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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20217J5801997-08-0505 August 1997 Revised Pages to CAA-96-146, Criticality Analysis of Point Beach Nuclear Plant Spent Fuel Storage Racks Considering Boraflex Gaps & Shrinkage W/Credit for Integral Fuel Burnable Absorbers ML20140D0481997-04-15015 April 1997 Suppl to Evaluation of EQ Impact of Wepc TS Change Request 192 ML20147J2821997-03-10010 March 1997 Rev 2 to Potential Failure of Redundant SR Circuits,Within Mcb ML20140G9941997-02-27027 February 1997 MR 96-069*A, Replace Breakers in 1Y-06, MR 96-069*B, Replace Breakers in 1Y-05 ML20140H0121996-11-15015 November 1996 MR 96-070, Replace Breakers on 2Y-05/06 ML20117L0141996-09-30030 September 1996 Evaluation of Possible Water-Hammer Loads in Svc Water Sys for DBA Conditions ML20117L0051996-09-0909 September 1996 Rev 0 to Operability Assessment for Transient Conditions in Pbnp Svc Water Sys During Coincidental LOCA & Loop,Safety Related ML20141G8411996-05-14014 May 1996 Criticality Analysis of Point Beach Nuclear Plant Spent Fuel Storage Racks Considering Boraflex Gaps & Shrinkage W/ Credit for Integral Fuel Burnable Absorbers ML20096H0181996-01-16016 January 1996 Rev 1 to Seismic Evaluation Rept ML20096H0221996-01-16016 January 1996 Rev 1 to Relay Evaluation Rept ML20094M9461995-11-14014 November 1995 Repair Roll Qualification ML20087H5701995-06-30030 June 1995 Rev 0 to Seismic Evaluation Rept ML20087J7251995-06-30030 June 1995 Rev 0 to Relay Evaluation Rept ML20086B4951995-06-0202 June 1995 Rev 0 to Point Beach Nuclear Plant Emergency Action Technical Basis Document ML20081G4681995-02-27027 February 1995 Rev 0 to Evaluation of Covered Cable Trays in AFW Pump Room at Point Beach Nuclear Plant,Fire Zone 304 ML20078S3621995-02-17017 February 1995 Unit 2 Refueling 20 Repair/Replacement Summary Rept for Form NIS-2 ML20057D9391993-09-21021 September 1993 Rev 0 to Pbnp Diesel Generator Addition Project Design Summary ML17352A8691993-05-31031 May 1993 Technical Rept, Assessment of Aging Degradation of Civil/ Structural Features at Selected Operating Nuclear Power Plants. ML20086U1171992-01-0707 January 1992 Rev 0 to Eighteen-Yr Inservice Tendon Surveillance Test Rept,Units 1 & 2 Containment Bldg Post-Tensioning Sys ML20082D4651991-07-22022 July 1991 Wisconsin Electric Power Co Point Beach Nuclear Plant Simulator Certification Rept - Jul 1991 ML20081M7581991-06-27027 June 1991 Addendum to Annual Results & Data Rept for 1987,1988 & 1989 Point Beach Units 1 & 2 ML20247C5971989-04-30030 April 1989 Containment Liner Plate Leak Chase Channel Pressure Boundary at Point Beach Units 1 & 2 ML17251A4811989-02-28028 February 1989 Ultrasonic Indication Sizing Technique Development. Related Info Encl ML20195C3001988-10-31031 October 1988 Final Rept for Increased Peaking Factors & Fuel Upgrade Analysis ML20153G7751988-08-31031 August 1988 Safety Evaluation for Increased Peaking Factors & Fuel Upgrade at Point Beach Nuclear Plant Units 1 & 2 ML20154H2571988-04-25025 April 1988 Supplemental Analyses & Comments/Responses to Epri/Wog Analysis of Decay Heat Removal Risk at Point Beach ML20154H1511988-03-31031 March 1988 Difference Between Sandia & NUMARC Analysis of Decay Heat Removal Related Risk for Point Beach ML20154H1871988-03-30030 March 1988 Final Draft Supplemental Analyses & Comments/Responses to Epri/Wog Analysis of Decay Heat Removal Risk at Point Beach ML20148C9851988-02-29029 February 1988 Response to 10CFR50,App R 'Alternate Shutdown Capability,' 4,160 Volt Switchgear Room ML20236Y0941987-10-21021 October 1987 Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Final Rept ML20235J3751987-08-31031 August 1987 Rev 1 to Evaluation of Pressurizer Safety & Relief Valve Sys Final Rept ML20236D3901987-07-22022 July 1987 