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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/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc 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 ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) 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) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm 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 ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) 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 ML20137P8441997-02-14014 February 1997 Rev 5 to Authorization of Changes,Test & Experiments (10CFR50.59 & 72.48 Reviews) ML20140G9351997-02-14014 February 1997 Rev 13 to ISTs IT 585, Leakage Reduction & Preventive Maint Program Test of Post-Accident Containment Atmospheric Sampling Sys (Refueling) ML20140G8921997-02-14014 February 1997 Rev 7 to ISTs IT 215, SI Valves (Cold Shutdown) ML20140G9401997-02-0707 February 1997 Rev 21 to TS Tests TS 10A, Containment Airlock Door Seal Testing ML20138K2991997-01-31031 January 1997 Rev 46 to OP 4D,Part 1, Draining RCS to CVCS Hut W/O Entering Reduced Inventory ML20138K2031997-01-31031 January 1997 Rev 6 to IT 380, Purge Valve Air Sys Check Valve (Quarterly) for Unit 1 ML20138K2551997-01-31031 January 1997 Rev 2 to IT 530B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) for Unit 1 ML20138K2411997-01-31031 January 1997 Rev 12 to IT 530, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 1 ML20138K3231997-01-31031 January 1997 Rev 9 to RP 6A, SG Crevice Flush (Vacuum Mode) ML20137P8551997-01-31031 January 1997 Brine Tank Standpipe Mod ML20138K3071997-01-31031 January 1997 Rev 38 to OP 9C, Containment Venting & Purging ML20138K2901997-01-31031 January 1997 Rev 2 to IT 535A, Leakage Reduction & Preventive Maint Program Test of Train a HHSI & RHR Sys (Refueling) Unit 2 ML20138K2641997-01-31031 January 1997 Rev 12 to IT 535, Leakage Reduction & Preventive Maint Program Test of RHR Sys (Refueling) for Unit 2 ML20138K4991997-01-31031 January 1997 Rev 9 to Ort 4, Main Turbine Mechanical Overspeed Trip Device for Unit 2 ML20138K3181997-01-31031 January 1997 Rev 33 to RP 1B, Recovery from Refueling ML20138K3031997-01-31031 January 1997 Rev 1 to OP 4D,Part 5, Draining RCS to CVCS Hut W/O Entering Reduced Inventory & W/O SG Tubes ML20138K2251997-01-31031 January 1997 Rev 7 to IT 385, Purge Valve Air Sys Check Valve (Quarterly) for Unit 2 ML20138K4791997-01-31031 January 1997 Rev 15 to Ort 67, Component Cooling Water to & from Excess Letdown Heat Exchanger-Refueling Shutdown for Unit 1 ML20138K4701997-01-31031 January 1997 Rev 17 to Ort 59, Train Spray Sys CIV Leakage Test for Unit 1 ML20138K5041997-01-31031 January 1997 Rev 7 to Ort 50, PRT to Gas Analyzer Sample Line for Unit 2 ML20138K5161997-01-31031 January 1997 Rev 18 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 2 ML20138K4751997-01-31031 January 1997 Rev 19 to Ort 60, Train B Spray Sys CIV Leakage Test for Unit 1 ML20138K5231997-01-31031 January 1997 Rev 7 to Ort 71, Electrical Penetration Leak Test for Unit 2 ML20138K7311997-01-31031 January 1997 Rev 9 to TS 80, Sampling of Emergency Fuel Oil Tank (T-72), Fuel Oil Storage Tanks (T-175A,B) & EDG Day Tanks (T-31A,B & T-176A,B)(Quarterly) ML20138K7171997-01-31031 January 1997 Rev 6 to TS 37, Containment Spray Nozzles Check (Frequency of Less than or Equal to Five Yrs) for Unit 1 ML20138K3121997-01-31031 January 1997 Rev 43 to RP 1A, Preparation for Refueling 1998-09-30
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PROCEDURE TO ACCOUNT FOR OUT-OF-PLANE INTERSTORY DRIFT EFFECTS ON THE MASONRY WALL EVALUATION Prepared for Point Beach Nuclear Power Plant Units 1 and 2 WISCONSIN ELECTRIC POWER COMPANY Milwaukee, Wisconsin Prepared by COMPUTECH ENGlh5ERING SERVICES, INC.
Berkeley, California September,1981 REPORT NO. R553.11 Revision 1 8110130469 81 007 PDR O
ADCCK 05000266 PDR
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1 INTRODUCTION . . . . . . . . . . . . ................. . . . . . 1 i 2 A NALYSIS METHODOLOGY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 3 R E S U LTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4 DISCUSSION OF RESULTS . . . . ...... .......... . . . . . 2 5 CONC LUSION S . . . . . . . . . . . . . . . . . . . . .......... . . . . . 2
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1 INTRODUCTION The Nuciear 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 11 resulting from the review meeting stated that the licensee shall provide the criteria and procedures to account for the out-of-plane Interstory drift effects in seismic analysis.
This short report is in response to that action item and includes a description of the analysis methodology, the 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, to assess the out-of-plane response of the walls the boundary conditions at all supports were assumed to be pinned. This assumption was made for the following reasons.
(1) The stresses resulting from out-of-plane selsmic load are conservative.
(2) The boundary rotations required for the existence of pinned supports are very small and will exist regardless of what type of fixity is used to prevent it. A field inspection of the walls indicated this was the only reasonable assumption.
(3) The majority of the walls had no support at the top of the wall. In addition r o support was assumed around any door or other opening.
