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Category:FUEL CYCLE RELOAD REPORTS
MONTHYEARML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 ML20247N6281998-05-19019 May 1998 Rev 2 to COLR for Quad Cities Unit 2 Cycle 15 ML20198R1451997-11-0404 November 1997 Rev 1 to Quad Cities,Unit 2 Cycle 15 Colr ML20198R1911997-11-0404 November 1997 COLR for Quad Cities Unit 2 Cycle 15 ML20117H8791996-05-31031 May 1996 Revised COLR for Quad Cities Unit 2,Cycle 14 ML20117H7321996-05-31031 May 1996 Revised COLR for Quad Cities Unit 1,Cycle 15 ML20077E3421994-12-0606 December 1994 Revised COLR for Quad-Cities Unit 2 Cycle 13 ML20069F7221994-05-31031 May 1994 Cycle 14 Core Operating Limits Rept ML20045A5481993-05-31031 May 1993 Quad-Cities Nuclear Power Station Unit 1,Summary of Fuel Performance,End-of-Cycle 12, May 1993 ML20044F9731993-05-21021 May 1993 Revised, Quad-Cities Unit 2,Cycle 13 Colr. ML20044F9931993-05-21021 May 1993 Revised Quad-Cities Unit 1,Cycle 13 Colr. ML20125B5301992-12-0303 December 1992 Cycle 13 Colr ML20101A0201992-01-31031 January 1992 Core Operating Limits Rept Quad Cities Nuclear Power Station,Unit 2,Reload 11 (Cycle 12) ML20066F4001991-01-21021 January 1991 Core Operating Limits Rept for Quad-Cities Unit 1 Cycle 12 ML19325C9081989-10-11011 October 1989 Core Operating Limits Rept for Quad Cities Nuclear Power Station Unit 1,Reload 10 (Cycle 11). ML20247D3071989-05-31031 May 1989 Core Operating Limits Rept for Quad Cities Nuclear Power Station Unit 1,Reload 9 (Cycle 10) ML20247D3171989-05-31031 May 1989 Core Operating Limits Rept for Quad Cities Nuclear Power Station Unit 2,Reload 9 (Cycle 10) ML20148N4111988-01-31031 January 1988 Rev 0 to, Supplemental Reload Licensing Submittal for Quad Cities Nuclear Power Station Unit 2,Reload 9,Cycle 10 ML20215A5451986-08-31031 August 1986 Errata & Addenda Sheet 14,replacing Pages v/vi,3-2,4-3,4-10, 4-15 & 4-16,to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Station ML20215A5271986-07-31031 July 1986 Rev 0 to Supplemental Reload Licensing Submittal for Quad Cities Nuclear Power Station,Unit 2,Reload 8 (Cycle 9) ML20215A5341986-05-21021 May 1986 Errata & Addenda Sheet 15,replacing Pages v/vi,3-2,4-3 & 4-16,to LOCA Analysis Rept for Dresden Units 2 & 3 & Quad Cities 1 & 2 Nuclear Power Station ML20212Q2301985-08-31031 August 1985 Rev 0 to Supplemental Reload Licensing Submittal for Quad Cities Nuclear Power Station Unit 1,Reload 8 (Cycle 9) ML20024C2481983-05-31031 May 1983 Rev 0 to Supplemental Reload Licensing Submittal for Quad Cities Nuclear Power Station,Unit 2,Reload 6 (Cycle 7). 1998-05-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With SVP-98-326, Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151T2711998-09-0404 September 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 ML20151Y7261998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Quad Cities Nuclear Power Station ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20151Y7301998-07-31031 July 1998 Revised MOR for Jul 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20237A6251998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Quad Cities Nuclear Power Station,Unit 1 & 2 SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With1998-07-15015 July 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2 ML20247N6281998-05-19019 May 1998 Rev 2 to COLR for Quad Cities Unit 2 Cycle 15 ML20216C0561998-04-30030 April 1998 Safe Shutdown Rept for Quad Cities Station,Units 1 & 2, Vols 1 & 2.W/22 Oversize Figures SVP-98-176, Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20217G3951998-04-0808 April 1998 TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 2 TS (Safety-Related) Snubber Population 129 Snubbers SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2 1999-09-30
