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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 ML20044F9931993-05-21021 May 1993 Revised Quad-Cities Unit 1,Cycle 13 Colr ML20044F9731993-05-21021 May 1993 Revised, Quad-Cities Unit 2,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). ML20247D3171989-05-31031 May 1989 Core Operating Limits Rept for Quad Cities Nuclear Power Station Unit 2,Reload 9 (Cycle 10) ML20247D3071989-05-31031 May 1989 Core Operating Limits Rept for Quad Cities Nuclear Power Station Unit 1,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) ML20030C1281981-06-30030 June 1981 Supplemental Reload Licensing Submittal for Quad Cities Nuclear Power Station,Unit 2 Reload 5 (Cycle 6) 1998-05-19
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000254/LER-1999-004-03, :on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-021999-10-12012 October 1999
- on 990910,CREVS Air Filtration Unit Was Declared Inoperable.Caused by Airflow Rate in Excess of TS Allowable.Airflow Was Adjusted During Performance of Surveillance Procedure Qcos 5750-02
05000254/LER-1999-003-05, :on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure1999-10-0707 October 1999
- on 990907,noted That HPCI Was Inoperable Due to Manual Closure of HPCI Steam Supply Isolation Valve.Cause Indeterminate.Suppl LER Will Be Issued Upon Determination of Root Cause of Control Switch Failure
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 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20216H8481999-09-23023 September 1999 Safety Evaluation Supporting Amends 190 & 187 to Licenses DPR-29 & DPR-30,respectively 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 ML20210U7831999-08-0404 August 1999 Safety Evaluation Supporting Amends 189 & 186 to Licenses DPR-29 & DPR-30,respectively 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 ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept 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 05000265/LER-1999-002-04, :on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 9907151999-06-25025 June 1999
- on 990527,station Personnel Discovered Unsealed One Inch Diameter Pipe Penetrating Secondary Containment.Caused by Lack of Proper Work Control.Util Will Permanently Cap Spare Subject Pipe by 990715
ML20196F4261999-06-25025 June 1999 Safety Evaluation Supporting Amends 188 & 185 to Licenses DPR-29 & DPR-30,respectively 05000254/LER-1999-004-02, :on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised1999-06-18018 June 1999
- on 990521,reactor Scram Occurred.Caused by Steam Intrusion Into Scram Discharge Volume.Procedure Qcop 12200-11, RWCU Sys Startup & Pump Operation, Revised
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 ML20210H3501999-05-25025 May 1999 Rev 1 to Quad Cities Station IPEEE Submittal Rept ML20207E1621999-05-25025 May 1999 Rev 1 to Quad Cities IPEEE, Consisting of Revised Chapter 4.0 Re Internal Fire Analysis 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 05000254/LER-1999-001-04, :on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance1999-05-12012 May 1999
- on 970715,three Spare Valves Were Determined to Require Monthly Verification in Accordance with TS SR 4.7.A.2.Caused by Inadequate Review of Procedure Rev. Surveillance Revised to Ensure to Continued Compliance
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 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 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 ML20205F4791999-03-31031 March 1999 Safety Evaluation Supporting Amends 187 & 184 to Licenses DPR-29 & DPR-30,respectively 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 ML20205D4171999-03-26026 March 1999 Safety Evaluation Supporting Amends 186 & 183 to Licenses DPR-29 & DPR-30,respectively ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20204D9751999-03-17017 March 1999 Safety Evaluation Supporting Amends 185 & 182 to Licenses DPR-29 & DPR-30,respectively 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 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 ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20198S6841998-12-22022 December 1998 Safety Evaluation Re Proposed Merger of Calenergy Co,Inc & Midamarican Energy Holdings Co.Nrc Should Approve Application with Listed Condition ML20196F8931998-12-0303 December 1998 Safety Evaluation Supporting Amend 182 to License DPR-29 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 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 ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 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 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-98-358, 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-98-346, 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 05000254/LER-1998-001-01, :on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation1998-10-27027 October 1998
- on 980105,EDG Failed to Start When Received Inadvertent Start Signal.Caused by Degraded Fuse Clip in EDG Control Power Circuit.Corrective Actions Have Included Training,Counseling,Component Testing & Evaluation
05000265/LER-1998-006-04, :on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-061998-10-15015 October 1998
- on 980918,Unit 2 Entered 12 H LCO to Hot Shutdown,Due to HPCI & RCIC Being Declared Inoperable.Caused by Inadequate Procedure Rev.Revised Procedure Qcis 0200-06
1999-09-30
[Table view] |
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TABEE OF CCtmNTS
'Page 3
REFERDCES....................................................... iii LIST OF FIGURES................................................. iv
- 1. 0 -
CONTROL ROD WIEDRAHAL BLOCK INETTRUMENTATION (3.2/4.2)....
