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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20199K9741997-11-30030 November 1997 Brief Aerial Photography Analysis of RBS at St Francisville,LA:1996-1997 ML20135C1951996-10-31031 October 1996 Brief Aerial Photography Analysis of River Bend Station at St Francisville,LA:1995-1996 ML20134H1791996-06-30030 June 1996 Rev 2 Suppl Reload Licensing Rept for RBS Reload 6,Cycle 7 ML20117H2871996-06-30030 June 1996 Common Cause Assessment of Refuel Operations at River Bend Station ML20096F2351995-11-30030 November 1995 Brief Aerial Photography Analysis of River Bend Station at St Francisville,LA:1994-1995 ML20100F3191995-11-30030 November 1995 Suppl Reload Licensing Rept for RBS Reload 6,Cycle 7 ML20129E2981995-05-31031 May 1995 Final BNL Technical Rept, Metallurgical Evaluation of FW Nozzle to Safe-End Weld from River Bend Station Unit 1 ML20086C4371995-05-31031 May 1995 Draft, Metallurgical Evaluation of Feedwater Nozzle to Safe-End Weld from River Bend Station,Unit 1 ML20080B3961994-11-30030 November 1994 Brief Aerial Photography Analysis of River Bend Station at St Francisville,LA:1993-94 ML20078C7881994-06-30030 June 1994 Revised Semi-Annual Rept on Fitness-For-Duty Program, for Reporting Period of 940101-0630 ML18010B0841993-05-0505 May 1993 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20128N3271993-02-17017 February 1993 Rev 0 to EA-PT-0003-S2, Responses to NRC Questions on River Bend Station Plant Transient Analysis Methodology, Suppl 1,EA-PT-91-0003-SP ML18010A9521992-11-30030 November 1992 NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216. ML20101R0691992-06-0808 June 1992 Rev 92-6 to Approved Vendors List Matl Mfgs & Suppliers of ASME Section III Matl & Subcontracted Svcs ML20094P2691992-03-31031 March 1992 Rev 0 to EA-CA-91-0001-S2, Steady State Core Physics Methods for BWR Design & Analysis, App G ML20091J5161992-01-31031 January 1992 Rev 0 to Steady State Core Physics Methods for BWR Design & Analysis ML20079P1211991-10-31031 October 1991 Suppl 1 to Nonproprietary River Bend Station Plant Station Plant Transient Analysis Methodology - Delta CPR Methodology & Addl Benchmarks RS-91-137, Rev 0 to RCIC Reliability Analysis,River Bend Nuclear Station1991-09-10010 September 1991 Rev 0 to RCIC Reliability Analysis,River Bend Nuclear Station ML20091C5391991-07-31031 July 1991 Technical Justification for Eliminating Mid-Cycle Insp of Feedwater Nozzle (N4A) to Safe-End Weld Indication at River Bend Plant ML20077A4611991-04-30030 April 1991 Transient Analysis Methodology ML20072T6571991-03-31031 March 1991 Rev 1 to Bounding Evaluation for River Bend 1 Heatup Rate Event ML20072P9881990-11-15015 November 1990 Draft Reassessment of Indication in Riverbend Feedwater Nozzle (N4A) to Safe End Weld ML20043A9051990-03-31031 March 1990 Rev 1 to Implementation of Reg Guide 1.99,Rev 2 for River Bend Station,Unit 1. ML20247J9411989-02-0909 February 1989 Analyses of Components in Asco Solenoid Valve ML20043A9061988-06-30030 June 1988 Flux Wire Dosimeter Evaluation for River Bend Station. ML20149J4111988-02-29029 February 1988 IE Bulletin Program Rept ML17279A1911987-04-0707 April 1987 Comparision of Electrical Design of Wye Pattern Globe Valve Actuator W/Ball Valve,Hanford 2 & River Bend Design. Five Oversize Drawings Encl ML20203N4171986-04-30030 April 1986 Rev 2 to Tdi Owners Group App Ii:Generic Maint Matrix & Justifications ML20141M8571986-01-28028 January 1986 Investigation,Analysis & Corrective Action for River Bend Station,860101 Loss of Offsite Power ML20137H2091985-08-31031 August 1985 Suppl 3 to Preliminary Equipment Survivability ML20134G9611985-08-31031 August 1985 Revised Stuck Open Relief Valve Base Case ML20134G9681985-08-31031 August 1985 Suppl 2 to Preliminary Equipment Survivability Rept ML20134H1661985-08-31031 August 1985 Equipment Survivability Enhancement ML20129E9081985-07-31031 July 1985 Hydrogen Deflagration Pressure Effects on Equipment ML20129F0971985-07-31031 July 1985 Revised Drywell Break Base Case Analysis ML20128H4581985-07-31031 July 1985 Preliminary Equipment Survivability Rept,River Bend Station Unit 1,Jul 1985 ML20128L9401985-06-30030 June 1985 Reg Guide 1.97,Rev 3 Compliance Rept ML20127K6031985-06-0101 June 1985 Operational Safety of Tdi DSR-48 Emergency Diesel Generator Crankshafts at River Bend Station,Gulf States Utils ML20125C4601985-05-31031 May 1985 Dcrdr Summary Rept Suppl ML20127K7081985-05-18018 May 1985 Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at River Bend Station ML20117A5631985-04-30030 April 1985 Design & Computer Analysis of Siren Prompt Notification Sys River Bend Station ML20111C5501985-02-28028 February 1985 Rev 1 to Tdi Diesel Generator Design Review & Quality Revalidation Rept