[Table view] |
Text
_ _ _ . . _ _ _ _ _ _ _ . _ . . _ . _ . _ . _ _ _ _ _ _ _ . . . _ _ _ _ _ _ . _ _ _ _ _ _ _
e Core Operating Limits Report Quad Cities Nuclear Power Station Unit 2. Reload 11 (Cycle 12)
~
O 9204170202 DR 920413 p ADOCK 05000265 PDR
p Core Operating Limits Report ISSUANCE OF CHANGES
SUMMARY
Affected Affected Summary of Changes Date Section Pages All All Original issue (Cycle 11) 10/89 All All Cycle 12 Reissue - Includes Revised MCPR 1/92 Option A SSAF l
1
~
i Quad Cities Unit 2 1 Cycle 12
. . ~ . . . . . . . ~ . . - . - - - - - - . - . - - - - . ~ . -.- -
Core Operating Limits Report Table of Contents Paag REFERENCES........................................................... iii LIST OF FIGURES..................................................... iv 1.0 CONTROL R0D WITHDRAWAL BLOCK INSTRUMENTATION (3.2/4.2)........ 1-1 1.1 Technical Spacification Reference....................... 1-1 2.0 AVERAGE PLANAR-LINEAR HEAT GENERATION RATE (3.5/4.5).......... 2-1 2.1 . Technical Specification................................. 2-1 2.2 Description.................................... . ...... 2-1 3.0 LINEAR HEAT GENERATION RATE................................... 3-1
-2.1 Technical Specification................................. 3-1 2.2 Description............................................. 3-1 4.0 MINIMUM CRITICAL POWER RAT 10.................................. 4-1 2.1 Technical Specification................................. 4-1 2.2 Dest; '9 tion............................................. 4-1 d
Quad Cities Unit 2 ii Cycle 12 i
l . _ _ - . -..
. .- -. . . . . . _ - < - ~ - . - - . - _ - _ =. -- -. - . - . -
Core' Operating Limits Report REFERENCES
- 1. Commonwealth Edison Company and lowa-Illinois Gas and Electric Company Docket No. 50-265, Quad Cities Station, Unit 2 Facility Operating License No. DPR-30.
- 2. NRC letter, D. M. Crutchfield to All Power Reactor Licenses and Applicants, Gerieric Letter 88-16; Concerning the Removal of Cycle Specific Parameter Limits from Technical Specifications.
- 3. GE document, 23A7118 Rev. O, Suppleneatal Reload License Report for Quad Cities Nuclear Power Station Unit E Reload 11 Cycle 12, June 1991.
4, GE document, NEDC-31345P, Quad Cities Nuclear Power Station Units 1 & 2, SAFER /GESTAR-LOCA Loss-of-Coolant Accident Analysis, July 1989 (as amended),
- 5. GE document, NEDE-240ll-P-A-9, General Electric Standard Application for Reactor Fuel (GESTAR), September 1988 (as amended).
Quad Cities Unit 2 iii Cycle 12 1
l
Core Operating Limits Report LIST OF FIGURES FIGURE TITLE / DESCRIPTION PAGE !
2.2-1 MAPLHGR Limit vs. Actual Planar Exposure for Fuel 2-2 Type BP80RB282.
2.2-2 .MAPLHGR Limit vs. Actual Planar Exposure for Fuel 2-3 Type BP8DRB283H.
2.2-3 MAPLHGR Limit vs. Actual Planar Exposure for fuel 2-4 :
Type BP8DRB239.
2.2-4 MAPLHGR Limit vs. Actual Planar Exposure for Fuel 2-5 Type BP80RB299L.
2.2-5 HAPLHGR Limit vs. Actual Planar Exposure for fuel 2-6 Type BD316A.
2.2-6 MAPLHGR Limit vs. Actual Planar Exposure for Fuel 2-7 Type BD300C.
2.2-7 MAPLHGR Limit vs. Actual Planar Exposure for Fuel 2-8 Type GE9B-P8DWB299-llGZ-80M-145-T.
2.2-8 MAPLHGR Limit vs. Actual Planar Exposure for Fuel 2-9 Type GE98-P8DWB310-9GZ-80M-145-T. --
2.2-9 MAPLHGR Limit vs. Actual Planar Exposure for Fuel 2-10 Type GE9B-P80WB286-9GZ-80M-145-T.
2.2-10 MAPLHGR Limit vs. Actual Planar Exposure for Fuel 2-11 Type GE98-P80WB286-7G3.0-80M-145-T.
