Similar Documents at Byron |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20209B7411999-06-30030 June 1999 Proposed Tech Specs Section 3.8.5, DC Sources - Shutdown, Correcting LCO & Braidwood TS Section 3.8, Electrical Power Systems, Deleting Various References to At&T Batteries ML20211C3311999-04-30030 April 1999 Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood ML20204H9781999-03-23023 March 1999 Proposed Tech Specs,Revising Sections 3.7.15,3.7.16,4.3.1 & 4.3.3 to Support Installation of New Boral high-density SFP Storage Racks at Byron & Braidwood Stations ML20204H4291999-03-22022 March 1999 Proposed Tech Specs 3.9.3,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20202G9361999-01-30030 January 1999 Rev 1.4 to Chapter 10, Radioactive Effluent Treatment & Monitoring, Rev 1.6 to Chapter 11, Radiological Environ Program & Rev 1.6 to Chapter 12, Radioactive Effluent Technical Standards (Rets), for Odcm,Byron Annex ML20198N3471998-12-29029 December 1998 Proposed ITS Tables 3.3.1-1 & 3.3.2-1,revising Twelve Allowable Values ML20198N2041998-12-29029 December 1998 Revised Tech Specs Change,Page 3/4 3-54,providing Early Implementation of Containment Floor Drain Sump Water Level Instrumentation Requirements ML20198A0811998-12-14014 December 1998 Proposed Rev T to Improved Tech Specs Section 3.4, Reactor Coolant Sys ML20196G6611998-11-30030 November 1998 Proposed Rev to Improved Tech Specs Section 3.1 ML20155J2051998-11-0505 November 1998 Proposed TS Converting to Its,Rev R ML20155J0041998-10-30030 October 1998 Proposed Tech Specs Section 5.6.2, Fuel Storage Drainage, to Identify Sf Pool Level Sufficient to Ensure SRP Acceptance Criteria ML20154S5011998-10-18018 October 1998 Proposed Rev N to Improved TS Section 3.7 ML20154M5281998-10-15015 October 1998 Revisions K,O & P of 961213 ITS Submittal ML20154A8881998-10-0202 October 1998 Proposed Rev L to Improved Tech Specs Section 3.8 Closeout ML20153G4331998-09-25025 September 1998 Revs J & M to Tech Specs Sections 3.6 & 5.0,converting to Improved Tech Specs (Its),Final Closeout Package ML20236W5851998-07-31031 July 1998 Proposed Rev G to Sections 3.1 & 3.2 of Improved Tech Specs ML20237B6391998-07-30030 July 1998 Proposed Rev H to Section 3.5 of Improved Tech Specs ML20237E9971998-07-21021 July 1998 Rev I to Proposed Improved Tss,Section 3.9 Re Final Closeout ML20237B7021998-07-0909 July 1998 Proposed Improved TS (ITS) Section 3.3 Issued as Result of Removing Generic Change Traveler TSTF-135,Rev E from ITS Submittal ML20236H6531998-07-0202 July 1998 Rev F to 961213 Improved TS Submittal,Containing Final Package Closeout for Improved TS Sections 1.0,2.0 & 3.0 ML20248M1491998-06-0101 June 1998 Proposed Tech Specs Bases Page B 3.8-58b,converting to Improved Tech Specs ML20248K7361998-05-31031 May 1998 Commonwealth Edison Bnps Unit 1 Cycle 9 Startup Rept ML20248C5511998-05-29029 May 1998 Proposed Tech Specs Bases Section 3/4.4.4, Relief Valves, Specifically Crediting Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS at Power Accident ML20217Q8521998-05-0101 May 1998 Rev 9 to Bzp 310-2, Nuclear Accident Reporting Sys Form (Primary Responsibility - Station Director). W/Notes & Comments ML20216D9431998-04-0909 April 1998 Modified Proposed TS Pages Re 980324 Request for Amends to Licenses NPF-37 & NPF-66 ML20217E1891998-03-24024 March 1998 Proposed Tech Specs Surveillance Sections & Bases Allowing Util to Defer 10CFR50,App J,Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20217B2681998-02-14014 February 1998 Proposed Rev D to ITS ML20199J7581997-12-31031 December 1997 Rev 1 to IST Plan Pumps & Valves Byron Nuclear Generating Station,Units 1 & 2 ML20198C3181997-12-30030 December 1997 Proposed Tech Specs 3.7.1.3 Re Condensate Storage Tank ML20203M5921997-12-17017 December 1997 Proposed Tech Specs,Rev C Changes Improved TSs 3.0,3.3,3.7, 3.8 & 5.0 as Result of Removing Generic Change Traveler TSTF-115 from Improved TS Submittal ML20203D0361997-12-0909 December 1997 Proposed Tech Specs Pages Correcting Errors Discovered in Current TS W/Regards to Total RCS Volume & Correction to Increase in RCS Volume Associated W/Unit 1 Replacement SGs Accounting for Hot Conditions ML20199A4751997-11-0707 