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Category:REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)
MONTHYEARML20137W1301997-03-31031 March 1997 Application of FIBWR2 Core Hydraulic Code to BWR Reload Analysis ML20128P1911996-10-31031 October 1996 Rev 2 to GE-NE-523-B13-01805-105, Evaluation of Indications at Collar to Shroud Weld of Vermont Yankee Annulus Core Spray Piping ML20082Q8621995-04-18018 April 1995 Ahroud Safety Assessment ML20082N5921995-01-20020 January 1995 Cycle 18 Core Performance Analysis Rept ML20066E1571990-12-31031 December 1990 Rev 1 to Analysis to Support Removal of Vermont Yankee Toxic Gas Monitoring Sys ML19332F2831989-11-30030 November 1989 Rev 1 to Application of One-Dimensional Kinetics to BWR Transient Analysis Methods. ML20043C6211989-09-30030 September 1989 Simulate-3 Validation & Verification. ML20245L1641989-06-30030 June 1989 Application of One-Dimensional Kinetics to Vermont Yankee Transient Analysis Methods ML20012C6141989-06-29029 June 1989 Method for Generation of One-Dimensional Kinetics Data for RETRAN-02. ML20043C6061989-03-31031 March 1989 MICBURN-3/CASMO-3/TABLES-3/SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 Through 13. ML20247D2991989-03-14014 March 1989 MICBURN-3/CASMO-3/TABLES-3/SIMULATE-3 Benchmarking of Vermont Yankee Cycles 9 Through 13 ML20084F2211983-11-30030 November 1983 Rev 2 to Mark I Containment Program:Plant-Unique Analysis Rept of Torus Suppression Chamber ML20080Q2241983-10-0303 October 1983 Mark I Containment Program Plant-Unique Analysis Rept of Torus Attached Piping for Vermont Yankee Nuclear Power Plant ML20079Q6591983-05-31031 May 1983 Rev 1 to Safety Evaluation of MSIV Low Turbine Inlet Pressure Isolation Setpoint Change for Vermont Yankee Nuclear Power Station ML20140F6771983-02-28028 February 1983 Single Loop Operation ML20011A7741981-10-30030 October 1981 Yankee Atomic BWR Analysis Methods:Analysis of Typical BWR/4 Turbine Trip W/O Bypass Transients. ML20038B0821981-08-31031 August 1981 Errata 3 to Topical Rept NEDO-21697, LOCA Analysis Rept for VT Yankee Nuclear Power Station. ML20010H4771981-07-31031 July 1981 Fibwr:Steady State Core Flow Distribution Code for Bwrs, Computer Code Users Manual. ML20217C4581981-06-30030 June 1981 BWR Owners Group Evaluation of NUREG-0737 Item II.K.3.24, HPCI & RCIC Sys Environ Capabilities ML19350C1431981-03-24024 March 1981 Methods for Analysis of BWRs Steady State Core Physics. ML20003C3031981-01-31031 January 1981 VT Yankee Nuclear Power Station Proposed Stability & Recirculation Pump Trip Tests. ML20002D5671981-01-14014 January 1981 Errata Sheets of Matl to Be Added to Methods for Analysis of BWRs Transient Thermal Margin Analysis Code (MAYUO4-YAEC), Submitted 801231 ML19353A4121980-12-31031 December 1980 Methods for Analysis of BWRs,Steady-State Core Flow Distribution Code (Fibwr). ML19353A4221980-12-31031 December 1980 Methods for Analysis of BWRs Lattice Physics. ML20002C0411980-12-30030 December 1980 Methods for Analysis of Bwrs,Transient Thermal Margin Analysis Code (MAYUO4-YAEC). 1997-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217L8831999-10-21021 October 1999 Safety Evaluation Supporting Proposed Alternatives to Code Requirements Described in RR-V17 & RR-V18 ML20217G2041999-10-13013 October 1999 Safety Evaluation Supporting Amend 179 to License DPR-28 BVY-99-127, Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Vermont Yankee Nuclear Power Station.With ML20212C2551999-09-17017 September 1999 Safety Evaluation Supporting Amend 175 to License DPR-28 BVY-99-112, Monthly Operating Rept for Aug 1999 for Vermont Yankee.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Vermont Yankee.With BVY-99-109, Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 9908311999-08-19019 August 1999 Ro:On 990812,stack Ng Effluent Instrumentation for PAM Was Declared Oos.Caused by Instrument Drift Due to Electronic Components Based on Insps by Instrumentation & Controls Dept.Detector & Preamplifier Will Be Replaced on 990831 BVY-99-102, Monthly Operating Rept for July 1999 for Vermont Yankee. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Vermont Yankee. with ML20209J0081999-07-14014 July 1999 Special Rept:On 990615,diesel Driven Fire Pump Failed to Achieve Rated Flow of 2500 Gallons Per Minute.Pump Was Inoperable for Greater than 7 Days.Corrective Maint Was Performed to Reset Pump Lift Setting BVY-99-090, Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Vermont Yankee Nuclear Power Station.With ML20196G5071999-06-23023 June 1999 Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading BVY-99-077, Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Vermont Yankee Nuclear Power Station.With BVY-99-068, Monthly Operating Rept for Apr 1999 for Vynp.