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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 1999-08-04
[Table view] Category:TEST REPORT
MONTHYEARML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20086N3171995-07-19019 July 1995 Four-YR Performance Test Rept ML20045D6521993-12-31031 December 1993 Summary Rept,Reactor Containment Bldg Ilrt,Point Beach Nuclear Plant,Unit 1,1993. ML20059H4361993-12-14014 December 1993 Rev 1 to Third Interval of Pbnp ASME Section XI Periodic Pressure Test Program ML20126A1011992-12-14014 December 1992 Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Unit 2 ML20077R9931991-08-16016 August 1991 Cycle 19 Startup Rept ML20006A3511990-01-0909 January 1990 Cycle 16 Startup. W/900118 Ltr ML20005E2351989-12-31031 December 1989 Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Nuclear Plant Unit 2, Summary Rept ML20245J1091989-07-25025 July 1989 Wisconsin Electric Power Co Point Beach Nuclear Plant Unit 1 Cycle 17 Startup May 1989 ML20153G3481987-11-25025 November 1987 Rev 1 to Irradiation Study of Boraflex Neutron Absorber Interim Test Data, Interim Technical Rept ML20207E5321986-12-29029 December 1986 Summary Rept:1986 Unit 2 Integrated Leakage Rate Test ML20197H5651986-05-13013 May 1986 Reanalysis of Main Steam Line Outside Containment W/Energy Absorbers as Replacements for Hydraulic Snubbers for Point Beach Nuclear Plant ML20204F1671985-12-31031 December 1985 Test Rept on Static Load Tests on Liner Plate Leak Chase Channel Assemblies. Supporting Data Rept Encl ML20107D6841985-01-31031 January 1985 Cycle 11 Startup ML20093D2651984-03-30030 March 1984 Type B & C Leakage Testing Summary for Period Between Oct 1981 Type a Containment Integrated Leak Rate Test (Cilrt) & Mar 1984 Type a Cilrt ML20062K1691982-07-31031 July 1982 Rept of Reactor Containment Bldg Integrated Leakage Rate Test for Point Beach Unit 2 ML20011A4691981-09-30030 September 1981 Compressive Strength of Prisms & Concrete Blocks. ML20011A4661981-09-30030 September 1981 Evaluation of Allowable Tensile Stresses Normal to Bed Joint. ML20011A4761981-09-30030 September 1981 Evaluation of Single Wythe Assumption to Represent Multiple Wythe Walls. ML20011A4631981-09-30030 September 1981 Evaluation of Allowable In-Plane Shear Stresses & Strains. ML19312F0181981-09-15015 September 1981 Concrete Block & Prism Testing. ML19247D5421981-01-15015 January 1981 Steam Generator Crevice Flow Test for Wi Electric Power Co. ML19330C0581980-08-0505 August 1980 Steam Generator Insp Results W/Comparison to Previous Insps. ML20126D7061980-04-25025 April 1980 Microscopic & Other Examinations of Nuclear Steam Generator Tubing Removed in Mar 1980 ML19320D5111979-12-28028 December 1979 Seventy-Two Hour Test of Turbine-Driven Auxiliary Feed Pump. ML19320D5231979-12-26026 December 1979 Seventy-Two Hour Test of Electrically-Driven Auxiliary Feed Pump. ML19320D5261979-12-23023 December 1979 Seventy-Two Hour Test of Electrically-Driven Auxiliary Feed Pumps. ML19320D5181979-12-0707 December 1979 Seventy-Two Hour Test of Turbine-Driven Auxiliary Feed Pump. ML20104A3871979-02-28028 February 1979 Inservice Test Plan,Feb 1979. W/Drawings of Reactor Coolant Sys Process,Safety Injection Sys & Chemical & Volume Control Sys ML20236X6381978-09-15015 September 1978 Rev 0 to Summary Rept of Equipment Qualification Analyses 1999-07-15
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EVALUATION OF SINGLE WYTHE ASSUMPTION TO REPRESENT MULTIPLE WYTHE WALLS Prepared for Point Beach Nuclear Power Plant, Units 1 and 2 WISCONSIN ELECTRIC POWER COMPANY Milwaukee, Wisconsin Prepared by I COMPUTECH ENGINEERING SERVICES, INC.
Berkeley, California September,1981 REPORT NO. R553.07 t
Revision 1 8110130463 811007 PDR ADOCK 05000266 O PDR
TABLE OF CONTENTS 1 INTRODUCTION . ... .. .. ... . 1 2 ANALYSIS METHODOLOGY . . . . ... . .. . 1 3 RESULTS . .. . . I 4 OISCUSSION OF RESULTS 2 5 CONCLUSIONS . . .. . . . . 2 4
1 INTRODUCTION The Nuclear Regulatory Commission (NRC) staff on June 9-11. 1981 reviewed the criteria and calculations performed on IE Bulletin 80-11 " Masonry Walt Design' for the Point Beach Nuclear Power Plant. Action item 5 resuliing from the review meeting stated that with regard to out-of-plane loading. the licensee shall demonstrate that the use of the single wythe assumption for multiple wythe walls results in a conservative evaluation with respect to frequency shift and out-of-plane dr ,t consideration.
. , short report p esents the analyses that were, performed. ine resuits of ine a.1alyses, a discussion of the results, and the conclusions.