November 1997 Proposed Tech Specs Pages Revising TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.c & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20216H8241997-10-31031 October 1997 Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F ML20198M2621997-10-31031 October 1997 Revs to Offsite Dose Calculation Manual,Consisting of Rev 1.5 to Chapter 11 & Rev 1.5 to Chapter 12 ML20217K4461997-10-21021 October 1997 Proposed Tech Specs Re Boron Credit in SFP ML20202F4561997-10-10010 October 1997 Proposed Tech Specs,Deleting Lower Flow Rate Requirement Associated W/Nonaccessible Area Exhaust Filter Plenum & Fuel Handling Bldg Ventilation Sys ML20211D9421997-09-24024 September 1997 Proposed Tech Specs Revising Allowable Time Interval for Performing Turbine Throttle Valve & Turbine Valve SRs Requirements from Monthly to Quarterly ML20216G8541997-09-0808 September 1997 Proposed Tech Specs Change to TS 4.5.2.b & Associated Bases Bringing Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20217H6071997-08-0707 August 1997 Proposed Tech Specs Pages,Revising Bases for Proposed Improved TS SR 3.8.6.1 & 3.8.6.3,to Indicate That Correction for Level Is Not Required When Battery Charging Current Is Less than 2 Amps for Gould & Less than 3 Amps for C&D ML20148P7721997-06-30030 June 1997 Proposed Tech Specs,Revising TS 3.9.11,5.6.1.1 & 6.9.10 to Allow Util to Permanently Take Credit for Soluble B in Spent Fuel Storage Pool Water to Maintain Acceptable Margin of Subcriticality ML20141F3081997-06-24024 June 1997 Proposed Tech Specs,Changing TS for ECCS Venting ML20141B7781997-06-17017 June 1997 Proposed Tech Specs Revising TS Sections 3/4.6.1.6,4.6.1.2, 6.8.4 & 6.9.1.11 to Support New Requirements in 10CFR50.55a, Which Requires Utils to Update Existing Containment Vessel Structural Integrity Programs ML20148J3231997-06-0909 June 1997 Proposed TS Reflecting Latest Rev of Waste Gas Decay Tank Rupture Accident Dose Calculation ML20140D0081997-05-31031 May 1997 Proposed Tech Specs,Revising TS Surveillance Requirement Re ECCS Pump Casings & Discharge Piping High Points Outside of Containment ML20141K8991997-05-24024 May 1997 Proposed Tech Specs Revising TS Surveillance Requirement 4.5.2.b to Encompass non-operating ECCS Pumps & Discharge Piping Which Are Provided W/High Point Vent Valves ML20141K3381997-05-23023 May 1997 Proposed Tech Specs Requesting Enforcement Discretion from Compliance W/Ts 4.5.2.b.1 Requirements of Venting of Emergency Core Cooling Sys Pump Casings & Discharge Piping High Points Outside of Containment ML20141K0011997-05-21021 May 1997 Proposed Tech Specs Relocating Reactor Vessel Surveillance Program Capsule Withdrawal Schedules IAW GL 91-01 ML20148B6151997-05-0606 May 1997 Proposed Tech Specs,Revising TS 3/4.7.5, Ultimate Heat Sink & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20196G0501997-04-25025 April 1997 Proposed Tech Specs Revising Primary Containment & Reactor Coolant Sys Volume Associated W/Unit 1 Steam Generator Replacement ML20137S5341997-04-0707 April 1997 Proposed Tech Specs 3/4.8.2 Re D.C. Sources 1999-06-30
[Table view] Category:TEST REPORT
MONTHYEARML20248K7361998-05-31031 May 1998 Commonwealth Edison Bnps Unit 1 Cycle 9 Startup Rept ML20086R5071995-07-31031 July 1995 Indications Restrained from Burst (Ibrs) Summary Leak Test Rept ML20086S7751995-07-28028 July 1995 Table 2-10 Summary of Test Dimensional Measurement Results ML20059J2091994-01-21021 January 1994 Reactor Primary Containment Bldg Ilrt,Byron Nuclear Station Unit 2,930909-10 ML20211H1141986-07-18018 July 1986 Reactor Containment Bldg Integrated Leakage Rate Test for Byron Unit 2,Preoperational Test on 860702-18 ML20205M2411985-10-25025 October 1985 Commonwealth Edison Co,Byron Unit 1,Cycle 1,Startup Rept ML20133N0211985-08-27027 August 1985 Electrical Cable Separation Verification Testing ML20129C0161985-05-24024 May 1985 Summary Rept of Preliminary Ultrasonic Exams on Byron Unit 2 Steam Generators & Pressurizer ML20129C0481985-05-24024 May 1985 Summary of Repair Methodology of Ultrasonic Testing Indications in Byron Unit 1 Steam Generator Shell Welds ML20137Z8271984-11-30030 November 1984 Nuclear Component Qualification Test Rept Square D 9025-BCW-45 