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Vynp.With ML20206E8741999-04-29029 April 1999 SER Determined That Flaw Evaluation Meets Rules of ASME Code & Assumed Crack Growth Rate Adequate for Application ML20206D9301999-04-27027 April 1999 1999 Emergency Preparedness Exercise 990427 Exercise Manual (Plume Portion) ML20205S4211999-04-16016 April 1999 Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion ML20205K7581999-04-0707 April 1999 Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV BVY-99-046, Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Vermont Yankee Nuclear Power Station.With ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation BVY-99-035, Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Vermont Yankee Nuclear Station.With ML20205P8241999-02-28028 February 1999 Rev 2 to Vermont Yankee Cycle 20 Colr ML20203H9881999-02-18018 February 1999 SER Accepting Alternative to 10CFR50.55a(g)(6)(ii)(A) Augmented Reactor Vessel Exam at Vermont Yankee Nuclear Power Station.Technical Ltr Rept Encl ML20203A6951999-02-0404 February 1999 Revised Rev 2,App B to Vermont Yankee Operational QA Manual (Voqam) ML20199K7151999-01-21021 January 1999 Corrected Safety Evaluation Supporting Amend 163 Issued to FOL DPR-28.Pages 2 & 3 Required Correction & Clarification ML20199K6991999-01-20020 January 1999 Safety Evaluation Concluding That Request to Use YAEC-1339, Yankee Atomic Electric Co Application of FIBWR2 Core Hydraulics Code to BWR Reload Analysis, at Vermont Yankee Acceptable ML20199L5951999-01-14014 January 1999 Safety Evaluation Accepting Licensee Proposed Alternative to Code Requirement,Described in Rev 2 to Pump Relief Request RR-P10 Pursuant to 10CFR50.55a(a)(3)(i) BVY-99-071, Corp 1998 Annual Rept. with1998-12-31031 December 1998 Corp 1998 Annual Rept. with BVY-99-001, Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Vermont Yankee Nuclear Power Station ML20198H5481998-12-23023 December 1998 Rev 2 to Vermont Operational QA Manual,Voqam ML20196H8641998-12-0101 December 1998 Cycle 19 Operating Rept BVY-98-163, Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Vermont Yankee Nuclear Power Station.With ML20195C4161998-11-0909 November 1998 SER Accepting Request That NRC Approve ASME Code Case N-560, Alternative Exam Requirement for Class 1,Category B-J Piping Welds BVY-98-154, Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Vermont Yankee Nuclear Power Station.With ML20155B6471998-10-26026 October 1998 Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage ML20154N0891998-10-16016 October 1998 Rev 1 to Vermont Operational QA Program Manual (Voqam) ML20154B6951998-10-0101 October 1998 SER Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Vermont Yankee Nuclear Power Station BVY-98-149, Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Vermont Yankee Nuclear Power Station.With ML20239A1361998-09-0202 September 1998 SER Re License Request for NRC Review & Concurrence W/Changes to NRC-approved Fire Protection Program BVY-98-135, Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Vermont Yankee Nuclear Power Station.With ML20151U0361998-08-28028 August 1998 Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project ML20237E9221998-08-20020 August 1998 Vynp 1998 Form NIS-1 Owners Summary Rept for ISI, 961103-980603 BVY-98-122, Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Vermont Yankee Nuclear Power Station ML20205F6491998-07-31031 July 1998 Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee ML20236G0011998-06-30030 June 1998 Individual Plant Exam External Events BVY-98-098, Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Vermont Yankee Nuclear Power Station ML20248C5081998-05-31031 May 1998 Rev 2 to 24A5416, Supplemental Reload Licensing Rept for Vermont Yankee Nuclear Power Station Reload 19 Cycle 20 ML20248C4951998-05-31031 May 1998 Rev 1 to Vermont Yankee Nuclear Power Station Cycle 20 Colr BVY-98-081, Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Vermont Yankee Nuclear Power Station ML20247J8341998-05-31031 May 1998 Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998 ML20247G4001998-05-12012 May 1998 Interview Rept of Ej Massey ML20247E6351998-04-30030 April 1998 Rev 1 to GE-NE-B13-01935-LTR, Jet Pump Riser Welds Allowable Flaw Sizes Ltr Rept for Vermont Yankee 1999-09-30
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JUNE 1981 BWR OWNERS' GROUP EVALUATION OF NUREG-0737 ITEM ll.K.3.24:
HPCI AND RCIC SYSTEM ENVIRONMENTAL CAPABILITIES I
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' GENER AL $ ELECTRI' lu 188e: Pd88en P PDR
NEDE-24955 Class 11 June 1981 Bit OWNER 8' CROUP EVALUATION OF NUREG-0737 ITEN II.K.3.24 EPCI Am RCIC SYSTEN EB71303 ENTAL CAPASILITIES Approved:
J. D. Duncan,. Senior Program Manager TMI Prograss P
Approved ,
P. W. Marr ott, Manager BWR Operations Analysis NUCLE.M FUEL AND SERVICES DIVISION e GENSRAL ELECTRIC COtePANY SAN JOSE, CAUPORNIA SS126 SENERAL $ ELECTRIC
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NEDE-24955 FOREWORD This report was prepared by General Electric Company for the BWR Owners' Group as authorized at the Owners' Group July 1, 1980 general meeting. It is not I
intended to serve as a freestanding response to NUREG-0737 Requirement II.K.3.24; I rather it is a specialized contribution which is to be used by individual utilitie in preparing their own submittals.
