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Category:ANNUAL OPERATING REPORT
MONTHYEARML20206B4001998-12-31031 December 1998
Annual & 30-Day Rept of ECCS Evaluation Model Changes & Errors for Byron & Braidwood Stations
ML20196K6731998-12-31031 December 1998
10CFR50.59 Summary Rept for 1998
ML20198A0151998-06-18018 June 1998
10CFR50.59 Summary Rept 960619 Through 980618, Vols I & Ii,Consisting of Descriptions & SE Summaries for Changes to Procedural UFSAR Changes,Tests & Experiments & FP Rept.Without Fp,Rept
ML20217G6011997-12-31031 December 1997
Annual Rept for 1997 for Units 1 & 2 of Braidwood & Byron Nuclear Power Stations
ML20132D0301996-06-18018 June 1996
Station,10CFR50.59 Summary Rept 940619-960618
ML20126C5891992-12-31031 December 1992
10CFR50.59 Annual Rept for 1992
ML20090J9101991-12-31031 December 1991
Annual 10CFR50.59 Rept 1991
ML20101F1431991-12-31031 December 1991
Annual Rept for Braidwood Nuclear Power Station for June - Dec 1991
ML20099A6971991-07-25025 July 1991
10CFR50.46 Margin Utilization Byron & Braidwood Station, Units 1 & 2, Constituting Annual Rept of Results of ECCS Evaluation Models for Period Ending 910725
ML20079K5491991-06-18018 June 1991
10CFR50.59 Annual Rept 1990-1991
ML20058B1821989-12-31031 December 1989
10CFR50.59 Annual Rept 1989
ML20012B5491989-12-31031 December 1989
Annual 10CFR50.59 Rept 1989. W/900227 Ltr
ML19325D4981989-10-12012 October 1989
10CFR50.59 Annual Rept. W/ 891012 Ltr
ML20236D8481988-12-31031 December 1988
Annual 10CFR50.59 Rept 1988
ML20248C1521988-12-31031 December 1988
Annual 10CFR50.59 Rept-Suppl,1988
ML20207N4391988-12-31031 December 1988
10CFR50.59 Annual Rept 1988
ML20149M4671987-12-31031 December 1987
Initial Annual Operating Rept for 1987,submitted Prior to Mar 1 of Yr Following Initial Criticality.Recorded Whole Body Exposure for CY87 Indicated No Individual Received Exposure of 100 Mrem or Greater
ML20236Q1171987-10-14014 October 1987
Annual 10CFR50.59 Rept,Based on 861017 Fuel Load License NPF-59,of Descriptions & Safety Evaluations for Changes to Facility as Described in SAR
ML20212H2491985-12-31031 December 1985
Errata,Consisting of Missing Pages 5 & 6,to 1985 Annual Operating Rept
ML20207K5981985-12-31031 December 1985
Addendum for Part 3 of 1985 Annual Operating Rept,Indicating Results of Environ Radiological & Meteorological Monitoring
1998-06-18
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20217G9961999-10-14014 October 1999
SER Accepting First 10-year Interval Inservice Insp Requests for Relief for Plant,Units 1 &
BW990066, Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With1999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Braidwood Station, Units 1 & 2.With
ML20217H5221999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Byron Station, Units 1 & 2.With
ML20217P6351999-09-29029 September 1999
Non-proprietary Rev 6 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations
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
ML20212A7441999-09-10010 September 1999
Safety Evaluation Concluding That Alternatives Contained in Relief Request 12R-07 Provide Acceptable Level of Quality & Safety
ML20212B9261999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Byron Station,Units 1 & 2.With
BW990056, Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With1999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Braidwood Station, Units 1 & 2.With
ML20210R6421999-08-13013 August 1999
ISI Outage Rept for A2R07
ML20210U8111999-08-0404 August 1999
SER Granting Licensee Relief Requests VR-1,VR-3 & Portion of VR-2 Pursuant to 10CFR50.55a(a)(3)(ii).Relief Request VR-4 Does Not Require Explicit NRC Approval Because Relief Applies to Valves Not Required by 10CFR50.55a
BW990048, Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With1999-07-31031 July 1999
Monthly Operating Repts for Jul 1999 for Braidwood Station, Units 1 & 2.With
ML20210R3431999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Byron Station, Units 1 & 2.With
ML20210K9861999-07-30030 July 1999
Safety Evaluation Accepting Licensee 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs
ML20210E2251999-07-21021 July 1999
B1R09 ISI Summary Rept Spring 1999 Outage, 980309-990424
M990002, Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function1999-07-12012 July 1999
Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function
ML20216D3841999-07-12012 July 1999
Revised NFM9900022, Braidwood Unit 2 Cycle 8 COLR in ITS Format & W(Z) Function
ML20209G1751999-07-0808 July 1999
SG Eddy Current Insp Rept,Cycle 9 Refueling Outage (B1R09)