Summary Rept:Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Nuclear Plant Unit 1,1987 ML20236J7371987-07-0101 July 1987 Partially Withheld Final Rept of Ad Hoc Investigation Committee for 870619 Release. Related Info Encl ML20215B6761987-06-0202 June 1987 Evaluation & Analysis of Point Beach Nuclear Plant Unit 1, Reactor Vessel Safety Injection Nozzle-to-Shell Weld Indication ML20205P5461987-03-31031 March 1987 Crdr Summary Rept ML17347B6741987-02-11011 February 1987 Results of Boraflex Exam,Point Beach Nuclear Plant. ML20236N4481987-01-21021 January 1987 Rev 3 to Emergency Operating Procedures, Training Course Syllabus ML20204F1541986-06-30030 June 1986 Evaluation of Containment Liner Plate Leak Chase Channel Sys for Point Beach Nuclear Plant Units 1 & 2 ML20086U1111985-05-15015 May 1985 Containment Bldg Post-Tensioning Sys Thirteen-Yr Surveillance ML20115G3561985-04-30030 April 1985 Radwaste Cost-Benefit Analysis ML20087N4381984-03-30030 March 1984 Sizing of Ultrasonically Detected Indications in Point Beach,Unit 1 Reactor Pressure Vessel Outlet Nozzles ML20087N4431984-03-27027 March 1984 Reactor Vessel Outlet Nozzle-to-Shell Weld Flaw Indication Fracture Mechanics Evaluation for Point Beach Nuclear Plant, Unit 1 ML20087K2161984-03-0505 March 1984 Westinghouse Safety Evaluation,Cracked Control Rod Guide Tube Support Pins ML20107F2701984-01-31031 January 1984 Nonproprietary Software Design Rept for Class a Model & Meteorological,Radiological Effluent & Dose Repts for Point Beach Nuclear Plant ML20080K9511983-12-31031 December 1983 Criteria for Determining Duration of Integrated Leakage Rate Tests of Reactor Containments ML20081E5171983-10-31031 October 1983 Final Rept,Response to 10CFR50 App R `Alternate Shutdown Capability.' ML20077M4371983-08-31031 August 1983 Safety Evaluation for Point Beach Units 1 & 2 Transition to Westinghouse 14X14 Optimized Fuel Assemblies ML20072L9751983-06-0808 June 1983 Present Status & Projected Future Progression of Steam Generator Tube Corrosion/Degradation at Point Beach Unit 1, Wisconsin Electric Power Co,Two Creeks,Wi ML20072C4431983-03-0101 March 1983 Amend 1 to Steam Generator Repair Rept 1999-06-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
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ACTION ITEM 16 COMPARISON BETWEEN FINITE ELEMENT PLATE ANALYSIS AND ONE WAY BEAM ACTION Prepared for Point Beach Nuclear Power Plant, Units 1 and 2 WISCONSIN ELECTRIC POWER COMPANY willwaukee, Wisconsin Prepared by COMPUTECH ENGINEERING SERVICES, INC.
Berkeley, California September,1981 REPORT NO. R553.12 hh OO G
TABLE OF CONTENTS
.. 1 1 INTRODUCTION . . . .. .... ... .
1 2 ANALYSIS METHODOLOGY . . . . . . . .. .. .. .....
1 3 RESULTS .. ....... .. . .. .. .
2 4 DISCUSSION OF RESULTS .... . ..... .. .
2 5 CONCLUSIONS .... .... ... ..... ... .. .
.)
1 INTRODUCTION The Nuclear Regulatory Commission (NRC) staff on June 9-11,1981 reviewed the criteria and calculations performed on IE Bulletin 80-11
- for the Point Beach Nuclear Power Plant. Action item 16 resulting from the review meeting stated that the licensee will provide comparative analyses on three types of Point Beach masonry walls (four s! des simply supported, three sides simply supported, and two sides - vertical and horizontal - simply supported) using both the plate assumption and one-way beam action in two orthogonal directions.
This short report is in response to that action item and presents the analysis methodology, the analysis results, 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 the Point Beach Nuclear Power Plant." Specifically, a finda element plate analysis was used to assess the out-of-plane response of the wall. The computer program SAPSA was used to perform the finite element dynamic analysis, utill::ing the response spectrum method.