is 1 1.1 Technical Specification Reference.................
1-1 1.7 Description........................................
1-1
- 2.0 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (3.5/4.5).....
2-1.
2.1' Technical Specification Reference.................
2 2.2
- Description.......................................
2-1 3.0 LINEAR HEAT GENERATION RAE (3.5/4.5)..................
3-1 3.1 Technical Specification Reference.................
3-1 3.2 Description 3-1 4.0 MINIMUM CRITICAL BOWER BATIO (3.5/4.5).................
4-1 4.1 Technical Specification Reference................. 4-1 4.2 Description....................................... 4-1 Quad Cities - Unit 2 11 Cycle 10
(-
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- Core Oper-ting Limits Report j
l 1
aErEaErcES 1..
Carmonwealth Edison Ccmpany and Iowa-Illinois Gas and Electric Campany Docket No. 50-265, Quad Cities Station, Unit 2 Facility
- Operating License, License No. DRP-30..
2.
Ietter from D. M. Crutchfield to All Power Reactor Licenses and Applicants, Generic letter 88-16; Concerning the Renoval of Cycle-Specific Parameter Limits frun Technical Specifications.
3.
Supplemental Reload License Subnittal for Quad Cities Nuclear Power Station, Unit 2, Reload 9 (Cycle 10), 23A5846, nev.~ 0, January 1988.
4.
Quad Cities Nuclear Power Station, Units 1 and 2, SAFER /GESTR-II)CA Loss-of-Coolant-Accident Analysis, NEDC-31345P, June 1987 (as amended).
5.
General Electric Standard Application for Reactor Fuel (GESTAR),
NEDE-24011-P-A, Septaber 1988 (as amended).
l Quad Cities - Unit 2 111 Cycle 10
" tore OperOting Limits Report i
u LIST OF FIGURES FIGURE TITLE / DESCRIPTION PAGE 2-l Maxima Average Planar Linear Heat Generation Rate 2-2 (MAPI1ER) vs. Average Planar Exposure for Fuel Type P8DGB263L.
2-2 Maximum Average Planar Linear Heat Generation Rate 2-3
~(MAP 11ER) vs. Average Planar Exposure for Fuel Type BP8DRB265H.
I' 2-3 Maximum Average Planar Linear Heat Generation Rate 2-4 (MAPIllGR) vs. Average Planar Exposure for Fuel Type BP8DRB283H.
2-4 Maximum Average Planar Linear Heat Gelreration Rate 2-5 (MAPI1ER) vs. Average Planar Exposure for Fuel Type BP8DRB282.
2-5 Maximum Average Planar Linear Heat Generation Rate 2-6 (MAPIIER) vs. Average Planar Exposure for Fuel Type P8DGB298.
2-6 Maxian Average Planar Linear Heat Generation Rate 2-7 l
(MAPIllGR) vs. Average Planar Exposure for Fuel Type BP8DRB299.
2-7 Maximum Average Planar Linear Heat Generation Rate 2-8 (MAPIllGR) vs. Average Planar Exposure for Fuel Type BP8DRB299L.
2-8 Maximum Average Plana. Linear Heat Generation Rate 2-9 (MAPIllGR) vs. Average !.'wiar Exposure for Fuel Type i
BD300C.
2-9 Maxian Average Planar Linear Heat Generation Rate 2-10 (MAPIJER) vs. Average Planar Exposure for Fuel Type BD316A.
4-1 Kf Factor vs. Core Flow %.