This study is intended to assist the BWR Owners' Group in responding to NUREG-073' Requirement II.K.3.24, which states, "Long-term operation of.the reactor core isolation cooling (RCIC) and high pressure coolant injection (HPCI) systems may require space cooling to maintain the pump room temperatures within allowable limits. Licensees should verify the acceptability of the consequences of a ,
complete loss of alternating-current power. The RCIC and RPCI systems should be designed to withstand a complete loss of off-site alternating current power to their support systems, including coolers, for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />." l The NRC has subsequently clarified the phrase " complete loss of alternating current power" to mean loss of only off-site alternating current power. This clarification is doctamented in Appendix A. For most plants, satisfying this requirement involves a statement that all support systems necessary for HPCI and RCIC systems operation, including room coolers, are powered by on-site emergency power, and RCIC and RPCI can operate for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with loss of off-site AC power. For plants whose room coolers are not on emergency power, this NRC item can be satisfied by showing that these systems can operate for the 2-hour period without exceeding the equipment capabilities defined in this study.
This report is not intended to be used as a direct submittal to the NRC; it should be used only to assist individual utilities in responding to this task.
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NEDE-24955 INTRODUCTION Nis study presents the realistic equipment environmental capability for the HPCI and RCIC pumps, turbines, and turbine control components. The turbine control components are the limiting equipment with regard to env$ronmental capability. The following; information is applicable to HPCI an% RCIC systems using Terry steam turbines for the plants listed in Appendix B.
1 CONCLUSIONS The realistic equipment raos environmental limit for the HPCI and RCIC systems using Terry steam turbines and Woodward electronio control r/ stems is 1500F, and 100% relative humidity for the required M.our perici, l
If this environmental limit earnot be saintained in the e .tuipment rooms, consideration can be given to remoi,41y locating the electronio control panel.
' The equipment supplier has identified the acosptability of a remote location, up to 600 feet removed, using 16 gage, twisted, shielded wiring for interconnecting cabling. (It must be noted that the remote loostion of the electronio control panel complicates the control system calibration procedures 2 and increases the poter.tial for noise interference in the control systaa.) If l
the electronic control panel can be remotely located for an environmental condition not exceeding 1500F and 100$ relative humidity, system operation with the turt',ne/ pump equipment room reaching an environmental limit of 2120F and 100% relative humidity is possible for the required 24our period.
BA dsavumu INFORMATION AND DATA The following inforsution and data enlain and justify the conclusions defined above.
The design basis for the equipment i.s:
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NEDE-24955 Normal er.rironment, equipment not running - 1040F, 90% RH Normat environment, equipment running - 1500F, 90% M Abnormal environment, equipment running
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Turbine mounted equipment - 2120F for 0 ts 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 1500F for 6 to 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1005 M Electronio controls, remote mounted - 1500F for 0-12 hours 1005 RH Woodward Governor Company, supplier of the turbine control components, has identified a maximum operating temperature of 1680F, with 80% reistive humidity for their electronic controls (any time interval) and 2120F with 1005 relative humidity for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> operation for the control components which must be mounted on the turbine assembly.