BW990038, Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With1999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Braidwood Station, Units 1 & 2.With
ML20207H7771999-06-30030 June 1999
Rev 0 to WCAP-15177, Evaluation of Pressurized Thermal Shock for Byron,Unit 2
ML20207H7851999-06-30030 June 1999
Rev 0 to WCAP-15183, Commonwealth Edison Co Byron,Unit 1 Surveillance Program Credibility Evaluation
ML20207H7941999-06-30030 June 1999
Rev 0 to WCAP-15180, Commonwealth Edison Co Byron,Unit 2 Surveillance Program Credibility Evaluation
ML20207H8071999-06-30030 June 1999
Rev 0 to WCAP-15178, Byron Unit 2 Heatup & Cooldowm Limit Curves for Normal Operations
ML20209H3711999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Byron Station, Units 1 & 2.With
ML20207H7561999-06-28028 June 1999
Pressure Temp Limits Rept (Ptlr)
ML20207H7621999-06-28028 June 1999
Pressure Temp Limits Rept (Ptlr)
BW990029, Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With1999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Braidwood Stations, Units 1 & 2.With
ML20209H7481999-05-31031 May 1999
Revised Monthly Operating Repts for May 1999 for Braidwood Station,Units 1 & 2
ML20195J8001999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Byron Station,Units 1 & 2.With
ML20207B6481999-05-25025 May 1999
SER Accepting Revised SGTR Analysis for Byron & Braidwood Stations.Revised Analysis Was Submitted to Support SG Replacement at Unit 1 of Each Station
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
ML20206R6991999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Byron Station Units 1 & 2.With
BW990021, Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With1999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Braidwood Station, Units 1 & 2.With
ML20195C7961999-04-28028 April 1999
Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)
M980023, Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)1999-04-28028 April 1999
Rev 2 to NFM9800233, Byron Station Unit 2 COLR for Cycle 8A (BY2C8A)
BW990016, Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With1999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Braidwood Generating Station,Units 1 & 2.With
ML20205P7001999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Byron Station,Units 1 & 2.With
ML20205B5091999-03-26026 March 1999
SER Accepting Relief Requests 12R-24,Rev 0 & 12R-34,Rev 0, Related to Second 10-year Interval Inservice Insp for Byron Station,Units 1 & 2
ML20205C5101999-03-21021 March 1999
Revised Safety Evaluation Supporting Improved TS Amends Issued by NRC on 981222 to FOLs NPF-37,NPF-66,NPF-72 & NPF-77.Revised Pages Include Editorial Corrections
ML20204G3831999-03-19019 March 1999
Safety Evaluation Accepting Second 10-yr Interval ISI Request for Relief 12R-11
ML20206A8831999-03-17017 March 1999
Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function
M990004, Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function1999-03-17017 March 1999
Rev 0 to NFM9900043, Byron Unit 1,Cycle 10 COLR in ITS Format W(Z) Function
ML20196A0721999-03-16016 March 1999
Cycle 8 COLR in ITS Format & W(Z) Function
ML20207M9231999-03-12012 March 1999
Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results
ML20207J4371999-03-0808 March 1999
ISI Outage Rept for A1R07
ML20204H9941999-03-0303 March 1999
Non-proprietary Rev 4 to HI-982083, Licensing Rept for Spent Fuel Rack Installation at Byron & Braidwood Nuclear Stations
BW990010, Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With1999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Braidwood Generating Station,Units 1 & 2.With
ML20204C7671999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Byron Station,Units 1 & 2.With
ML20206U9011999-02-15015 February 1999
COLR for Braidwood Unit 2 Cycle 7. Page 1 0f 13 of Incoming Submittal Was Not Included
BW990004, Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With1999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Braidwood Generating Station,Units 1 & 2.With
ML20199G8271998-12-31031 December 1998
Rev 1 Comm Ed Byron Nuclear Power Station,Unit 1 Cycle 9 Startup Rept
1999-09-30
[Table view] |
Text
'
ATTACHMENT 1 10CFR50.46 -
MARGIN UTLIZIATION BYRON AND BRAIDWOOD STATION UNITS 1 and 2
=. .. . . .. - .. - ~-
ATTACHMENT 1
~**
BYRON 1 LARGE BREAK LOCA 10CF.30.46 MARGIN UTILIZATION Page 1 of 5 PLANT NAME: B1R0lLSIAII0tLUHIL1 UTILITY NAME: COMMONWEALTH EDISON A. ANALYSIS OF RECORD PCT. 18B3107'F (Comments: Calc-Note No.__SEC-SAll-3152-CD Evaluation Model: BASH __, FQT.2.50_, FdH.ldS.
