Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion| ML20205S421 |
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Vermont Yankee  |
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| Issue date: |
04/16/1999 |
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| From: |
HOLTEC INTERNATIONAL |
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| To: |
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| Shared Package |
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| ML20137L670 |
List: |
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| References |
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| HI-981932, NUDOCS 9904260212 |
| Download: ML20205S421 (1) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20196G5071999-06-23023 June 1999
Vynp Assessment of On-Site Disposal of Contaminated Soil by Land Spreading
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Rev 1 to GE-NE-B13-01935-02, Jet Pump Assembly Welds Flaw Evaluation Handbook for Vermont Yankee
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Final Rept of Rev 0 to 1HQXE, Vynp Unit 1 Recirculation Inlet Riser Ultrasonic Exam
A34600, Hydrodynamic Mass & Acceleration Drag Vol of Vermont Yankee ECCS Strainers1998-03-13013 March 1998
Hydrodynamic Mass & Acceleration Drag Vol of Vermont Yankee ECCS Strainers
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Addl Benchmarking of BWR Using CASMO-3/SIMULATE-3
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Consequence Evaluation of Vynp Class 1 Piping in Support of ASME Code Case N-560
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Advanced Offgas Follow-up Rept
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Tech Specs for Offsite Power
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Compliance W/Sbo Regulation
ML20107D5951996-04-30030 April 1996
Rev 0 to Vermont Yankee Nuclear Power Station Core Shroud Repair Summary
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Method for Power/Flow Exclusion Region Calculation Using LAPUR5 Computer Code
ML20086S3141995-07-20020 July 1995
Vynp 1995 Summary Rept for Repairs & Replacements 931001- 950505
ML20086K4581995-06-20020 June 1995
Inside Surface Ultrasonic Technique Capabilities as Demonstrated for Insp of FW Nozzles Final Rept
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Investigation of Certain Anonymous Allegations Re Advanced Off-Gas Sys at Vermont Yankee Nuclear Power Station
ML20097A5281992-05-29029 May 1992
Rev 1 to Decommissioning Funding Assurance Rept & Certification Submitted Per 10CFR50.33(k)(2),10CFR30.35 & 10CFR50.75,Vermont Yankee Nuclear Power Station
ML20101S1261992-05-15015 May 1992
Application to Dispose in Place Contaminated Soil
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Emergency Response Exercise Manual 1991
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Simulator Certification Rept,Vermont Yankee Training Dept Jan 1991
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Rev 0 to Vermont Yankee Cycle 14 Core Operating Limits Rept
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Method for Generation of One-Dimensional Kinetics Data for RETRAN-02
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Rev 3 to Vermont Yankee Procedure Generation Package
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Impact of Alternate Testing on Component & Sys Availability
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CASMO-3G Validation
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Rept on Containment Safety at Vermont Yankee
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Justification for Long-Term Operation for Vermont Yankee Core Spray Nozzle Weld Overlays
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Shutdown Assessment of Vermont Yankee Nuclear Power Facility, Interim Rept to State of Vt General Assembly
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Dcrdr Summary Rept Suppl for Vermont Yankee Nuclear Power Plant
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Cycle 13 Core Performance Analysis
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Thermal Effects on Precoat Matl for Spent Fuel Pool Filter/ Demineralizers,Vermont Yankee Nuclear Power Station
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Evaluation of Matl Performance Suitability of New Vermont Yankee Spent Fuel Storage Rack Design
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Justification for Multi-Cycle Operation for Vermont Yankee Core Spray Nozzle Weld Overlays
ML20214K6871986-08-31031 August 1986
Vols 1 & 2 to Dcrdr Implementation Task Team Final Rept, Supplementary NRC Matl. W/Two Oversize Encls
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Containment Safety Study
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Revised SAR for Vermont Yankee Spds
ML20210S2391986-06-25025 June 1986
High Risk:Ge Mark I Pressure-Suppression Design. Public Citizen Press Release Re Natl Coalition of Citizen Groups Petitions NRC to Revoke CPs for New Nuclear Plants Encl
ML20203K8191986-04-30030 April 1986
Spent Fuel Storage Rack Replacement Rept
ML20204G7371986-04-22022 April 1986
IHSI Weld Package for Vermont Yankee Nuclear Power Station
ML20128E4131985-07-0101 July 1985
Dcrdr Summary Rept for Vermont Yankee Nuclear Power Plant
ML20128P0891985-05-21021 May 1985
Rept of Investigation Carried Out by Ropes & Gray of Apparent False Documentation of Results of Receipt Insps at Vermont Yankee Nuclear Power Station
ML20117A1071985-04-0808 April 1985
Safe Shutdown Capability Analysis
ML20154N4811985-01-31031 January 1985
Rev 0 to Mark I Wetwell to Drywell Differential Pressure Load & Vacuum Breaker Response for Vermont Yankee Generation Station
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Functional SPDS Sar
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Rev 2 to Environ Qualification Master Equipment List
1999-06-23
[Table view]
Category:TEXT-SAFETY REPORT
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Safety Evaluation Supporting Amend 175 to License DPR-28
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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
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Monthly Operating Rept for Apr 1999 for Vynp.With
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Non-proprietary Version of Revised Page 4-3 of HI-981932 Technical Rept for Vermont Yankee Spent Fuel Pool Storage Expansion
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Safety Evaluation Supporting Alternative Proposal for Reexamination of Circumferential Welds with Detected Flaw Indications in Plant RPV
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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
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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
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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
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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
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Safety Evaluation Accepting Jet Pump Riser Insp Results & Flaw Evaluation,Conducted During 1998 Refueling Outage
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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
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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
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Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project
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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
[Table view] |
Text
-
..o
- The rack-to-rack gap between the existing VYNPS racks was assumed to be 1 inch for the cvaluation of the lateral rack movement accident. This value is smaller than the minimum rack-to-rack gap of 2 inches permitted under the previous rerack project.
- Conservatively, uniform average enrichments were used for all fuel pins in a fuel assembly instead of distributed enrichments.
The BWR spent fuel storage racks are designed to accammodate any and all of the fuel assemblies listed in Table 4.3.1 with a maximum planar average enrichment of 4.6 wt.% *U.
Each fuel assembly type was analyzed independently to determine its acceptability in the rack.
4.2 Summary of Criticality Analyses 4.2.1 Normal Operatina Conditions All BWR fuel. assembly types being considered were explicitly analyzed to determine the acceptability for storage in the spent fuel pool. A maximum average enrichment was assumed for all rods in the assembly and no credit was taken for gadolinia which might be present.
l l
The criticality safety was evaluated at the burnup corresponding to a k nt i of 1.33 in the Standard Cold Core Geometry (SCCG). SCCG is defined as an infinite array of fuel assemblies on a 6-inch lattice spacing at 20 C, without any control absorber or voids. l The maximum kint in the new Holtec BWR storage rack module was determined to be 0.9280 g, (95% probability at the 95% confidence level) including all known calculational and manufacturing uncertainties. The maximum knr i in the existing VYNPS BWR storage rack modules was determined to be 0.9469 (95% probability at the 95% confidence level) including g all known calculational and manufacturing uncertainties. [S@lR3dSEM26533
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