4-1 Kf Factor vs. Core flow %. 4-2 d
l Quad Cities Unit 2 iv Cycle 12
Corea Operating Limits Report i
1.0 (QNTROL ROD WITHDRAWAt BLOCK INSTRUMENlATION (3.2/4.2) 1.1 TECHNICAL SPECIFICATION
REFERENCE:
Technical Specification Table 3.2-3 and 3.6.H 1.2 DESCRIPT10N1 The f.od Withdrawal Block Monitor Upscale Instrumentation Trip 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 allowcble value for recirculation loop flow (W )d of 100%.
Wd is the percent of drive flow required to produce a rated core flow of 98 million lb/hr. Trip level setting is in percent of rated power (2511 MWth).
Quad Cities Unit 2 1-1 Cycle 12
~.
Core Operating Limits Report 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 DESCRIPT10N1 The MAPLHGR Limit versus Actual Planar Exposure for fuel Type BP8DRB282 are determined from figure 2.2-1.
The MAPLHGR Limit versus Actual Planar Exposure for fuel Type BP80RB283H are determined from Figure 2.2-2.
The MAPLHGR Limit versus Actual Planar Exposure for Fuel Type BP80RB299 are determined from figure 2.2-3.
The MAPLHGR Limit versus Actual Planar Exposure for fuel Type BP80RB299L are determined from Figure 2.2-4.
The MAPLHGR Limit versus Actual Planar Exposure for Fuel Type BD316A are determined from figure 2.2-5.
The MAPLHGR Limit versus Actual Planar Exposure for Fuel Type B0300C are determined froni Figure 2.2-6.
The MAPLHGR Limit versus Actual Planar Exposure for Fuel Type -
GE98-P8DWB299-llGZ-80M-145-T are determined from Figure 2.2-7.
The MAPLHGR Limit versus Actual Planar Exposure for Fuel Type GE9B-P8DWB310-9GZ-80M-145-T are determined from Figure 2.2-8.
The MAPLHGR Limit versus Actual Planar Exposure for Fuel Type GE9B-P80WB286-9GZ-80M-145-T are determined from Figure 2.2-9.
The MAPLHGR Limit versus Actual Planar Exposure for Fuel Type GE9B-P8DWB286-7G3.0-80M-145-T are determined from figure 2.2-10.
Quad Cities Unit 2 2-1 Cycle 12
Figure 2.2-1 g.
[
-i
- i MAPLHGR Limit vs Average Planar Exposure
% for Fuel Type BP8DRB282 i,e X- ,
12.50 i a -
- 7 g.
s
~
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P 11.50
/ 3 g .
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. (3 11.00 ;
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t 9.00 3, I
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n w
& Average Planar Exposure (GWd/STU) n 4
Figure 2.2-2 y-a = .
a MAPLHGR Limit vs Average Planar Exposure g for Fuel Type BP8DRB283H 3
.7 12.50
- g% 7
- ~ b 12.00 uf P 11.50 3 a H
o 11.00 3 m
R 10.50
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. I
.t ,lll>! i e il:f; t!! t!!li l1 i; l :! i l : '
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_ g . 0 0 0 0 0 0 0 0 0 0 5 0 5 0 5 0 5 0 5 2 2 1 1 0 0 9. 9 8 1 1 1 1 1 1 MAPLHGR .i n kW/ft i
y l ;;_0 eE [ ?. '
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' !ll!llj (il,lll!
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'e Figure 2.2-4' MAPLHGR Limit vs Average Planar Exposure $
[" g
$ for Fuel Type BP8DRB299L' ;
12.50 g
[
a e
I p >
\% W
\
t 11.50 L
H, 11.00 -
\ 3 1-
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10.50 x 10.00
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i t
9.00 I
8.50 o 5 10 15 20 25 30 35 40 45 50 :
f
=
. Average Planar Exposure (GWd/STU)
'y' Figure 2.2-5 MAPLHGR Limit vs Average Planar Exposure g n
E for Fuel Type BD316A g a
l
~
14 5
M j [ \ ]=
g 12 f p
L
\ A H 11 %
~,
G R 10
\-
e m
n 9 N
\
k 8 \
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/ 7 3 l \
6 5 55 n
15 20 25 30 35 40 45 50 I 0 5 10 f_.