SGTP . 15 1., Other: )
B. PRIOR LOCA MODEL ASSESSMENTS --1989 .
APCT. + 0'F (Permanent Assessment of PCT Margin - Letter #: CAE-90-314 1 C. nRIOR LOCA MODEL ASSESSMENTS - 1990 APCT. + 0*F (Permanent Assessment of PCT Margin - Letter #: CAE-91-135 )
D. -CURRENT LOCA MODEL ASSESSMENTS - 06/1991 (Permanent Assessment of PCT Margin)
- 1. FUEL ROD INITIAL CONDITION INCONSISTENCY APCT. + _LO'F
- 2. LB-LOCA BURST & BLOCKAGE ASSUMPTION APCT. + 0*F
- 3. SG TUBE SEISMIC /LOCA ASSUMPTION APCT. + 7,2*F E. 10CFR50.59 SAFETY EVALUATIONS - (Permanent Assessment of PCT Margin)
- 1. Letter: NOTE 1 Issue: ERLOR TO 1990 APCT. + 1*F 2, Letter: Issue: APCT. 'F F. OTHER. MARGIN ALLOCATIONS-(Temporary Use of PCT Margin):
- 1. ANALYSIS MARGINS USED: VANTAGE 5 TRANSIUQN (NOTE 21 APCT. + 50*F i 2. PLANT:MAPGINS USED: N/A APCT. *F
- 3. FUEL MARGINS USED: LB-LQCA_P_0HELDIST. G0lL3)_ APCT._t___100*F LICENSING BASIS PCT + MARGIN ALLOCATION APCT. 2051.3*F
-Hotal:
/ -- _1 . This penalty resulted from an evaluation of the containment mini-purge valve as' discussed in UFSAR Sect. 6.2.1.5.
- 2. The transition core penalty for 17x17 Vantage 5 fuel is addressed in NCAP 10444-P-A.
3-. A temporary PCT penalty of 100*F was applied beginning in August 1990 to bound the potential PCT impact associated with the adequacy of the assumed
. power shape (chopped cosine) for the LBLOCA initial condition.
l L
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ATTACHMENT 1 BRAIDHOOD 1 LARGE BREAK LOCA
-10CFR50.46 MARGIN UTILIZATION Page 2 of 5 PLANT NAME: BRAIDB000_SIAIl0tLUNIT 1 UTILITY NAME: COBM0MEALIB_ EDISON A. - ANALYSIS OF RECORD PCT.__lBB1102*F (Comments: Calc-Note No._ SEC-SA11 3151-C0 Evaluation Model: BASH , FQT.L30_, FdH.L15, SGTP . 15 %, Other: )
B. PRIOR LOCA MODEL ASSESSMENTS-- 1989 APCT. + 0'F .
(Permanent Assessment of PCT Margin - Letter #: CAE SD:314 1 aPCT. + 0*F C, PRIOR LOCA MODEL ASSESSMENTS -_1990 (Permanent Assessment of PCT Margin-- Letter #: CAE 21 J35 )
D. CURRENT LOCA MODEL ASSESSMENTS - 06/1991 (Permanent Assessment of PCT Margin)
- 1. FUEL R0D INITIAL CONDITION. INCONSISTENCY APCT. + 10*F
- 2. 'LB-LOCA BURST & BLOCKAGE ASSUMPTION APCT. + 0*F
- 3. SG TUBE SEISMIC /LOCA ASSUMPTION APCT. + 7.2*F E. 10CFR50.59 SAFETY EVALUATIONS _(Permanent Assessment of PCT Margin)
- 1. Letter: MQIE 1 Issue: f3LQR_IQ_1920 APCT. + 1*F
- 2. Letter: SECL-91-188D Issue: MISSING GRIQ_EIECE APCT. + 17'F F. OTHER MARGIN ALLOCATIONS (Temporary Use of PCT Margin):
- 1. ANALYSIS MARGINS USED: VANTAGE S TRANSIIloti._OLOIE_21 APCT._t SD*F
- 2. PLANT MARGINS USED: N/A APCT. ___ F
- 3. FUEL MARGINS USED: LB LOCA POWER DISTR. (NOTE 3) APCT. + 100*F LICENSING BASIS PCT + MARGIN ALLOCATION APCT= 2068.3*F.
