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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20236D9111987-10-26026 October 1987 Safety Evaluation Re Reactor Coolant Pump Flywheel Integrity.Matl,Fabrication,Design & Insp Aspects of Flywheels Acceptable 1987-10-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20024H1211991-04-30030 April 1991 Safety Evaluation Report Related to the Preliminary Design of the Standard Nuclear Steam Supply Reference System,Resar SP/90.Docket No. 50-601.(Westinghouse Electric Corporation, Inc.) ML20012E9321990-03-31031 March 1990 SP/90 Position on Severe Accident Policy Issues ML20247G3801989-08-31031 August 1989 RESAR-SP/90 Pda Response to Draft SER Open Issues 82-107 ML20248H8501989-08-31031 August 1989 Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20235N4791989-01-31031 January 1989 Amend 1a to RESAR-SP/90 Pda Module 7, Structural/Equipment Design ML20235N4951989-01-31031 January 1989 Amend 2 to RESAR-SP/90 Pda Module 7, Structural/Equipment Design ML20206F8861988-11-30030 November 1988 Amend 4 to RESAR-SP/90 Pda Module 5, Reactor Sys ML20195C7931988-10-31031 October 1988 Amend 2 to Westinghouse Advanced PWR RESAR-SP/90 Pda Module 4, Rcs ML20153F7341988-08-31031 August 1988 Amend 3 to Module 3, Introduction & Site ML20151T8661988-08-31031 August 1988 Nonproprietary Amend 4 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20207J9601988-08-31031 August 1988 Nonproprietary Version of Amend 4 to RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20151R6361988-07-31031 July 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 12, Waste Mgt ML20151N4321988-07-31031 July 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 11, Radiation Protection ML20154H5011988-05-31031 May 1988 Non-proprietary Amend 1 to RESAR-SP/90 Pda Module 4, Rcs ML20154F0811988-05-31031 May 1988 Amend 3 to Nonproprietary RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20154F0641988-05-31031 May 1988 Amend 1a to Nonproprietary RESAR-SP/90 Pda Module 1, Primary Side Safeguards Sys ML20154E9521988-04-30030 April 1988 Nonproprietary Amend 3 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20151Y0501988-04-30030 April 1988 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20154H6701988-03-31031 March 1988 Nonproprietary Amend 1a to RESAR-SP/90 Pda Module 3, Introduction & Site ML20234C5271987-11-30030 November 1987 Nonproprietary Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 9, Instrumentation & Controls & Electric Power ML20236V0721987-10-31031 October 1987 Nonproprietary Amend 2 to RESAR-SP/90 Pda Module 1,Primary Side Safeguards Sys ML20236V0741987-10-31031 October 1987 Nonproprietary Amend 1 to RESAR-SP/90 Pda Module 13, Auxiliary Sys ML20236D9111987-10-26026 October 1987 Safety Evaluation Re Reactor Coolant Pump Flywheel Integrity.Matl,Fabrication,Design & Insp Aspects of Flywheels Acceptable ML20236E9251987-09-30030 September 1987 Nonproprietary Amend 3 to Westinghouse Advanced PWR RESAR-SP/90 Preliminary Design Approval Module 16, Probabilistic Safety Study ML20236F6991987-09-30030 September 1987 Nonproprietary Amend 1 to RESAR-SP/90 Pda Module 2, Regulatory Conformance ML20207S2621986-11-30030 November 1986 Chapter 2, Site Characteristics, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3811986-11-30030 November 1986 Chapter 18, Human Factors Engineering, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3781986-11-30030 November 1986 Chapter 17, QA, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3751986-11-30030 November 1986 Chapter 16, Tech Specs, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3671986-11-30030 November 1986 Chapter 14, Initial Test Program, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3691986-11-30030 November 1986 Chapter 15, Accident Analyses, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3631986-11-30030 November 1986 Chapter 13, Conduct of Operations, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3541986-11-30030 November 1986 Chapter 12, Radiation Protection, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3381986-11-30030 November 1986 Chapter 11, Radwaste Mgt, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3321986-11-30030 November 1986 Chapter 10, Steam & Power Conversion Sys, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3221986-11-30030 November 1986 Chapter 9, Auxiliary Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3051986-11-30030 November 1986 Chapter 8, Electric Power, to Nonproprietary RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S3001986-11-30030 November 1986 Chapter 7, Instrumentation & Controls, to RESAR/SP-90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2941986-11-30030 November 1986 Chapter 6, ESF, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2781986-11-30030 November 1986 Chapter 5, RCS & Connected Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2681986-11-30030 November 1986 Chapter 3, Design of Structures,Components,Equipment & Sys, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20207S2581986-11-30030 November 1986 Chapter 1, Introduction & General Description of Plant, to Nonproprietary RESAR-SP/90 Westinghouse Advanced PWR, Module 10, Containment Sys ML20207R9661986-11-30030 November 1986 Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20214L5501986-11-30030 November 1986 Nonproprietary Amend 1 to RESAR-SP/90 Preliminary Design Approval Module 6/8, Secondary Side Safeguards Sys/Steam & Power Conversion ML20207S2731986-11-30030 November 1986 Chapter 4, Reactor, to Nonproprietary RESAR-SP/90 Westinghouse Advanced Pwr,Module 10, Containment Sys ML20213F7021986-10-31031 October 1986 Nonproprietary Chapter 1, Introduction & General Description of Plant, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7121986-10-31031 October 1986 Nonproprietary Chapter 3, Design of Structures,Components, Equipment & Sys, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7551986-10-31031 October 1986 Nonproprietary Chapter 9, Auxiliary Sys, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20213F7291986-10-31031 October 1986 Nonproprietary Chapter 8, Electric Power, of RESAR-SP/90 Westinghouse Advanced PWR Module 13, Auxiliary Sys ML20215M8681986-10-31031 October 1986 Nonproprietary RESAR-SP/90 Westinghouse Advanced PWR Std Plant Design Module 15, Control/Human Factors Engineering 1991-04-30
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ENCLOSURE:1' m
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UNITED STATES -
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j SAFETY EVALVATION BY THE OFFICE OF NUCLEAR REGULATION CONCERNING REACTOR COOLANT PUMPS (FLYWHEEL INTEGRITY)
.i FOR.