This method of anclysis was selected because it was capable of explicitly incorporating the effects of equipment and pipe loads. openings due to doors, pipes and cable trays, and different boundary conditions.
In order to provide a comparative analysis based on a beam solution, the formulation of the beam sclution is derived as follows. The beam was assumed to be uniform and prismatic. The fundamental frequency and mode shape was calculated with either simply supported or cantilever coundary conditions and these were then used to calculate the maximum moment in the beam. The relevant formulas for the simply supported beam and cantilever beam are given in Table 1.
3 RESULTS A summary of the maximum mornents obtained on both horizontal and vertical strips for two walls (19/9 and 20/9) with four sides simply supported, for one wall (65-1/15) with two sides simply supported, and for two walls (111-1/23 and 113/23) with three sides simply supported are given in Table 2.
In the case of the two walls with four simply supported sides the beams were simply supported in both the horizontal and vertical directions. In the case of the two walls with three simply supported sides the beams were simply supported in the horizontal direction and a cantilever in the vertical direction :!nce the wall was not supported at the top. In the case of the wall with two simply supported sides the beams were Cantlievers in both the horizental and vertical directions.
1
4 DISCUSSION OF RESULTS The maximum moments caiculated on a vertical strip from the beam formulae were all greater than ti e maximum moments calculated from the plate analysis. The maximum moments calculated on a horizontal strip from the beam formulae were greater than the maximu.n moments calculated from the plate analysis for the walls with four and two sides simply supported. For the walls with three sides simply supported the maximum moments obtained from the beam formulae were less than those calculated from the plate analysis.
For the examples given a beam analysis of walls in both orthogonal directions and simply supported on four and two sides would be conservative. For the examples given of a wall supported on three sides and not on the top a beam analysis would have produced non-conservative results if the wall had been assumed to span or1y in the horizontal direction. If, however, it had been checked as a cantilever beam in the vertical dir,ection, the vertical moments would have exceeded those obtained from a chie analysis.
5 CONCLUSIONS The walls at Point Ocach Nuclear Power Plant were dynamically analyzed as finite element plates so that the effects of equipment and pipe loads, door and other openings and different boundary conditions could be explicitly included in the analytical results. If beam analyses had been used on walls with two and four sides simply supported this method of analysis would have been conservative for the three examp!es given. If beam analyses had been used for walls with three simply supported sides and they had been assumed to span in only the horizontal direction then a beam analysis would have been non-conservative.
It is clear that a beam analysis may not always produce con'lervative results and furthermore it is very difficult to account for the effects of openings and equipment and pipe loads in a beam analysis. Therefore the finite element plates used to analyze the walls is considered to produce a realistic evaluation of the stresses in the walls and to accurately account for the effects of openings and equipment loads.
2
d TABLE 1 FORMULAE FOR BEAMS Simply Supported Beam Cantilever Beam Fundamental tr I (1.875)2 EI
- -r Frequency 2 m L" 2u liiL Fundamental Mode Shape sin 1*
L sin ax - sinh ax + 0.742 (cosh ax -
cos ax) a = 1.875/L Maximum g ( L_ ) a ~y L m
Moment u 2.3700 E = modulus of elasticity I = modulus of inertia iii = mass per unit length L = span length 0 = seismic acceleration 3.
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TABLE 2 COMPARISON OF MAXIMUM MOMENTS OBTAINED E ROM PLATE AND BEAM ANALYSES Wall No. Status Mx Mxb Mx Mb y
19/9 P 398.9 565.7 184.7 988.1 Four Sides U 319.8 469.9 148.1 823.4 20/9 P- 173.9 313.2 122.7 989.2 Four Sides U 142.2 259.9 100.3 824.3 64-E/15 G~ 85.96 223.64 103.2 1351.70 Two Sides U 44.58 121.37 53.51 653.07 111-1/23 P 205.8 103.6 202.7 999.2 i Three Sides U 179.9 90.4 176.9 813.5
113/23 P 265.3 107.6 631.8 999.2 Threc Sid;;s U 236.6 90.5 563.8 813.50 Note: (1) P = Fartially Grouted; G = Grouted; U = Ungrouted (2) Mx and My are the maximum moments on the horizontal and vertical strips respectively obtained from the plate analyses (3) Mx3 and Myb are the maximum moments on the horitental and vertical strips respectively obtained from the beam analyses 4
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