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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 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 ML20205F6631999-03-0404 March 1999 Jet Pump Riser Weld Leakage Evaluation ML20151U0361998-08-28028 August 1998 Non-proprietary Rev 1 to Holtec Rept HI-981932, Vermont Yankee Nuclear Power Station Spent Storage Expansion Project 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 ML20247J8341998-05-31031 May 1998 Peak Suppression Pool Temp Analyses for Large Break LOCA Scenarios, for May 1998 ML20247E6521998-04-30030 April 1998 Rev 0 to GE-NE-B13-01935-01, Jet Pump Riser Welds for RS-1 Indications Evaluation Rept for Vermont Yankee 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 ML20247E6221998-04-30030 April 1998 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 ML20210T5551997-09-10010 September 1997 Addl Benchmarking of BWR Using CASMO-3/SIMULATE-3 ML20210H1111997-07-0707 July 1997 Consequence Evaluation of Vynp Class 1 Piping in Support of ASME Code Case N-560 ML20148D8581997-05-0707 May 1997 Advanced Offgas Follow-up Rept ML20138H3351997-04-28028 April 1997 Tech Specs for Offsite Power ML20138H3081997-04-28028 April 1997 Compliance W/Sbo Regulation ML20107D5951996-04-30030 April 1996 Rev 0 to Vermont Yankee Nuclear Power Station Core Shroud Repair Summary ML20094D8351995-09-22022 September 1995 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 ML20106G5451995-01-17017 January 1995 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 ML20086G4141991-11-0606 November 1991 Emergency Response Exercise Manual 1991 ML20091B2281991-01-31031 January 1991 Simulator Certification Rept,Vermont Yankee Training Dept Jan 1991 ML20247G9901989-06-30030 June 1989 Rev 0 to Vermont Yankee Cycle 14 Core Operating Limits Rept ML20245L1821989-06-30030 June 1989 Method for Generation of One-Dimensional Kinetics Data for RETRAN-02 ML20247G2531989-03-21021 March 1989 Rev 3 to Vermont Yankee Procedure Generation Package ML20151E0111988-07-15015 July 1988 Impact of Alternate Testing on Component & Sys Availability ML20151H9581988-04-30030 April 1988 CASMO-3G Validation ML20154K3351988-04-29029 April 1988 Rept on Containment Safety at Vermont Yankee ML20147G3371988-02-29029 February 1988 Justification for Long-Term Operation for Vermont Yankee Core Spray Nozzle Weld Overlays ML20153H0451987-12-31031 December 1987 Shutdown Assessment of Vermont Yankee Nuclear Power Facility, Interim Rept to State of Vt General Assembly ML20216J6571987-06-25025 June 1987 Dcrdr Summary Rept Suppl for Vermont Yankee Nuclear Power Plant ML20234D8131987-05-31031 May 1987 Cycle 13 Core Performance Analysis ML20206H7331987-03-31031 March 1987 Thermal Effects on Precoat Matl for Spent Fuel Pool Filter/ Demineralizers,Vermont Yankee Nuclear Power Station ML20205Q5421987-03-31031 March 1987 Evaluation of Matl Performance Suitability of New Vermont Yankee Spent Fuel Storage Rack Design ML20207Q3461987-01-12012 January 1987 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 ML20212Q2731986-08-31031 August 1986 Containment Safety Study ML20204F6001986-07-30030 July 1986 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 ML20101S8291985-01-31031 January 1985 Functional SPDS Sar ML20094M9991984-08-10010 August 1984 Rev 2 to Environ Qualification Master Equipment List 1999-06-23
[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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TECHNICAL DOCUMENT COVER SHEET DOCUMENT NUMBER: VY9123-TD01 REV: 0 DOCUMENT TITLE: JET PUMP RISER WELD LEAKAGE EVALUATION PROJECT NAME: Supplemental Riser Weld Leakage Documentation PROJECT NUMBER: 00241.30.9123.00.0 CLIENT: Vermont Yankee Nuclear Power Corporation QA CONDITION I I
l DESIGN VERIFICATION METHOD:
O Design Review O Altemate Calculation O Qualification Testing Preparer Verifier Approver Signature
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. GooMn U J. S. Hsieh F M. WGyek Printed Name Date 3 - M- //(( d f f g [
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PDR ADOCK 05000271 P PDR 00241.30.9123.00.00000 Page1of5
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Duke Engineering andServices yy9;y3 399;
! JET PUMP RISER WELD LEAKAGE EVALUATION 1
Executive S'ummary Leakage rates through flawedjet pump riser welds found during the 1998 outage at Vermont Yankee were calculated reflecting the end of two subsequent cycles. The leakage rates were calculated using adjusted flaw lengths accounting for measurement uncertainty and IGSCC crack growth. The leakage rates were '
calculated for normal operation and post-LOCA conditions with pressure drops of 123 and 13 psid respectively.
