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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,, ATTACHMENT I i SUMARY OF REPAIR METHODOLOGY OF UT INDICATIONS' IN BYRON UNIT 1 STEAM GENERATOR SHELL WELDS I. STEAM GENERATOR SERIAL #CBGT-1731 Indication No. Ebasco Def. No. Location Weld Seam 1 D-147 95.25" CW SGC-06 2 D-148 113.0" CW SGC-06 -
3 D-160 - 69J5",CCW- SGC-06
- r. .
A brief synopsis of the removal / repair process is as follows:
- 1. A reference point was established from which to work.
2 U.T. examined for wall thickness and compared to minimum wall thickness requirements. -
3 ~ Removed indications by grinding. ,
- 4. M.T. and U.T. examined groundout areas to ensure complete removal.
- 5. Recorded length, width and depth of. grind out these were: _.
Indication No. Length Width Depth 1 8" 1.15" 3.0" 2 8.75" 2.0" 3.75" 3 8.75" 1.81 " 3.0" -
- 6. Cleaned repair area. Installed thermocouples and preheat elements.
- 7. Preheat: Maintained preheat to 250 degrees F min.-500 degrees F. max.
. 8. Perfom weld repair using E9018, SMAW process, Heat #32230
- 9. Perfom M.T. and U.T. Examination.
- 10. Attach Thermocouples and PWHT Elements.
i
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. k77ACHMENT $ CON T! n .
s l
- 11. Performed PWT at a maximum heating rate of 100 degrees F. per hour; maximum cooling rate of 100 degrees F per hour; soaking ,
I temperature: 11/25 degrees F. (plus/minus 25 degrees F.) hours i at soaking temperature: 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 45 minutes. l
- l
- 12. After PWT: ,
l A. MT examined repaired areas and thermocouple removal areas.
B. UT examined repaired areas to ensure defect removal.
C. UT examined for wall thickness.
Note: A completed 2033 form (ASME Section XI) was submitted to Ceco after Hydrostatic Test was completed ~ on 1/3/84.
II. STEAM GENERATOR SERIAL #CBGT-1732 Indication No. Ebasco Def. No. Location Wel d Seam -
4 1 D-139 93" CCW SGC-03 2 D-144 113" CCW SGC-03 The repair was accomplished by machining a 5.0" diameter and a 2.5" diameter ope; sing with bolted cover plates. The 5.0" diameter ,
opening received a weld pad build-up of 13" diameter and approxi- !
mately)2.25" 5.087 . thick (machined to 10.50" diameter and minimum wall A brief synopsis of the removal / repair is as follows:
- 1. Preheat: maintained preheat to 250 degrees F. min.-
500 degrees F. maximum.
- 2. Preheat and welded with E9018, SMAW process, Heat #32230 and 48409.
- 3. M.T. examined each 1/2 inch of deposited weld metal .
- 4. Checked minimum pad thickness.
- 5. Manually ground surfaces of the pad to an acceptable finish for U.T.
- 6. M.T. examined final finish.
- 7. U.T. examined for. acceptance to minimum pad thickness.
M.T. examined for indication, if any, removal .
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,,..' Ar,xcitstear 8 con r io
- 8. Attached thermocouples and PWT elements. I
- 9. Heat treated as foll ows:
A. Heat uniformly at any rate up to 800. Degrees F'
-B. Above 800 Degrees F heat unifornly at 100 Degrees F. per hour maximum to 1125 Degrees F. (+/-) 25 Degrees F.
C. Held at 1125 Degrees F. (+/-) 25 Degrees F. for 2-1/2 Hours. 1 D. Cooled uniformly to 800 Degrees F. at a maximum rate of '
100 Degrees F. per hour, thereafter steam generator.my cool to ambient.
- 10. Removed thermocouples and PWT elements.
- 11. M.T. examined removal areas.
-12. M.T. examined weld pad build-up.
- 13. U.T. examined weld pad build-up.
- 14. Finish machining finishes and spot facing of bolt holes.
- 15. Performed M.T. examination of finished machine work. -
Note: A completed 2033 form (Section XI) was submitted to CECO .>
after hydrostatic test was completed on 1/3/84.
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, 0h ATTACHMENT III I
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