t Typical turbine control systems have been subjected to thermal aging cnd accident environment conditions in specifio qualification tests in accord 6nce with IEEE-323. The electronio controls were "ageda ter 50 days at a temperature of 1850F in a non-operatiomi state, followed f operation in a temperature environment of 1500F, with 1005 relative humidity, for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The remaining control components, which must remain mountad on the turbine, were " aged" for 50 days at a temperature of 2250F, followed by operation in an enviemt of 2120F,1005 RH for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and 1500F,1005 RH for an additia. A 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
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- APPEND NRC CLARIFICATION SWR ommasTX onou, A: .__
P.O. Ses 1551 # Mey. North corohno 97ece * (919) a36 65a4 BWROG 811.4 January 23. 1981 l
l U. 5. Nuclear Regulatory Consission Division of Licensing l 4
Office of Nuclear Reactor Regulation l Washinimon. D. C. 20555 Attent<on: Darrell G. Eisenhut Director l
Subject:
Clarification of NUREG-0737 Items II.K.3.24 and II.K.3.25 Gentlemen: t This letter documents the telephone conversation between H. W. Sherwood and F. R. Hayes of General Electric and Wayne Hodges of the NRC on January 14 1981. The subject of the telephone conversation was clarification of NUREG- l 0737 Requirements II.K.3.24 and II.K.3.25.
The questiotu pertained to defining what was intended by " loss of alternsting-current power" as described in the two items. Item II.K.3.24 states. " Licensees i should verify the acceptability of the consequences of a complete loss of i alternating-current power" and item II.K.3.25 states. "The pump seals should be designed to withstand a complete loss of alternating-current (ac) power for at least 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />." 4 Mr. Hodges indicated that loss of alternating-current power is intended to mean j only loss of offsite power for both items, and that failure of onsite emergency power does not have to be assumed. 4 If have any further questions. pivase contact R. H. Buchholz (GE).
(408 925-5722. . 4 Sincerely. !
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,h b D. 8. Waters. Chairman 1 2 BWR Owners' Group 08W:na cc: M R Owners' Group M. W. Hodges (MR J. A. 01shinski C)
R.H.Suchholzq <
- k. W. Marriott L h.J. Stark (GED .<
I B l 0128M9 /h j
NEDE-24955 APPENDIX B Participating Utilities HPCI/RCIC Environmental Capabilities
' This report applies to the following plants, whose Duners participated in the report'a development.
Boston Edison Pilgrim 1 Carolina Pcmer & Light Brunswick 1&2
? r z = 1th Edison LaSalle 1&2, Dresden 2 & 3, Quad Cities 1 & 2 Georgia Power Batch 142 '
Ious Electrio Light & Power Duane Arnold Niagara Mohawk Power Nine Mile Point 2 Nebruska Public Power District Cooper Northern States Power Monticello Ph!1adelphia Electric Peach Botton 2&3; Limerick 142 Detroit Edison Enrico Fermi 2 Mississippi Power & Light i Grand Gulf 1&2 Pennsylvania Power & Light Susquehanna 1&2 i
iisshington Public Power Supply System Hanford 2 Cleveland Electric Illuminating Perry 1&2 Houston Lighting & Power Allens Creek Illinois Power ;
Clinton Station 1&2 Publio' Service of Oklahoma Black Fox 1&2 Tennessee Valley Authority l Browns Ferry 1-3, Hartsville 1-4; Phipps Bend 1-2 Power Authority of the State of New York Fitzpatrick Vermont Yankee Nuclear Power Vermont Yankee Gulf States Utilities River Bend 1 & E Public' Service Electric & Ges l Hope Creek 1 & 2 1
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. i NEDE-24955 DISTRIBUTION Name M/C W. R. Becraft 738 )
R. J. Bogisich/R. B. Hamilton 364
. R. J. Brandon/J. H. Oates/A. E. Rogers /L. H. Youngborg 889 R. M. Buchhols 682 D. W. Diefenderfer/F, P. Felini 880 {
.. C. W. Dillmann 1 750 i J. D. Duncan I 738 l
W. C. R1hoff 886 R. M. Fairfield 855 R. M. Felthous TTC L. F. Fidrych 167 J. S. Gay /J. J. Marguin 864 L. S. Cifford Bethesda F. R. Hayes 682 ;
R. A. Hill 682 I D. W. Books 277 P. W. Ianni 151 D. L. Janacek MTC J. C. Ralso 750 J. H. Rrepick 603 P. W. Marriott 848 R. F. McClelland (33) 681 W. C. Meinhardt 886 J. F. Schilder 848 M. W. Laerwood 848 l
F. F. Smith 580 S. J. Stark 682 :
B. Stevens (5 + 1) 126 I. F. Stuart 1 886 '
M. E. Tanner 855 T. Trocki 681
.C. A. VonDr.amt
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NEDE-24W33 DISTRIBUTION (Coat Name M/C D. E. W111ste 844 W. J. Ear 11a 843
. J. F. Eilinskas 843 {
NEBG Library (5) - 328 VNC Library (2) V01 l
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