SER wtiere the Bases Section of the Technical Specifications does not explicitly state the basis.

1.1.A Safety Limit Minimum Critical Power Ratio less than 1.06 constitutes a violation of the fuel cladding integrity safety limit.

1 3.5.L. Minimum Critical Power Ratio (MCPR)(COLR 4.0, Operating Limit  !

Minimum Critical Power Ratio).

During steady state operation at rated core flow, MCPR shall be equal to or greater than the MCPR limit specified in the Core Operating Limits Report.

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.. 1 NFS:BSS:94-200 10CFR50.59 SAFETY EVALUATION

9. Will the change involve a Technical Specification revision? [] Yes [X) No If a Technical Specification revision is involved, the change cannot be implemented until the NRC issues a license amendment. When completing Step 14, indicate that a Technical Specification revision is required.

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NFS:BSS:94-200 10CFR50.59 SAFETY EVALUATION

10. To determine if the probability or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the SAR may be increased, use one copy of this page to answer the following questions for each accident listed in Step 7. Provide the rationale for all NO answers.

Affected accident: SAR Section:

Increased Feedwater Flow 15.1.2 May the probability of the accident be increased? [] Yes [X] No This proposed change does not impact equipment or processes which could affect the probability of the Increased Feedwater Flow transient. The margin of safety to the SLMCPR is being re-established.

May the consequences of the accident (off-site dose) [] Yes (X) No be increased?

The proposed change implements a conservative MCPR Operating Limit by assuming that the main turbine bypass valves fall to open. The new OLMCPR will ensure that the SLMCPR is protected thus ensuring fuel integrity.

May the probability of a malfunction of equipment [] Yes [X] No -

important to safety increase?

The proposed change provides a new OLMCPR. The i processes by which equipment important to, safety is operated and the equipment itself are not affected.

May the consequences of a malfunction of equipment [] Yes [X] No i important to safety increase? l l

The proposed change implements a bounding and l conservative Operating Limit MCPR recommended by j General Electric. The failure of the main turbine bypass '

valves to open during a FWCF transient is bounded by the new OLMCPR, thereby ensuring that the SLMCPR is protected. ~

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NFS:BSS:94-200 10CFR50.59 SAFETY EVALUATION If any answer to Question 10 is YES. then an Unreviewed Safety Question exists.

11. Based on your answers to Questions 5 and 6, does the change adversely impact systems or functions so as to create the possibility of an accident or malfunction of a type different from those evaluated in the SAR7

[] Yes [X] No Describe the rationale for your answer:

The proposed change implements a conservative MCPR Operating Limit by assuming that the main turbine bypass valves fall to open during the transient. The processes by which equipment is operated has not been changed. The equipment has not been changed.

If the answer to Question 11 is YES. then an Unreviewed Safety Question exists.

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i NFS:BSS:94-200 l 10CFR50.59 SAFETY EVALUAT!ON

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12. Determine if parameters used to establish the Technical Specification limits are changed. Use one copy of this page to answer the following questions for each

' Technical Specification listed in Step 8. List the Technical Specification,

- Technical Specification Bases, SAR and SER Sections reviewed for this evaluation.

Evaluation of Technical Specification:

(enter N/A if none are_affected and check last option.) ,

i (Check appropriate condition):

[] All changes to the parameters or conditions used to establish the Technical Specification requirements are in a conservative direction. Therefore, the actual acceptance limit need not be identified to determine that no reduction in margin of safety exists -

3 proceed to Question 13.

[X) The Technical Specification or SAR provides a margin of safety or acceptance limit for the applicable parameter or condition. List the limit (s)/ margin (s) and applicable reference for the margin of safety  ;

below - proceed to Question 13.

[] The applicable parameter or condition change is in a potentially non-conservative direction and neither the Technical Specification, l the SAR, or the SER provides a margin of safety or an acceptance i limit. Request Nuclear Licensing assistance to identify the ,

acceptance limit / margin for the Margin of Safety determination by t consulting the NRC, SAR, SER's or other appropriate references.

List the agreed limit (s)/ margin (s) below, i

[ ]The change does not affect any parameters upon which Technical Specifications are based; therefore, there is no reduction in the margin of safety - proceed to Question 14.

List Acceptance Limit (s)/ Margin (s) of Safety-

)

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'l NFS:BSS:94-200 10CFR50.59 SAFETY EVALUATION -

Tech. Spec.: 1.1.A The existence of a minimum critical power ratio (MCPR) less than 1.06 for Quad Cities Unit 2 Cycle 13 shall constitute violation of the MCPR fuel cladding integrity safety limit.

3.5.L. Minimum Critical Power Ratio (MCPR) (COLR 4.0, Operating Limit Minimum Critical Power Ratio). .

During steady-state operation at rated core flow, MCPR shall be equal to or greater than the MCPR limit specified in the Core Operating Limits Report.

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, NFS:BSS:94-200

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10CFR50.59 SAFETY EVALUATION

13. Use the above limits to determine if the margin of safety is reduced (i.e., the new values exceed the acceptance limits). Describe the rationale for your l determination. Include a description of compensating factors used to reach that I conclusion. '

The proposed change establishes a conservative OLMCPR based upon a postulated FWCF with failure o'I the bypass valves to open, thereby protecting the MCPR safety limit. .

If a Marain of Safetv is reduced an Unreviewed Safety Question exists.

14. Check one of the following:

[] An Unreviewed Safety Question was identified in Step 10, Step 11, or Step 13. The proposed change MUST NOT be implemented without NRC approval.

[X] No Unreviewed Safety Question will result (Steps 10,11, and 13)

AND no Technical Specification revision will be involved. The change may be implemented in accordance with applicable procedures.

[] A Technical Specification revision is involved; but no Unreviewed Safety Question will result. The proposed change requires a License Amendment. Notify Station Regulatory Assurance and Nuclear Licensing that a Technical Specification revision is required.

Mark below as applicable.

[] The change is not a plant modification or minor plant change and will not be implemented under 10CFR50.59.

Upon receipt of the approve'd Technical Specification change from the NRC, the change may be implemented.

[] The change is a plant modification or minor plant change.  !

Mark below as applicable.

[] A revision to an existing Technical Specification is I required. The change MUST NOT be installed until receipt of an approved Technical Specification <

revision.

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>g NFS:BSS:94-200  ;

10CFR50.59 SAFETY EVALUATION

[] The change will not conflict.with any existing Technical Specifications and only new Technical Specifications are required. In these cases, Nuclear Licensing may authorize installation, but not operation, prior to receipt of NRC approval of the License Amendment. If such authorization is granted, the block below should be checked.

[] Nuclear Licensing ha's authorized installation, but not operation, prior to receipt of NRC approval of the License Amendment. -The 10CFR50.59 Safety Evaluation indicates that no Unreviewed Safety Question will result and provides authority for installation only.

. NOTE: Partial modifications and/or separate 10CFR50.59 reviews forportions of the work may be used to facilitate installation.

Preparer: u.w~ 12 - S - s'y

/_ _ $ignature Date

15. The reviewer has determined that the documentation is adequate to support the above conclusion and agrees with the conclusion.

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Reviewer: 8m M/[~n /7-9 & ,

f /Signaturef Date i

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