2 ANALYSIS METHODOLOGY All walls were analyzed in accordance with the procedures given in " Criteria for the Re-evaluation of Concrete Masonry Walls for Point Bear.h Nuclear Power Piant." Specifically, plate analysis was used to assess the out-of plane response cf the wall. The computer program SAPSA was used to perform a f nite element cynamic analysis, utilizing the response spectrum method.
All wythes in a multlwythe wall were assumed to respond as single wythe walls because of the difficulty in verifying the adequacy of the collar joint between the wythes. This was assumed to be conservative when using the ro-evaluation criteria and the objective of Action item 5 ls to validate the degree of conservatism.
Two double wythe walls (Wall Nos. 24 and GS-D were selected to compare the results obtained from the wall acting either as a single or double wythe wall using the re-evaluation criteria. In using the re-evaluation criterla the walls were assumed to have pinned supports at all appropriate boundsries. As a consequence no forces are induced in the wall due to out-of-plane drift.
The validity of this assumption is addr1ssed in Computech Engineering Services. Inc. Report No. R553.11. Some of the results of Report No. R553.11 are included in this report for the purpose of addressing Action item 5. Wall 24 is 164 inches long 156 inches high and consists of two wythes of twelve Inch wide units. Wall 65-1 is 109 inches long.176 inches high ano consists of two wythes of six inch wide units. Each wall was analyzed as both a sir.gle and double wythe wall using the same number of nodes, mesh size and boundary conditions. Two boundary conditions were used for each wall; one simply supported on each boundary and the otner fixed. For the fixed boundary condition the out-of-plane drift effects were included as reported in Report No. W3.11.
3 RESlJLTS The results of the analyses performed using the simply supported boundary conditions are Ol ven in Table 1 and 2. Table 1 compares the frequencies of each wall acting either as a single or double wythe wall. Table 2 compares the maximum stress ratlos for each wall acting eittier as a single l I
L 1
or double wythe wall. The valu. , given in Table 2 are based on the procedures given in the re-evaluation criteria. That is the walls are assumed to have simply supported boundary conditions.
The results given in Table 3 are extracted from Report No. R553.11 and provide a comparison of the single or double wythe wall with fixed boundary conditions incorporating the effects of out-of-plane drift.
4 DISCUSSION OF RESULTS From the results presenwd in Table 1 it is clear that the single wythe assumption is conservative eith respect to frequency shift. The fundamental or first mode frequency of the double wythe wall is approximately twice that of the single wythe wall. For walls with more than two wythe.s the shift in frequency would be even greater. The effect of out-of-plane drift effects depends on how this is incorporated in the analysis of the walls and is further discussed in Report No. R553.11. For the case of simply supported boundary conditions, out-of-plane drift does not induce forces in the walls and the maximum stress ratios given in Table 2 indicate that the maximum stressss in the wali due to other out-of-p!ane forces for the double wythe wall are approximately one-half of those of the corresponding single wythe wall.
For the case of fixed boundary conditions, incorporating out-of-plane drift effects, the results given in Table 3 indicate that the maximum stress ratios for the double wythe walls are from 1 to 130 percent less than the corresponding single wythe walls. Therefore, for Walls 24 and 65-1 the use of the single wythe assumption to represent double wythe walls results in a conservative evaluation regardless of how out-of-plane drift effects are incorporated.
5 CONCLUSIONS Two walls were selected to demonstrate that the use of the single wythe assumption for multiple wythe walls results in a conservatNa evaluation with respect to frequency shift and out-of-plane drift wasiderations. The results indicate that the frequency of the double wythc. walls are almost twice those of the equivalent single wythe wall. Therefore, from frequency shift considerations the use of the single wythe assumption is conservative.
The impact on out-of-plane drif t considerations depends on how this is incorporated in the analysis. With the method used in the re-evaluation criteria no forces are Induced in the wall due to out-of-plane drift effects and the maximum stress ratios from other out-of-plane fi tces in the double wythe wall are approximately one-half of those in the single wythe wall. If fixed boundory conditions are used and out-of-plane drif t effects are included, then the maximum stress ratios in the double wythe walls were 1 to 130 percent less than those in the single wythe wall.
The single wythe assumption is therefore conservative for the procedures specified in the re-evaluLtion criteria and is reasonably conservative for the procedure of including out-of-plane drift effects specified in Report No. R553.11.
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TA3LE 1 FREQUENCY OF WALLS WITH SIMPLY SUPPORTED BOUNDARY CONDITIONS Wall No. Thickness Wythos Frequancies (!!z) 12 1 15.39, 37.72 24 25 2 32.06, 78.57 ,
6 1 15.28, 24.99, 43.97 65 -1 g
12 2 30.56, 49.98, 87.95 TABLE 2 MAXIMUM STRESS RATIOS OF WALLS WITH SIMPLY SUPPORTED BOUNDARY CONDITIONS Wall No. Thickness Wythes Mx/Mxa My/Mya 12 1 24
.4057 .1699 25 2 .1809 .0751 6 1 .4834 .1572 65-1 12 2 .2146 .0697 Note: Subscripts x and y denote stress ratios on horizontal and vertical strips respectively 3
- . g TABLE 3 MAXIMUM STRESS RATIOS OF WALLS WITH FIXED BOUNDARY CONDITIONS INCLUDING OUT-OF-PLANE DRIFT EFFECTS Wall No. Thickness Wythes Mx/Mxa My/Mya 12 1 0.265 0.228 24 25 2 0.129 0.226 6 1 0.264 0.136 65-1 12 2 0.117 0.097 Note: Subscripts x and y denote stress ratios on horizontal and vertical strips respectively S
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