ML20107H1721985-02-15015 February 1985 Rev 0 to High Energy Line Break Evaluation Rept (Effect on Nonsafety-Related Control Components) ML20101M6091984-12-31031 December 1984 Vols I-IV of Tdi Diesel Generator Design Review & Quality Revalidation Rept ML20100N2701984-11-20020 November 1984 Rev 1 to IE Bulletin 79-27 Study,Rept of Findings for River Bend Station Unit 1 ML20099H3761984-10-31031 October 1984 Detailed Control Room Design Review,Methodology & Approach, Human Engineering Discrepancy Results, Summary Rept ML20100N4141984-10-31031 October 1984 Common Sensor Failure Evaluation Rept ML20100N4121984-10-31031 October 1984 Control Sys Failures Evaluation Rept ML20093M7121984-10-0808 October 1984 Gulf States Util Co Position Re Safety/Relief Valve Discharge Testing at River Bend Station ML20093D1861984-07-0909 July 1984 Seismic OBE & SSE Required Response Spectra for Auxiliary, Control,Diesel Generator,Fuel,Turbine,Pipe Tunnels 1 & 2 & Standby Svc Water Pumphouse & Cooling Tower Bldg 1997-11-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARRBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 RBG-44969, Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for River Bend Station, Unit 1.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205D5481999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Exam Weld AA with Weld Volume Coverage of 62 Percent for First 10-year Insp Interval Pursuant to 10CFR50.55a(a)(3)(ii) & 10CFR50.55a(g)(6)(ii)(A)(5) RBG-44930, Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for River Bend Station, Unit 1.With RBG-44826, Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for River Bend Station Unit 1.With ML20198K2701998-12-22022 December 1998 Rev 1 to RBS Cycle 8 Colr RBG-44773, Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for River Bend Station, Unit 1.With RBG-44727, LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With1998-11-17017 November 1998 LER 98-S01-00:on 981021,identified That Contract Employee with Temporary Access Authorization Failed to Disclose Complete Criminal & Employment History.Individual Denied Access to Plants for Five Years.With ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program ML20155H3491998-11-0303 November 1998 Safety Evaluation Granting Requests for Relief RR2-0001, RR2-0002 & RR2-0003 RBG-44719, Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for River Bend Station, Unit 1.With ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual RBG-44677, Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for River Bend Station, Unit 1.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20151S5421998-09-0303 September 1998 Safety Evaluation Opposing Licensee Thermal Model as Currently Implemented.Evaluation Recommended to Be Used in Any follow-up Site Insp RBG-44629, Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for River Bend Station, Unit 1.With ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed RBG-44600, Monthly Operating Rept for July 1998 for River Bend Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for River Bend Station RBG-44564, Monthly Operating Rept for June 1998 for River Bend Station, Unit 11998-06-30030 June 1998 Monthly Operating Rept for June 1998 for River Bend Station, Unit 1 ML20249A6431998-06-12012 June 1998 SER Accepting 980427 Request for Change to River Bend QA Manual Program Description,Per 10CFR50.54(a)(3) RBG-44539, Monthly Operating Rept for May 1998 for River Bend Station, Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for River Bend Station, Unit 1 RBG-44501, Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for River Bend Station, Unit 1 ML20217M8951998-04-30030 April 1998 QA Program Manual ML20217P8281998-04-0707 April 1998 Safety Evaluation Accepting Relief Authorization for Alternative to Requirements of ASME Section Xi,Subarticle IWA-5250 Bolting Exam for Plants,Per 10CFR50.55a(a)(3)(i) RBG-44458, Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for River Bend Station, Unit 1 RBG-44423, Monthly Operating Rept for Feb 1998 for River Bend Station Unit 11998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for River Bend Station Unit 1 ML20203L6631998-02-11011 February 1998 Rev 0 to River Bend Station,1998 Emergency Preparedness Exercise RBG-44385, Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 11998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for River Bend Station, Unit 1 RBG-44353, Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 11997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for River Bend Station, Unit 1 RBG-44460, Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 19971997-12-31031 December 1997 Forwards Annual Radiological Environmental Operating Rept, for Period Jan-Dec 1997 ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies