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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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NUCLE AR ENERGY BUSINESS GROUP
- GENE RAL ELECTRIC COMPANY SAN JOSE, CALIFORNI A 95125 GEN ER AL h ELECTRIC APPLICABLE TO:
NED0-21697
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77NED149 ERRATA And ADDENDA T.i.E. N o. gg
,,, , LOCA Analysis Report for ,
"O' Vermont Yankee Nuclear Power U^
Station August 1977 NOTE: Correct allcopies of the applicable ISSUE DATE publication as specified belcw.
RE ERENCES INSTRUCTIONS
' YAc Ap (CORRECTIONS AND ADDITIONS) p LIRE) 1 Page iv Replace with new page iv 2 Page 3-1 Replace with new page 3-1 3 Page 4-3 Replace with new pagc 4-3 4 Page 4-8 Replace with new page 4-8 5 Page 4-11 Replace with new page 4-11 6 Page 4-13 Add new page 4-13 Changes are indicated by vertical bar in right-hand margin.
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- o NED0-21697 LIST OF TABLES Table Title Page 1 Significant Input Parameters to the Loss-of-Coolant Accident 3-1 2 Summary of Break Spectrum Results 4- 5 3 LOCA Analysis Figure Summary - Non-Lead Plant 4-6 4A MAPLHGR Versus Average Planar Exposure 4-7 4B MAPLHGR Versus Average Planar Exposure 4-8 4C MAPLHGR Versus Average Planar Exposure 4-9 4D MAPLHGR Versus Average Planar Exposure 4-10 4E MAPLHGR Versus Average Planar Exposure 4-11 4F MAPLHGR Versus Average Planar Exposure 4-12 4G MAPLGHR Versus Average Planar Exposure 4-13 )
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- 3. INPUT TO ANALYSIS A list of the significant plant input parameters to the LOCA analysis is presented in Table 1.
Table i SIGNIFICANT INPUT PARAMETERS TO THE LOSS-OF-COOLANT ACCIDENT ANALYSIS Plant Parameters:
Core Therma.L. Power 1664 MWt, which corresponds to 105% of rated steam flow 0
Vessel Steam Output 6.75 x 10 lbm/h, which corresponds to 105% of rated steam flow Vessel Stean N=e Pressure 1055 psia Recirculation i ne Break Area for Large Breakt - Discharge 2.26 ft2 (DBA)
- Suction 4.14 ft2 L mber of Drilled Bundles 220 Fuel Parameters:
Peak Technical Initial Specification Design Minimum Linear Heat Axial Critical Fuel Bundle Generation Rate Peaking Power Fuel Type Geometry (kW/ft) Factor Ratio
- A. 7D230 7x7 18.5 1.5 1.2 B. 8D219 8x8 13.4 1.4 1.2 C. 8D274L 8x8 13.4 1.4 1.2 D. 8D274H 8x8 13.4 1.4 1.2 E. 8D274 (High Gd) 8x8 13.4 1.4 1.2 F. LTA 8x8 13.4 1.4 1.2 v'
G. 8D/LB28p 8x8 13.4 1.4 1.2
& P8DKB289
- To account for the 2% uncertainty in bundle power required by Appendix K, the SCAT talcula*.icn is performed with an MCPR of 1.18 (i.e., 1.2 divided by 1.02) for a bundle with en initial MCPR of 1.20.
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MED0-21697 4.5 RESULTS OF THE CHASTE ANALYSIS This code is used, with suitable inputs from the other codes, to calculate the fuel cladding heatup rate, peak cladding temperature, peak local cladding oxidation, and core-wide metal-water reaction for large breaks. The detailed fuel model in CHASTE considers transient gap conductance, clad swelling and rupture, and metal-water reaction. The empirical core spray heat transfer and channel wetting correlations are built into CHASTE, which solves the transient heat transfer equations for the entire LOCA transient at a single axial plane in a single fuel assembly. Iterative applications of CHASTE determine the maximum permissible planar power where required to satisfy the requirements of 10CFR50.46 acceptance Criteria.
The CHASTE results presented are:
o Peak Cladding Temperature versus time e Peak Cladding Temperature versus Break Area e Peak Cladding Temperature and Peak Local Oxidation versus Planar Average Exposure for the most limiting break size e Maximum Average Planar Heat Generation Rate (MAPLHGR) versus Planar Average Exposure for the most limiting break size A summary of the analytical results is given in Table 2. Table 3 lists the figures provided for this analysis. The MAPLHGR values for each fuel type in the Vermont Yankee core are presented in Tables 4A through 4G. )
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NEDO-21697 Table 4B MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: Vermont Yankee Fuel Type: 8D219 Average Planar Exposure MAPLHGR PCT 0xidation l (MRd/t) (kW/ft) (*F) Fraction 200.u 11.4 2053. 0.021 1,000.0 11.5 2061. 0.021 5,000.0 11.9 2117. 0.023 10,000.0 12.1 2164. 0.026 15,000.0 12.3 2192. 0.029 20,000.0 12.1 2189. 0.029 25,000.0 11.3 2077. 0.020 30,000.0 10.2 1933. 0.012 35,000.0 9.6 1704. 0.004 )
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NEDO-21697 Table 4E MAPLHGR VERSUS AVERAGE PLANAR EXPOSURE Plant: Vertront Yankee Fuel Type: 8D274 (High Gd)
Average Planar Exposure MAPLHGR PCT 0xidation (mwd /t) (kW/ft) (*F) Fraction 200.0 11.1 2053. 0.019 1,000.0 11.1 2044. O.018 5,000.0 ll.6 2092. O.021 10,000.0 12.1 2141. O.024 15,000.0 12.2 2165. O.026 20,000.0 12.1 2170. 0.027 25,000.0 11,6 2119. O.023 30,000.0 10.6 1993. O.015 35,000.0 10.0 1751. 0.005 40,000.0 9.4 1671. 0.004 i
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NED& 21697 Table 4G MAPLHGR VERSUS AVERAGE PLANAR FlPOSURE e P PIANT: Vermont Yankee Fuel Type: 8DJtB289 & P8D)tB289 Average Planar Exposure MAPLHGR PCT 0xidation (mwd /t) (kW/ft) ('F) Fraction 200.0 11.2 2126 0.027 1,000.0 11.2 2119 0.026 5,000.0 11.8 2178 0.030 10,000.0 12.0 2185 0.030 15,000.L 12.1 2200 0.032 20,000.0 11.8 2187 0.031 25,000.0 11.3 2120 0.025 30,000.0 11.1 2095 0.023 35,000.0 0.008 10.4 1862 40,000.0 9.8 1784 0.006 I
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