4-2 Quad Cities - Unit 2 iv Cycle 10
,.. : d ICore Oper:iting LimitsL Report '
j v.,
j l
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- 1. 0. ' C0tf1ML HOD WITHDRAHAL BIOCK INSTRLM2ffATION (3.2/4.2) 3 1
1,1-
'IECHNICAL SPECIFICATION REFERDCEs-Technical Specification Table 3.2-3 and 3.6.H
)
- 1. 2' DESCRIP1' ION:
l The Rod Withdrawl Block lenitor Upscale Instrumentation Trip,
Setpoint for two recirculation loop operation is determined from the following relationship:
< (0.65)Wd + 43%**
- Clanped, with an allowable value not to exceed the allowable value for recirculation loop ficw (Wd) of 100%.
Wd is the percent of drive flow required to produce a rated core flow of 98 million 1b/hr. Trip level setting is in percent of rated power (2511 Mwt).
l Quad Cities - Unit 2 1-1 tW. 1e 10
i
. Core Oper ting Limits Report l
f4 2.0 AVER /G PLANAR LUEAR HEAT GENEPATION RATE (APIEGR) (3.5/4.5) 2.1
'IECHNICAL SPECIFICATION REFEREtCE:
Technical Specification 3.5.I 2.2 DESCRIPI' ION:
'Ihe Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) versus Average Planar Exposure for fuel type P8DGB263L is determined from Figure 2-1.
The Maximum Average Planar Linear Heat Generation Rates (MAPIEGR) versus Average Planar Exposure for fuel type BP8DRB265H is determined from Figure 2-2.
The Maximum Average Planar Linear Heat Generation Rates (MAPLHGR) versus Average Planar Exposure for fuel type BP8DRB283H is determined fran Figure 2-3.
The Maximum Average Planar Linear Heat Generation Rates (MAPIJKEI) versus Average Planar Exposum for fuel type BP8DRB282 is determined fran Figure 2-4.
The Maximum Average Planar Linear Heat Generation Rates (MAPIRGR) versus Average Planar Exposure for fuel type P8DGB298 is determined fran Figure 2-5.
'Ihe Maximum Average Planar Linear Heat Generation Rates (MAPIRGR) versus Average Planar Exposure for fuel type BP8DRB299 is detennined fran Figure 2-6.
The Maximum Average Planar Linear Heat Generation Rates (MAPIRGR) versus Average Planar Exposure for fuel type BP8DRB299L is detenidned fran Figure 2-7.
The Maximum Average Planar Linear Heat Generation Rates (MAPIRGR) versus Average Planar Expusure for fuel type BD300C is determined fran Figure 2-8.
The Maxinum Average Planar Linear Heat Generation Rates (MAPIRGR) versus Average Planar Exposure for fuel type BD316A is determined fran Figure 2-9.
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3.0 - LINEAR HEAT GENERK120N RATE (IJER) (3.5/4.5) 3.1 TECHNICAL SPECIFICATION
REFERENCE:
Technical Specification 3.5.J
3.2 DESCRIPTION
a.
'Ihe' IJGR limit is 13.4 kw/ft for ' fuel types:
1.
P8DGB263L 2.
BP8DRB265H 3.
BP8DRB282 4.
BP8DRB283H 5.-
P8DGB298
- 6. 'BP8DRB299 7.
BP8DRB299L b.
The LHGR limit is 14.4 kw/ft for fuel types:
1.
BD300C 2.
BD316A Quad Cities - Unit 2 3-1 Cycle 10
-. "wre Oper: ting IJmits Report i e.; o
-i 4.0-MINIME CRITICAL POWER RATIO OCPR) (3.5/4.5)
L:..
'4.1 TECHNICAL SPECIFICATTOI
REFERENCE:
Technical Specification 3.5.K
4.2 DESCRIPTION
During steady-state operation at rated core flow, ICPR shall be greater than or equal:
1.30 for tave 5 0.68 sec.
1.35 for tave > 0.86 sec.
L (0.278)tave + 1.111 for 0.68 sec. 5 tave 5 0.86 sec, where tave = mean 20% scram insertion time for all surveillance data frun Tech. Spec. 4.3.C which has been generated l
in the current cycle For core flows other than rated, these nutinal values of ICPR shall be increased by a factor of Kf where FI is as shown in Figure 4-1.
Quad Cities - Unit 2 4-1 Cycle 10 l
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