ML19350A690
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| ML19350A690 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/02/1981 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19350A688 | List: |
| References | |
| NUDOCS 8103160666 | |
| Download: ML19350A690 (1) | |
Similar Documents at Quad Cities | |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999
[Table view]NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 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 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 ML20216C0561998-04-30030 April 1998 Safe Shutdown Rept for Quad Cities Station,Units 1 & 2, Vols 1 & 2.W/22 Oversize Figures 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 ML20217G3641998-03-0909 March 1998 TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 1 TS (Safety-Related) Snubber Population 118 Snubbers ML20113C9131996-06-28028 June 1996 NRC USI A-46 Resolution Seismic Evaluation Rept Quad Cities Nuclear Station Units 1 & 2 ML20113C9221996-06-28028 June 1996 A-46 Relay Evaluation Rept for Quad Cites Nuclear Power Station Units 1 & 2 ML20101P0981996-03-28028 March 1996 Core Spray Flaw Evaluation Rept B130172, Safety Evaluation for Quad Cities Unit 1 Core Spray Line Repair1996-01-31031 January 1996 Safety Evaluation for Quad Cities Unit 1 Core Spray Line Repair ML20083L5311995-05-0404 May 1995 Evaluation of Acceptability of Fddr 1E6AR-FDDR-001 for Shroud Repair Program at Quad Cities Unit 2 ML20083K9321995-04-10010 April 1995 Core Shroud Repair,Design Reliant Structures Insp Requirements & Acceptance Criteria ML20081C2891995-03-31031 March 1995 Simulator Four Yr Certification Rept,Mar 1995 ML20081A7461995-03-31031 March 1995 First Quad Cities Station Course of Action Progress Rept ML20078S2841995-02-14014 February 1995 Flaw Tolerance Evaluation Quad Cities Units 1 & 2 Feedwater Nozzles, ML20078D8431995-01-0707 January 1995 Reactor Pressure Vessel ML20078D8531995-01-0707 January 1995 Shroud Stabilizer ML20078D8401995-01-0707 January 1995 Shroud Stabilizer Hardware ML20078D8511995-01-0606 January 1995 Fabrication of Shroud Stabilizer ML20086A3001994-10-31031 October 1994 Reactor Bldg Crane & Cask Yoke Assembly Mods ML20078C6131994-10-21021 October 1994 Foreign Matl Exclusion Program Deficiencies Level 2 Investigation PIF 94-1837 ML20065L2221994-04-14014 April 1994 Course of Action ML20155A6881993-09-30030 September 1993 Evaluation of Min Post-LOCA Heat Removal Requirements to Assure Adequate NPSH for Core Spray & Lpci/Containment Cooling Pumps ML20056F8891993-08-23023 August 1993 Rev 1 to COE-301-200, Evaluation & Disposition of IGSCC- Susceptible Welding at Quad Cities Nuclear Power Station Unit 2 1993 Outage ML20073A2141991-03-31031 March 1991 Bellows Expansion Joint Design Evaluation Drywell Penetration X-25,Quad Cities Nuclear Power Station,Unit 1 ML20073A2281991-03-31031 March 1991 Rev 0 to Evaluation of Quad Cities Penetration Bellows Assemblies Leakage Rates ML20082A6931991-03-31031 March 1991 Structural Evaluation of Com Ed BWR Reactor Pressure Vessel Head Stud Cracking ML20070S8901991-03-19019 March 1991 Simulator Initial Certification Rept,Mar 1991, Vols 1 & 2 ML20029A0591990-11-21021 November 1990 Feedwater Line Thermal Hydraulic Behavior During LOCA Conditions for Quad-Cities Nuclear Power Station. ML20083A0831990-03-31031 March 1990 Draft 137-0010,rev 2 to Vessel Fatigue Evaluation Considering Revised Thermal Cycles for Quad Cities Nuclear Station Units 1 & 2 ML19332E6701989-10-26026 October 1989 Rev 1 to Vessel Fatigue Evaluation Considering Revised Thermal