ML20202E9941997-12-0101 December 1997 ISI Plan Second Ten-Yr Interval (Dec 1,1997-Nov 30,2007) ML20199K9741997-11-30030 November 1997 Brief Aerial Photography Analysis of RBS at St Francisville,LA:1996-1997 RBG-44337, Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 11997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for River Bend Station, Unit 1 ML20202F0191997-11-28028 November 1997 Safety Evaluation Approving Transfer of License NPF-47 for River Bend Station,Unit 1 ML20199H3711997-11-19019 November 1997 SER Accepting Approving Request Relief from Requirements of Section XI, Rule for Inservice Insp of NPP Components, of ASME for Current or New 10-year Inservice Insp Interval IAW 50.55(a)(3)(i) of 10CFR50 RBG-44295, Monthly Operating Rept for Oct 1997 for River Bend Station Unit 11997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for River Bend Station Unit 1 RBG-44243, LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee1997-10-13013 October 1997 LER 97-S03-00:on 970911,contract Employee Was Granted Temporary Access After Failing to List Prior Employment Termination & Access Denial.Caused by Employee Failure to Provide Accurate Info.Updated Info Re Employee 1999-09-09
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Attachnent II River Bend Station Preliminary Equipnent Survivability Report Supplanent 'Am Gulf States Utilities Ccrnpany River Eend Station - Unit 1 August, 1985 3
I-i B508280190 850819 PDR ADOCK 05000458 A PDR
Introduction The previously subnitted preliminary equignent survivability report (Ref.1) was based on the original CIASIX-3 analysis of the pressure and tmperature response of the River Bend Station following a hydrogen generation event (Ref. 2) . We thermal p7ofiles predicted by CLASIX-3 for the wetwell and intar=vliate volume were used to determine equipnent response to deflagration burns. mis analysis determined that no deflagration burns would occur in the intermediate volume although a single burn was forced to occur concurrently in the wetwell, intermediate volume and upper containment to deplete the renaining hydrogen inventory after hydrogen release was coupleted. 'Ihe equipnent survivability analyses based on this thermal environment indicated that with the exception of the hydrogen igniters located in the wetwell all analyzed equipnent was capable of surviving the hydrogen generation event.
Although the intarwvliate volume thermal environment predicted by CLASIX-3 is consistent with the design of the hydrogen ignition system which is based on maximizing hydrogen burning at low concentration which would occur primarily below the HCU floor, there is a possibility that sane burns could occur above the HCU floor. Consequently, at the request of the NBC staff, GSU subnitted a supplanent to the preliminary equignent survivability report (Ref. 3) which evaluated the thermal response of equignent located in the intermediate volume assuming that i the equipnent was exposed directly to the burn environment predicted for
- m-= ,
a the wetwell region below the HCU floor. his was an extremely conservative approach since the CIASIX-3 results are very conservative and the intamadiate volume equipnent will not be exposed to the wetwell thermal enviroment.
To provide a more realistic upper bound for the in+amadiate volune thermal envirorsnent, a revised Stuck Open Relief Valve (SOW) CLASIX-3 analysis has been performed (see Attachment I of this subnittal) . This repvrt. evaluates the ability of equipnent located in the intermediate volume to survive this thermal envirornent.
2.0 Sermal Environment he revised SOW base case CIASIX-3 analysis is presented in f
Attachment I. %is analysis was based on a more detailed nodalization of the intamadiate volune and more realistic hAwen burn parameters for all con +aimant regions except -in the wetwell
- volume. : The CLASIX-3 model used in the revised SOW analysis split the previously defined intermediate volume into two separate volumes to- provide a better definition of the thermal environment to which the equipnent would be caevsed. %ese new volumes were termed the lower in+amadiate volune (HCU floor to El.141') and the upper intamadiate volume (El.141 ft to refueling floor). @e thermal
- profiles used in this analysis.are shown in figures 1 through 3 for i
the wetwell, lower intermediate volume and upper intermediate volume respectively. Equipnent located in the lower intermediate volume L
L
o .
near the HCU floor will be directly exposed to deflagration burns occurring in this voltme. Evaluation of the thennal loading to equipnent in the lower ini-arnviiate volume due to deflagration burns in the wetwell indicates that the thermal radiation contribution should be minimal cmpared to the intermediate volume deflagrations.