Thermal Switch ML20093J0821984-10-10010 October 1984 I-130 Removal Efficiency Determination of Adsorbent Samples ML20098F5441984-09-30030 September 1984 Rev 0 to Evaluation of Tests Performed on Energy Absorbing Matl for Pipe Whip Restraints ML20094G7451984-04-30030 April 1984 Rev 1 to Evaluation of Energy Absorbing Matl for Pipe Whip Restraints ML20087N3181984-03-26026 March 1984 Reactor Containment Bldg Integrated Leakrate Test, Conducted 830902-26 ML20129C0791983-12-31031 December 1983 Metallurgical Investigation of Recorded Ultrasonic Indications in Steam Generator Stub Barrel to Lower Shell Weld at Byron 1 Station ML20134D3611983-08-30030 August 1983 Preoperational Test 2.58.11:Integrated Leak Rate Test ML20078C3911983-04-22022 April 1983 Transco Test Rept TR-110, Fire & Hose Stream Tests of TCO-003 High Density Silicone Elastomer ML20078C4031983-04-20020 April 1983 Transco Test Rept TR-111, Fire & Hose Steam Tests of TCO-002 Medium Density Silicone Elastomer ML20072L3551981-10-27027 October 1981 Vol 2 to Nuclear Environ Qualification Program on Lead Acid Storage Batteries ML20072L3531981-10-27027 October 1981 Vol 1 to Nuclear Environ Qualification Program on Lead Acid Storage Batteries ML20072L3601981-05-15015 May 1981 Seismic Simulation Test Rept ML20095F5201975-08-11011 August 1975 Rept of Field Compaction Tests ML20095F5111975-07-22022 July 1975 Rept of Field Compaction Tests ML20095F4731975-06-20020 June 1975 Rept of Field Compaction Tests ML20095F4381975-05-30030 May 1975 Field Density Test Results 1998-05-31
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L LUOF IELD COMPACTION TESTS CLIENT' : COMMONWEALTH EDISON COMPANY REPORT NO. 81 PROJECT '
- BYRON NUCLEAR POWER STATION, PRELIMINARY DATE 7/22/75
. SITE WORK, UNITS #1 6 2, P.O. #160890-SCD-84 TEST DATA: "
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In Place Soil ID Lab Dry ; W/C Dry 5 Comp. Co==ents !
{[D. { Date Elevation Number Density Density j t -Z' Below ,
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1 7/22/75 Grade 867 10 129.3 11.4*3 126.9 98.1% 2 A/S
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' 2' 7/22/75 Grade 867 10 129.3 11.4% 125.3 96.9% 2 A/S I
below e 3 7/22/75 Grade 867 10 129.3 i 10.8% 125.7 97.2% 2 A/S i
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'5' 7/22/75 Grade 867 1 130.1 10.5% 126.7 97.4%. 2 A/S I
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!6 7/22/75 Grade S67 78 122.8 12.6% 118.5 96.5% 2 A/S !
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1 Switchyard. 32+05N 5 31+70E, Lift Thickness 6"
- l. 2 Switchyard, 30+50N S 30+00E, Lift Thickness 6" l
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'5 S.<itchyard, 35+60N 5 2S+15E, Lift Thickness 6" l
[6 Switchyard,31+65E S 38+05N, Lift Thickness 6" t3TES:
A. TEST RESULTS COMPLY CZNSITIES SHOVN: Lbs./Ft. *
! V.ATER CCNTENT : 5 of Dry Density 2. BACKFILL 8. RECOMPACTION REQUIRED t COMPACTION : Eased on Maximum Dry C. TEST IS AFTER RECOMPACTION Density obtained on Sample 3. BASE COURSE N. NUCLEAR METHOD indicated by Soil ID number 4. SUBBASE D. RUBBER BALLOON FETHOD S. SAND CCNE FETHOD 8408270292 840810 * '
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-m.n CLIENT :_ COMv0NWEALTH EDISON COf/PANY REPORT NO. 81 '9
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PROJECT: -: - BYRON NUCLEAR POWER STATION, PRELIMINARY DATE '7/22/75' SITE h'ORK, UNITS #1 6 2, P.O. #160890-SCD-84 ,t TEST DATA:
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".u imun ! In Place
!?e st '. Soil ID Lab Dry j W/C Dry % Corp. Co==ents No. Date '
Elevation IIumber Density Density
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-l7'N 7/22/75 Grade 867 -
78 122.8 11. 8'; 118.0 06 9e ? Als
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TEST LOCATION:
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NOTES: A. TEST RESULTS COMPLY
- 1. EMBANKtENT (FILL) WITH SPECIFICATICNS DENSITIES SHOWN: Lbs./Ft.3 * ' A I D WATER CONTENT : % of Dry Density 2. BACKFILL A
. RECOMPACTION
% COMPACTION : Eased on Maximum Dry
- 3. BASE COURS._t N. NUCLEAR METHOD -
Density obtained on Sample .
indicated by Soil ID nu=ber i+. SUBBASE
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