Cycles for Quad Cities Nuclear Station,Units 1 & 2. ML20245E8011989-07-13013 July 1989 Applicability of Pipelocks as Remedy for IGSCC in Bwrs ML20245E7971989-03-31031 March 1989 Rev 1 to Hydrogen Water Chemistry Installation Compliance W/Epri Guidelines for Permanent BWR Hydrogen Water Chemistry Installations Sept 1987 Rev ML20246F6371989-03-0303 March 1989 Rev 1 to Hydrogen Water Chemistry Installation Rept for Amend to Facility Ol ML20207H2491988-07-20020 July 1988 Metallurgical Analysis of End Cap-to-Header Weld Overlay Boat Samples from Quad Cities Station Unit 2 ML20151G2881988-07-0505 July 1988 Evaluation of End Cap Weld 02A-S10 Weld Overlay Repair Considering Ultrasonic Insp Findings During 1988 Outage ML20151G2931988-06-30030 June 1988 Design Rept for Recirculation & Rwcs Evaluations & Repairs Performed During 1988 Refueling Outage at Quad Cities Nuclear Power Plant Unit 2, Vol 2 ML20155C0571988-05-31031 May 1988 Rev 1 to Evaluation & Disposition of Flaws at Quad Cities Nuclear Power Plant Unit 1 (1987 Outage) ML20155A6111988-05-31031 May 1988 Rev 1,Vol 1 to, Design Rept for Recirculation & RWCU Sys Evaluations & Repairs Performed During 1988 Refueling Outage at Quad Cities Nuclear Power Plant Unit 2 ML20155C0521988-05-16016 May 1988 Hydrogen Water Chemistry Installation Rept for Amend to Facility Ol ML20237A6391987-12-0909 December 1987 Evaluation & Disposition of Flaws at Quad Cities Nuclear Power Plant Unit 1 (1987 Outage) ML20237A6141987-12-0404 December 1987 Summary Rept Re Ultrasonic Exam Performed During Fall 1987 Refueling Outage Quad Cities Unit 1 ML20236W6231987-11-24024 November 1987 Revised Interim Fracture Mechanics Analysis,Welds 02BS-S5 & 02BS-S9 ML20155C0631987-09-30030 September 1987 Hydrogen Water Chemistry Installation Compliance W/Epri Guidelines for Permanent BWR Hydrogen Water Chemistry Installations ML20237G1621987-08-31031 August 1987 Dcrdr Suppl 2 - Summary Rept ML20236A9121987-06-30030 June 1987 Criticality Safety Evaluation of Boraflex Degradation in Quad Cities Spent Fuel Storage Racks ML20236A9291987-05-28028 May 1987 Assessment of Boraflex Gap Distributions in Quad Cities Spent Fuel Storage Racks 1999-09-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217A9931999-09-30030 September 1999
[Table view]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 |
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l SPECIAL TEST l-46 Unit One End of Cycle 5 Fuel Test Program i Test Description j This test was similar to those performed on Unit One fuel during previous refueling outages. The test documentation included a detailed test schedule, and appropriate generic procedures utilized by General Electric Company. Test performed included the following:
I
- 1. Visual and special NDT performed on selected fuel.
- 2. Gamma scanning on selected bundles and individual fuel rods.
- - 3 Visual insp$ction and measurements performed on selected fuel J
bundle channels.
- 4. H02 Bundle investigations and re-work.
5 Anodized channel installation.
Summary of Safety Evaluation All fuel handling was performed within the confines of the spent fuel storage pool using standard, reviewed, and approved fuel handling procedures. -All fuel maneuvers were standard cperations, such as bundle transfers between racks, dechanneling, and channeling. These activities did not create accident potentials greater than the dropped fuel bundle accident described in the FSAR. No activities would cause release rates greater than those given by the Technical Specification bases.
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