l Leakage Rate, gpm l Weld ID Length for Analysis, Normal Operation LOCA Conditions !
inches 1 28.04 9.12 N2B-RS-1 5.83 28.04 9.12 N2C-RS-1 5.83 N2H-RS-1 3.85 18.52 6.02 f 28.04 9.12 l N2K-RS-1 5.83 l
l 00241.30.9123.00.00000 Pcge 2 of 5
J, u i Duke Engineering andServices VY9123-TDo1 JET PUMP RISER WELD LEAKAGE EVALUATION
Introduction:
To address the recommended strategy on Jet Pump Leakage (Reference 1), a detailed calculation of leakage rates and assessmem ofleakage acceptability for two cycles of operation was completed in Reference 2. Reference 2 conservatively examined leakage through the fourjet pump riser welds determined to be flawed following ultrasonic inspection (Reference 3).
- In Reference 2 the flaws were rssumed to have an equal length of 5.83 inches following an additional two cycles of flaw growth beyond that most recently measured. As reported in Reference 3, the flaw length of weld N2H-RS-1 was measured at a significantly smaller value then the other flawed welds. This 'i document modifies the detailed calculation documented in Reference 2 to reflect the smaller flaw length measured for that weld.
Inputs and Assumptions: .
- 1. Vermont Yankee riser differential pressure at nonnal operating conditions as found in the plant specific database and referenced in Reference 3 (DP = 123' psi).
- 2. Vermont Yankee riser differential pressure for post-LOCA conditions as described in Reference 3.
(DP = 13 psi). ;
- 3. The calculated IGSCC crack growth for two eighteen months cycles is based on a growth rate of 5E-5 inch / hot hour (Reference 4).
- 4. Per reference 4, a " Flaw Handbook" has been developed by General Electric for Vermont Yankee to identify the critical Flaw size for each of the jet pump circumferential welds. It was determined that the RS-1 welds could contain a flaw as large as 16.41" long and still satisfy structural integrity requirements.
- 5. The two-cycle time frame is assumed to be 26,280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br /> (Reference 5).
- 6. No additional cracks are assumed to initiate during the period between inspections.
- 7. As reported in Reference 3,26 of 30 welds were ultrasonic testing (UT) inspected. The remaining four welds were inspected using a modified visual, VT-1, inspection technique. The only flaws identified !
. were those found with using the UT technique.
- 8. Per Reference 4, the UT weld measurement has an uncertainty of 0.19 inches per end or 0.38 inches total.
Calculation..
Flaws Contributing to Leakane As described in Reference 3, four thermal sleeves to elbow welds were identified with existing flaws. To each measured flaw length a measurement uncertainty is acuunted for by adding a 0.191-inch evaluation factor to each end on the measured length. Additionally, to account for flaw growth due to Intergranular Stress Corcosion Cracking (IGSCC) for a two-cycle 36-month time frame (26,280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br />) an additional length is added using a flaw growth rate of SE-5 in/hr (Reference 4) that equates to a growth of 26,280 x 5E-5 = 1.314 inch growth per end.
00241.30.9123.00.00000 Page 3 of 5
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Duke Engineering andServices VY9123-TD01 JET PUMP RISER WELD LEAKAGE EVALUATION Summarizing:
Weld Measured Length, Evaluation Factor Two Cycle Growth, Predicted Length for inches per end, inches per end, inches Analysis, inches N2B-RS-1 2.82 0.191 1.314 5.83 N2C-RS-1 2.82 0.191 1.314 5.83 N2H-RS-1 0.84 0.191 1.314 3.85 N2K-RS-1 2.82 0.191 1.314 5.83 Note that the predicted flaw length following two cycles is smaller than the limit for structural integrity as identified in Inouts and Assumotions: number 4.