- Average Planar Exposure-(GWd/STU)
b Figure 2.2-6 g ,
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MAPLHGR Limit vs Average Planar Exposure *[- ,
for Fuel Type BD300C l 3 3-y 14 f 13 5
r C ;
- M A ' E 12
- P
/ K j ;
N <+ t L
H 11" 3 '
G
~ R 10 i g
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S-S 0 5 10 15 20 25 30 35 40 45 50 55 x
- Average Planar Exposure (GWd/STU)
F t
r >
' I
Figure 2.2-7 .c n
[
MAPLHGR Limit vs Average Planar Exposure j
- n for Fuel Type GE9B-P8DWB299-11GZ-80M-145-T 3
" e. -
E 14 5 !
EiF c ,
I
", 13 3 $
b 2
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R 10
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n 8 %
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W t I 7
,\
f i 6 w l-5 .i n 0 5 10 15 20 25 30 .35 40 45 50 55 i h Average Planar Exposure (GWd/STU) :
i.
f o 1 .;
'e Figure 2.2-8 g 5 MAPLHGR Limit vs Average Planar Exposure [.
l for Fuel Type GE9B-P8DWB310-9GZ-80M-145-T jc
$ 14 4 o r.
t N
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n Average Planar Exposure (GWd/STU)- ,
4 i
- [
' I'
if Figure 2.2-9 [
e MAPLHGR Limit vs Average Planar Exposure s .;
E for Fuel Type GE9B-P8DWB286-9GZ-80M-145-T [
ET c *
,) 14 ,_
~ E 13 g 3 0 t 5
12 g P
/ s H 11 %
I go -
9 N
n % -j k 8
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y, \
- S(
6 ,
Q 5 25 30 50 55 i
{ 0 5 10 15 20 35 40 45 M Average Planar Exposure (GWd/STU) i f
i
'e Figure 2.2-10 g
[-E MAPLHGR Limit vs Average Planar Exposure for Fuel Type GE9B-P8DWB286-7G3.0-80M-145-T
"[
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- Average Planar Exposure (GWd/STU)
4 Core Operating Limits Report 3.0 LINEAR HEAT GENERATION R&TE ILHGR) (3,5/4.J1 3.1 ' TECHNICAL _ SPECIFICATION
REFERENCE:
Technical Specification 3.5.J
3.2 DESCRIPTION
- a. The LHGR limit is 13.4 kw/ft for fuel types:
- 1. BP80RB282
- 2. BP8DRB283H
- 3. BP80RB299
- 4. BP8DRB299L
- b. The LHGR limit is 14.4 kw/ft for fuel types:
- 1. BD316A
- 2. BD300C
- 3. GE9B-P8DWB299-11GZ-80M-145-T
- 4. GE98-PSDWB310-9GZ-80M-145-T
- 5. GE98-P80WB286-9GZ-80M-145-T
- 6. GE98-P80WB286-7G3.0-80M-145-T Quad Cities Unit 2 3-1 Cycle 12 l
Core Operating Limits Report 4.0 MINIMUM CRITICAL POWER RATIO (MCPR) (3.5/4.5) 4.1 TECHNICAL SPECIFICATION
REFERENCE:
Technical Specification 3.5.K and 3.6.H
4.2 DESCRIPTION
During steady-state operation at rated core flow, MCPR shall be greater than or equal:
1.30 for tave s 0.68 sec.
1.40 for tave 2 0.86 sec.
(0.556)tave + 0.922 for 0.68 sec. < tave < 0.86 sec.
where tave - mean 20% _ scram insertion time for all surveillance data from Technical Spe:ification 4.3.0 which has been generated for the current cycle.
For core flows other than rated, these ncainal values of MCPR shall be increased by a f actor of Kf where Kf is as shown in Figure 4-1.
When operating with a Feedwater Heater Out-of-Service, the Operating MCPR Limit shall be increased by 0.02.
l l
l l
l l
I Quad Cities Unit 2 4-1 Cycle 12
e Figure 4-1 !?
Kf Factor e
- 4
$ 1.50 ",_'
r.
1.40- s.
i- .
~ E,
~
1.30 's
^h s.
K 1 20
\ '
s ,
+
i f % %
~ '
% m 1.10 , - ,
N '
~
% w ~
~
1.00 3
0.90 '
25 30 35 40 45 50 55 60 65 70 75 80 85 90 95 100 Core Flow % ~
cn ii;" -
Manual Flow Control Auto Flow Control g; i t
. 1