Notes' L 1. This penalty resulted from an evaluation of the containment mini-purge valve as discussed in UFSAR Sect. 6.2.1.5.
'2. .The transition core penalty for 17x17 Vantage 5 fuel is addressed in HCAP'10444-P-A.
- 3. A temporary PCT penalty of 100*F was applied beginning in August 1990 to bound'the potential PCT impact associated with the adequacy of the assumed; power shape (chopped cosine) for the.LBLOCA initial condition.
i.
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. .=-
ATTACHMENT 1 BYRON 2/BRAIDH000 2 LARGE BREAK LOCA 10CFR50.46 MARGIN UTILIZATION Page 3 of 5 PLANT NAME: SYAON_SIAIION_VNIllLERAI DH00DESIAIIONJLNIll UTILITY NAME: COMMONNEALTH EDISON i
A. ~ ANALYSIS OF RECORD PCT.__lBH110Z*F (Comments: _Cale-Note No. SEC-SAII:1157-C0 Evaluation Model: RASH , FQT.L._5Q_, FdH.lt63, SGTP ._15__%, Other: )
B. PRIOR LOCA MODEL ASSESSMENTS - 1989- APCT. + 0*F (Permanent Assessment of PCT Margin - Letter #: CAE-9.0-J14/CCE-9.0-3091 C. PRIOR LOCA MODEL ASSESSMENTS - 1990 APCT. + 0*F (Permanent Assessment of PCT Margin - Letter #: C&E-91-131/CCE-91-13hl D. CURRENT LOCA MODEL ASSESSMENTS - 06/1991 (Permanent Assessment of: PCT Margin)
- 1. FUEL ROD INITIAL CONDITION INCONSISTENCY APCT= + IQ'F
- 2. LB-LOCA BURST & BLOCKAGE _ ASSUMPTION APCT. + 0'F
- 3. SG TUBE SEISMIC /LOCA ASSUMPTION APCT. + 20'F E. 10CFR50.59 SAFETY EVALUATIONS - (Permanent Assessment of PCT Margin)
- 11. Letter: NOTE 1 Issue: PRIOR TO 1990 APCT. + 1*F
- 2. Letter: Issue: APCT. 'F F. OTHER MARGIN ALLOCATIONS-(Temporary Use of PCT Margin):
- 1. - ANALYSIS MARGINS USED: VANTAGE 5 TRANSITION (NOTE 21 APCT. + 50*F
_2. PLANT MARGINS USED: N/A APCT. 'F
- 3. FUEL MARGINS USED: LB-LOCA POWER DISTR. (NOTE 31 APCT. + 100*F LICENSING BASIS PCT + MARGIN ALLOCATION APCT.__l01Ll* F N0115:
- 1. This penalty resulted from an evaluation of the sontainment mini-purge valve as discussed in UFSAR Sect. 6.2.1.5.
- 2. The transition core penalty for 17x17 Vantage 5 fuel is addressed in NCAP 10444-P-A.-
- 3. A temporary PCT penalty of 100*F was applied beginning in August 1990 to bound the potential PCT impact associated with the_ adequacy of the assumed power shape (chopped cosine) for the_LBLOCA initial condition.