. WESTINGHOUSTTESAR SP/90 DOCKET NO. 50-601 l
5.4'1.5
. PUMP FLYWHEEL INTEGRITY.
The. safety objective of this review is to assure that the integrity of the primary reactor coolant' pump flywheel is maintained to prevent failure at normal operation speeds and speeds that might be reached under accident conditions and thus preclude the' generation of missiles.
The basis for review is ' outlined in St'andard Review Plan (SRP), Section 5.4.1.1 and the Regulatory Guide 1.14. which describes and recommends a method acceptable to the NRC staff in implementing General Design Criterion 4, " Environmental and'Hissile Design Bases" of Appendix A of L10 CFR Part 50 with regard to minimizing the. potential for failure of flywheels of the reactor coolant pump.
. EVALUATION-(a) Materials and Fabrication The flywheel consists of two. thick plates bolted together.
Each plate is fabricated from SA-533, Grade B, Class '..; teel. The flywheel material is produced by a process that minimizes flaws in the material and-improves its fracture toughness properties. -The materials as well as-finished flywheels are subjected to 100 percent
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volumetric ultrasonic inspection using procedures and acceptance standardsspecified'ipijectionIIIoftheASMECode.
The nil-ductility transition temperature (NDTT) of the flywheel material is no higher than 10 F.
The Charpy V-notch energy level is at least 50 foot-pound with a 35-mil lateral expansion at 70'F in both the parallel and normal orientation with respect to the rolling direction of the flywheel material.
Hence, the reference j
temperature RTNDT. of the 10 F can be assumed.
(b) Design Basis j
i The calculated stresses at the operation speed, due to centrifugal l
forces and the interference fit on the shaft are within the j
Regulatory Guide 1.14 limit. The pump runs at about 1190 rpm and j
- E may operate briefly at overspeed up to 110 percent during the loss l
of outside power. The design speed is 125 percent of the operating j
speed; hence, the flywheels are also tested at 125 percent of the maximum synchronous speed of the motor. The combined stresses at the design overspeed, due to interference fit and centrifugal forces i
are within the Regulatory Guide 1.14 limit.
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The flywheels can be inspected by reiaoving the cover; hence, any:
- The inservice inspection crack.that developed can be noticed.
program, a 100% volumetric ultrasonic inspection,'follows requirements of Section XI of the ASME Code and the recommendations of Regulatory Guide'1.14.
(c) Conclusion-l We have' reviewed:the material, fabrication, design and inspection aspects of the pump flywheels for conpliance with Regulatory Guide-1.14. We have concluded that the structural integrity of the flywheels is'. adequate to withstand the forces imposed.by overspeed transients without the loss of function, and the flywheel will be inspected periodically to assure that the integrity is maintained.
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ENCLOSURE.2-
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y REQUEST FOR ADDITIONAL INFORMATION RELATEC:TO WESTINGH0VSE RESAR SP/90 DESIGN
-MATERIALS ENGINEERING ASPECTS DOCKET NO.- 50-601 1.
-SRP Section 6.2.7, Fracture Prevention of Containment Pressure
. Boundary. is addressed in Module 1. Section 6.5.4.
The response to l
-the: requirements of the fracture.' toughness criteria for Class 2 ferritic materials used for all containment; pressure boundary' 1
components be determined by the Sunmer 1977 Addenda of Section III.
of the ASME Code is.too general. We cannot determine the l
acceptability of the materials within the context of General Design-Criterion 51. The materials fracture toughness must meet the requirements of Class 2 Components of the Summer 1977 Addenda of-Section III or.their equivalent.
252.1 Verify that the aging and tempering temperatures of heat treatable.
i materials used in the control rod drive mechanisms are specified to eliminate susceptibility)to stress corrosion cracking in reactor coolant (4.5.1, Module 5 252.2 What materials, cther than austeniti: stainless steels of limited coldwork-(maximum yield strength of 30 ksi) are used for reactor internals? (4.5.2, Module 5) 252.10 What is the basis (date, experiments, experience, etc.) for the use of Incoloy 800 as tube support plate material? (5.4.2.1, Module 4) 252.11 What steps have been taken to avoid corrosion / erosion of J tubes attached to the feedwater ring? (5.4.2.1, Module 4) 252.12 What are the fracture toughness requirements.for ferritic steel pressure boundary components in ESF systems? (6.1.1, Module 1,10) 252.13 What are.the fracture toughness requirements for ferritic steel l
pressure boundary components in main steam and feedwater gj; components?(10.3.6, Modules 6&8)
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