%is is based on the physical location of the equignent relative to the wetwell burns. For example, the Rosanont transmitters are effectively shielded fran the wetwell burns by the floor plate upon which the panels are mounted and by the HCU floor grating. Since the grating has a blockage function of 0.3 and the view angle is relatively small for these transmitters, the radiative heat flux due to wetwell burns was judged to be of minor importance. Inspection of the lower intermediate volume thermal profiles shows that the flow of hot gases fran the wetwell due to burns in the wetwell has been included in this profile.
-3.0 Equipment Modeled The equignent- modeled in this analysis are a Rosanont transmitter and a Reliance motor. h e HEATING 6 models used in this analysis are the same as the models previously subnitted (References 1 and 3) . anphasis was placed on these pieces of equipnent since these are the only equipnent, other than cable, required to survive a hydrogen generation event which are located in the lower inter =vliate volume. Inspection of the thermal profile for the upper intermediate volume indicates that the maximum tanperature
reached in this volume is 320 F, since these tanperatures are only slightly higher than the tenperature profiles previously analyzed (Referen m 1). All equignent located in the upper intarnvH ate voltzne is expected to survive the hydrogen generation event.
Further analysis of the survivability of equipnent located in this voltane is not judged to be necessary at this time.
4.0 Results/ Conclusions The results of this evaluation are sunnarized in Table 1 which shows the t.w g z.tures reached by the casing and the most thennally limiting sutHxxuponent when exposed to the lower intennediate volume deflagration burn envirorrnent predicted by CLASIX-3.
For the Rosemont transmitter, the case temperature at the end of the transient was below the equipnent qualification tenperature.
Therefore, the survivability of these transmitters is assured.
Although the case tenperature of the Reliance motor was slightly above the equipnent qualification tenperature at the end of the transient, the sensitive conponent, the motor coil, was well below the qualified temperature.
These results show that the essential equipnent located in the lower intarwaiate volume is capable of surviving the hydrogen generation event.
tezueNCES
- 1) RBG-21,423 dated July 1, 1985 fra Gulf States Utilities (J. E. Booker) to Nuclear Regulatory Ccunission (H. R. Denton)
- 2) RBG-21,218 dated June 7, 1985 frm Gulf States Utilities (J. E. Booker) to Nuclear Wp.datory Cmmission (H. R. Denton)
- 3) RBG-21,771 dated August 5, 1985
-frm Gulf States Utilities (J. E. Booker) to Nuclear Regulatory Cmmission (H. R. Denton)
Table 1 Stenary of Results Equipnent Predicted Tenperature Qualification Sersitive Unit Tenperature Casing Component Rosemont Transmitter
- 320 F 311 F 290 F Model 1154 Reliance Motor on 345 F 347 F 311 F Limitorque Operator-
e 4 g ,
FIGURE 1 GSU/ RIVERWETWELLBEND 5 VOL. AUG.85 TEMPERATURE 2.4 2.2 -
2-1.8 -
p 1.6 -
vm talj 1.4 -
1.2 -
0 US 1-I o.a -
0.6 -
O.4 -
, ((((( @ (LLb4bb400UU o , , , , , . . . . . i i i O 4 8 12 .16 20 24 28 TIME (1000 SECONDS)
A-
. FIGURE 2 l
l GSU/ LOWER RIVER BEND 5 VOL. AUG.85 INTERMEDIATE VOLUME TEMPERATURE 1
' O.9 -
O.8 -
0.7 -
C
[9 0.s -
2 5
g l 0.5 -
0 .4 -
I O.3 -
A' '
Js6 '
6-
- 6 L W 0.2 - (y(( ( 5 ( 5 O.1 -%
0 , , , , , , , , , , , , ,
O 4 8 12 16 20 .'44 28 -
TlWE (1000 SECONDS)
FIGURE 3 GSU/ RIVER BEND 5 VOL. AUG.85 UPPER INTERWEDIATE VOLUWE TEMPERATURE 320 -
300 -
280 -
260 -
Q 240 -
]
p 220 -
200 -
160-p 140 -
l i l 1 20 -
g s LLL a uN
)
V t L. /
l J 'lh[l I 100 - .
A U M i i a e a i i e i a i e i O 4 8 12 16 20 24 28 TlWE (1000 SECCHDS) i
._ _ _ . _ _ . , . _ _ _ _ _ . _