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ATTACHMENT 1 BYRON 1,2/BRAIDH000 2 SMALL BREAK'LOCA 10CFR50.46 MARGIN UTILIZATION Page 4 of S PLANT N ME: EiRON_ SI AU 0H_V NIISilL2B1mI DH00D_SIA110R_U NII_2 UTILITY NAME: C0tfj0MBEALULIDIS0N A. ANALYSIS OF. RECORD PCT. 145321*F (Comments: Cale-Note No._ SEC-SAI.I-3173-CQ_ _
Evaluation Model: NOIRUMP, FQT.2,50_, FdH. L65, SGlP _1_5 %, Other: )
- 8. PRIOR LOCA MODEL AaSESSMENTS - 1989 APCT. + 0*F (Permanent Assessment of PCT Margin - Letter #: CAE-9_0-314LCCE-20-3Q91 C. PRIOR LOCA MODEL ASSESSMENTS - 1990 APCT- + Q*F (Permanent. Assessment of PCT Margin - Letter #: C8E-91-135LCCE-11-llfil-D. CURRENT LOCA MODEL ASSESSMENTS - 06/1991 (Permanent Assessment of PCT Margin)
- 1. FUEL ROD INITIAL CONDITION INCONSISTENCY APCT. + 32*F
- 2. NOTRUMP SOLUTION CONVERGENCE RELIABILITY APCT. + 0*F
- 3. SB-LOCA ROD INTERNAL PRESSURE ASSUMPTION APCT. 4 0*F E. 10CFR50.59 SAFETY EVALUATIONS - (Permanent Assessment of PCT Margin)
- 1. Letter: Issue: APCT. 'F
- 2. Letter: Issue: APCT. 'F F. OTHER MARGIN ALLOCATIONS (Temporary Use'of PCT Margin):
- 1. ANALYSIS MARGINS USED: .N/A APCT. *F
- . 2. ' PLANT MARGINS USED: HHSI SURV. (NOTE 1) APCT. + 20*F j- a. FUEL MARGINS USED: N/A APCT. *F
'~
LICENSING BASIS PCT.+ MARGIN ALLOCATION APCT. _ 1510,1*F Boles:
l '. A temporary PCT penalty of no more.than~20*F was assessed by Westinghouse -
l_ (SECL-90-01S) in support.of a potential change to the charging pump.
surveillance acceptance limit. This proposed change is still under review and has not yet been submitted for NRC approval. The SBLOCA penalty would L result from a slight reduction in delivered SI under spilling line conditions between 1400 psia and 1000 psia RCS pressure.
DRR:kab ZKAB:27:6-1 - . .-. - ~ . - .
ATTACHMENT 1
-BRAIDH000 1 SMALL BREAK LOCA 10CFR50.46 MARGIN UTILIZATION Page 5 of 5 PLANT NAME: -- BBA10HQQD_SIA110N._ UNIT 1 UTILITY NAME: C0fiM0EBEALTH EDISON A. ANALYSIS ')F . RECORD PCT. 14 ell
- SGTP ._11_J., Oiher : )
- B. PRIOR LOCA MODEL ASSESSMENTS - 1989 APCT. + 0*F L (Permanent Assessment of
- PCT Margin - Letter #: CCE 9.0-309 .)
l-l- C. PRIOR LOCA MODEL ASSESSMENTS - 1990 APCT. + 0*F (Permanent Assessment of PCT Margin - Letter #:
CCE_91-136 1
- - D.~ CURRENT LOCA MODEL ASSESSMENTS - 06/1991
! (Permanent Assessment-of PCT Margin)
- 1. FUEL ROD INITIAL CONDITION INCONSISTENCY APCT. + 3Z*F
- 2. NOTRUMP SOLUTION CONVERGENCE RELIABILITY APCT. + 0*F
- 3. SB-LOCA R0D INTERNAL PRESSURE ASSUMPTION APCT. + 0*F l E. 10CFR50.59 SAFETY _ EVALUATIONS - (Permanent Assessment of PCT Margin)
- 1. Letter: SECL-91-188.Q Issue: MISSING GRID PIECE APCT. + 17*F L 2. Letter: Issue: APCT. *F l
F. OTHER MARGIN ALLOCATIONS (Temporary Use of PCT Margin):
- 1. ANALYSIS MARGINS USED: N/A- APCT. *F
-2. PLANT MARGINS USED:
HHSI SURV. (NOTE i) APCT. + 20*F
- 3. FUEL MARGINS'USED: N/A APCT. *F LICENSING BASIS PCT ( MARGIN ALLOCATION APCT. 152Ll*F Notes:
! 1. A temporary PCT penalty of no more than 20*F was assessed by Westinghouse l (SECL-90-015) in support of a potential change to the charging pump L surveillance acceptance limit. This proposed change it still under review and has not yet been submitted for NRC approval. The SBLOCA penalty would result from a slight reduction in delivered SI under spilling line conditions between 1400 psia and 1000 psia RCS pressure, b
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