Leakage Rate Calculation The leakage rate through the through-wall flaw can be estimated using assuming incompressible Bemoulli flow through the crack.
As described in Reference 2:
Q = CA 4 (2 g, AP/p)
Where: Q= Leakage (ft'/sec)
C= flow coefficient 2
A= Area (ft )
p= mass density of fluid at 520 F,Ib/ft' 2
AP = pressure difference across the pipe, Ib/ft 2
ge= 32.2 ft/sec To complete the calculation the flow area is assumed to correspond to a rectangular slot using the flaw length with a width of 10 mils as described in Reference 2. A AP value of 123 psi for normal operation was used in Reference 3 and will be used in this calculation. Per Reference 3, a AP of 13 psi is used for LOCA conditions. An assumed value of 1 is assumed for the flow coefficient (C), as was used in References 2 and 3. The following calculation is provided as an example; Q = 1.0 * (0.010 inch
- 5.83 inch)/1442in ffg2 *Y (64.4 ft/sec2
- 1442 in fp ,123 lb/ in2 / 47.9 lb/ft')=
= 6.248 e-2 ft' /sec = 28.04 gpm The resulting flow rates are:
Leakage Rate, gpm Weld Length for Analysis, inches Normal Operation LOCA Conditions 28.04 9.12 N2B-RS-1 5.83 28.04 9.12 N2C-RS-1 5.83 18.52 6.02 N2H-RS-1 3.85 28.04 9.12 N2K-RS-1 5.83 102.6 33.4 Total Flow Rate 00241.30.9123.00.00000 Page 4 of 5
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Duke Engineering and Services VY9123-TD01 JET PUMP RISER WELD LEAKAGE EVALUATION Leak, age Rate Acceptability Reference 2 evaluated the impact ofleakage through four identical through-wall weld flaws of 5.83 inches length. The results presented above reflect three flaw lengths of 5.83 inches and one of 3.85 inches. The total leakage flow rate calculated here for normal conditions are therefore lower. Based on the information presented in Reference 2, the following evaluation is provided.
Normal Ooeration i The total leakage through the jet pump welds during normal operation is 102.6 gpm. This represents less then 0.12 % of the rated core flow of 48 Mlb/hr. This additionalleakage will require the recirculation pumps to operate at a slightly higher speed at the rated core flow to compensate for the additional leakage bypassing the core.
The flow biased scram setpoint is automatically adjusted based on a calculated core flow from the i recirculation pump flow indication. Because the leakage occurs between the recirculation flow indication .
[ and the core flow indication at thejet pumps, this leakage would increase the actual flow difference I between the recirculation flow and thejet pump driving flow. However, because the recirculation flow is calibrated to the jet pump core flow indication, the additional leakage is accommodated in the calibration process. Therefore, this leakage does not impact the accuracy of the core flow measurement input to the flow biased scram setpoint. Consequently, there is no impact on the Anticipated Operational Transients, which credit the flow-biased scram.
LOCA Conditions The total leakage through thejet pump welds during LOCA is 9 gpm or less per weld. Since injection is credited in only one loop, the flow is decreased by leakage through only two welds. Using the worst case combination results in 18 gpm leakage. The 18 gpm ofleakage can be accommodated by the assumption of 500 gpm through the minimum flow bypass for one LPCI pump injecting in one loop and is accommodated by the conservatism in the analysis for two pumps injecting in one loop.
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References:
1 Memo J. Hoffman to D. Yasi, " Recommended Strategy for Jet Pump Riser Welds", OPVY 98/109,
- April 22,1998.
2 Calculation VYC-1864 , Rev 0 " Jet Pump Riser Weld Leakage Evaluation", dated February 4,1999 3 Letter from Donald A. Reid, Vermont Yankee Nuclear Power Corporation to U. S. Nuclear Regulatory Commission, BVY 98-67, dated May 4,1998 4 Report GE-NE-B13-01935-LTR, Rev 1, " Jet Pump Riser Welds Allowable Flaw Sizes Letter Report for Vermont Yankee", dated April 1998.
5 Memorandum from C. B. Larsen to L. Schor, " Jet Pump Flaw Lengths for Input to Leakage Calculation, Dated January 25,1999, TS 8/99 l
00241.30.9123.00.00000 Page 5 of 5