In assessing the effect of out-of-plane drift effects on the walls the same assumption of pinned boundary conditions was used for consistoney in the analytical procedures. With this assumption no forces are induced in the walls when out-of-plane interstory drift effects are assessed. The validity of this assumption I
was questioned in Action item 11 and as a result two walls (Wall Nos. 24 and 65-1) were selected to compare the results that would be obtained if fixed rather than simply supported boundary conditions had been assumed. Wall No.
24 is 164 inches long and 156 inches high and Wall No. 65-1 is 109 inches long and 176 inchos high. Each wall is double wythe and was analyzed as l a single and double wythe wall with both fixed and simply supported boundary conditions. For the fixed boundary conditions the effects of out-of-plane Interstory l drift were included in the analysis. The stresses resulting from out-of-plane l seismic load were combined absolutely with those resulting from out-of-plane l drift effects. Out-of-plane drift effects were calculated by imposing the out-of-plane displacement at the top of the wall witn the wall fixed against rotation at both the top corners and the bottom of the wall.
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3 RE3ULTS A summary of the maximum stress ratios resulting from the eight analyses perfor'aed are given in Table 1. Care must be exercised in evaluating the results becease the max! mum stresses do not fall in the same region of the wall for the different boundary conditions. In the case of the simply supported boundary conditions the maximum stress ratios are towards the center of the wall and for the fixed boundary Conditions they are close to or adjacent to the boundarles.
4 DISCUSSION OF RESULTS The results for Wall 65-1 Indicate that the maximum stress ratios of the simply supported boundary conditions for a single wythe wall are conservative when compared with those of the fixed boundary conditions that include out-of-plane Interstory drift effects. The maximum stress ratio for this wall occurred on a horizontal strip ano was reduced by almost one-half when fixed boundary conditions were used. When the same compr.rlson is made for the double wythe wall, again the maximum stress ratio, wh',ch was on a horizontal strip, was reduced by almost one-half. However, the maximum stress .atlo on the vertical strip increased from 0.n7 to 0.097. In comparing the three analyses: 1) single wythe with fixed botndarles -ad out-of-plane drift, 2) double wythe with simply supported boundaries and 3) double wythe with fixed boundaries and out-of-plane drift; the maximum stress ratlos are all less than the ratios obtained from analyzing the wall with the procedures given in the re-evaluation crite,ria.
The results for Wall 24 are similar to those of Wall 65-1 in that the maximum stress ratios on a horizontal strip decrease when fixed boundary conditions and out-of-plane drift are considered. However, on a vertical strip the maximum stress ratios increase for Wall 24. The increase for the single wythe wall is from 0.170 to 0.228 and for the double wythe wall it is from 0.075 to 0.226.
Although this increase for Wall 24 Indicates that for a vertical strip, the simply supported boundary conditions is non-conservativs the governing stress ratio on the horizontal strip is not exceeded by tha maximum stress ratlos in either direction for the other three analyses. Therefore, in this regard the assumption of simply supported boundary conc;tions used in the re-evaluation criteria can be considered conservative.
5 CONCLUSIONS The criteria and procedures used .o account for out-of-plane interstory drift effects in the re-evaluation criteria have been described and compared with results obtained from an alternate approach, in summary, the procedure used in the re-evaluation criteria assurnes the walls have pinned suppo-*- at .the boundarles because it is our opinion that this is the most realistic representation of field conditions and in addition it results in a conservative estimate of the I stresses resulting from out-of-plane selsmic load.
Two walls were selected to compare the maximum stress ratios obtained from the assumptions used in the re-evaluation criteria with those obtained from using the assumption that the top and bottom boundaries had fixed supports.
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The stresses obtained for the out-of-plane forces acting on the wall with flued boundary conditions were added absolutely to those resulting from out-of-plane drift effects.
For the two walls that were analyzed, the maximum magnitude of the stress ratio was obtained for the single wythe wall with simply supported boundary conditions. In both cases this was the stress on a horizontal strip. In th0 regard the assumptions used in the re-evaluation criteria are conservative. For Wall 65-1 the maximum stress ratio on both a horizonta! and vertical strip obtained f#om the single wythe wall with simply supported boundary conditions were consarvative. For Wall 24 the same statement is valid for the maximum stress ratio on a horizontal strip. For the maximum stress ratio on a vertical strip there was an increase when fixed boundary conditions were used but this increase did not exceed the maximum stress ratlo obtained on the horizontal strip.
From the results presented it is clear that the impact of different boundary conditions varies and is difficult to accurately assess because the region where the m'aximum stress occurs changes as the boundary condition changes. However.
for the two walls analyzed tne assumption of a single wythe wall with simply supported boundary conditions (i.e. that used in the re-evaluation criteria) produces the maximum magnitude in the stress ratio 'on either a horizontal or vertical strip. Furthermore. It is our opinion that these boundary conditions are the most realistlC for the Condillons that exist in t.9 field.
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. o TABLE 1 MAXIC4 STRESS RATIOS FOR VARYING BOU::DARY CONDITIONS tiall No. Thickness (in) Condition My /Mxa My/Mya 12 Simply Supported 0.406 0.170 12 Fixed. Drift . 0.265 0.228 24 l 25 i Simply supported 0.181 0.075 25 Fixed, Drift 0.129 0.226 6 Simply Supported 0.483 0.157 6 Fixed... Drif t 0.264 0.136 65-1 -
12 Simply Supported 0.215 0.070 12 Fixed, Drift 0.117 0.097 i<
Note: Subscripts x and y denote stress ratios on horizontal and vertical strips respectively i
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