ML20070T112
| ML20070T112 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 01/31/1983 |
| From: | TELEDYNE ENGINEERING SERVICES |
| To: | |
| Shared Package | |
| ML20070T098 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM TR-5639-2, TR-5639-2-R, TR-5639-2-R00, NUDOCS 8302080206 | |
| Download: ML20070T112 (176) | |
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TECHNICAL REFORT TR-5639-2 REVISION 0
) DAVIS-BESSE ANALYSIS AND EVALUATION OF THE SAFETY / RELIEF VALVE DISCHARGE SYSTEM PER NRC NUREG-0737 l 0, ,
JANUARY 1983 hDk bO!k o!bObOk6 P PDR
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- TOLEDO EDISON COMPANY
- O O Edison Plaza 300 Madison Avenue '
Toledo, Ohio 43652 I
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O TECHNICAL REPORT TR-5639-2 REVISION 0 DAVIS-BESSE 1
- O i ANALYSIS AND EVALUATION OF THE f SAFETY / RELIEF VALVE DISCHARGE SYSTEM
! PER NRC NUREG-0737 lO0 t
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.O JANUARY 1983 i
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O TTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 617-890-3350 O
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O Technical Report "#PTELEDYNE
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\._/ TABLE OF CONTENTS O
PAGE
1.0 INTRODUCTION
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2.0 CONCLUSION
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3.0 SYSTEM DESCRIPTION 4 3.1 Modification History 4 3.2 Final Modification 6 0 4.0 THERMAL FLUIDS ANALYSIS 8 4.1 Introduction 8 4.2 Relap Model 10 4.3 Plots 23 O 4.3.1 Force Time History Plots 24 4.3.2 Steam Quality Time History Plots 53 4.3.3 Junction Mass Flow Rate Plots 59 4.3.4 Pressure Time History 67 30 4.4 veive Flow Rete Ceicuietioas 77 4.5 Transients - SRV Opening Time 86 4.6 Relap Input 88 5.0 STRUCTURAL ANALYSIS 108 5.1 Piping 108 5.2 Supports 110 6.0 ANALYTICAL RESULTS 114 0 7.0 DRAWINGS 154
8.0 REFERENCES
155 APPENDIX A Plant Specific Evaluation of the Safety and Relief Valve Installation
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1.0 INTRODUCTION
Toledo Edison Company Purchase Order No. 031-Q-69641A-C1 authorized Teledyne Engineering Services (TES) to analyze the Pressurizer
) Safety / Relief Valve Piping and Valves (Safety Relief Valves, Power Operated Relief and Block Valves) per NRC NUREG-0737, Item II.D.1 for the Davis-Besse Nuclear Station.
Davis-Besse is a Babcox-Wilcox 177-FA plant using Crosby Model 3
- 4M 6 Safety / Relief Valves (2), a Crosby HPV-SN Power Operated Relief 1
Valve and a Velan Block Valve, (Reference 2 and 3). Appendix A of this report evaluates the valves for proper operation.
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This activity was performed in accordance with the TES Quality Assurance program which meets the requirements of 10CFR50, Appendix B, and ANSI N45.2.11 as interpreted by Regulatory Guide 1.64, Revision 2.
A D L.,)
The scope of work for the effort is described in detail in the Teledyne Engineering Services Technical Proposal PR-5700A dated January 20, 1982, and modified as stated in TES letter 5639-19, dated September 24, 1982. A summary of the work is as follows:
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- 1. The two safety relief valves (SRVs) were moved from the valve room to the pressurizer nozzles. The discharge lines to the
) quench tank were not connected. The valves were moved because of possible unstable operation shown in EPRI testing. The discharge lines were not installed because they do not need to relieve to the quench tank.
) 2. The power operated relief valve (PORV) was not moved and the discharge line to the quench tank was left in place. The piping loads were calculated using RELAP5, and then combined with deadweight, thermal, pressure and seismic loads.
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- 3. Analysis was done for the piping. Some supports have loads greater than originally analyzed and they were re-analyzed.
- 4. The pressurizer and quench tank nozzles were analyzed.
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- 5. The PORV and Blocking Valve and the SRVs (2) were evaluated for proper operation by using EPRI tests, and tests on the Davis-Besse valves. (Appendix A).
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2.0 CONCLUSION
S Based on the results in the report the following conclusions can be i
- . sumarized
- 1. The PORV and the block valve in the original position in the valve room will function properly for all expected operating
) and accident conditions. The PORV and blocking valve meet the requirements of NUREG-0737, Item II.D.1. (Reference 12).
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- 2. The PORY piping meets the requirements of NUREG-0737 Item
) II.D.1, if some of the supports are modified.
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- 3. The safety relief valves (2) in the new location mounted on the pressurizer with no discharge lines to .the quench tank, meet the requirements of NUREG-0737 Item II.D.1. The valves
) will function properly under all expected operating and accident conditions.
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V 3.0 SYSTEM DESCRIPTION The present configuration of the Davis - Besse pressurizer relief system is not the same as was originally installed. It is necessary to
) outline the history to understand how the piping and valves were changed to their present positions.
3.1 Modification History
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The Davis-Besse plant was shut down for refueling when TES was retained to perform the analysis on the system per NUREG-0737 Item II.D.1. At that time (April, 1982) the code to be used to calculate 3 piping blowdown force due to valve actuation (RELAP5 MOD 1, Cycle 14) was not available. A review of the EPRI data generated while testing valves similar to those used at Davis-Besse, with the same long inlet piping and a water filled loop seal, lead to the following conclusions:
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- 1. The safety relief valves (SRVs) may have operated in an unstable manner because of the long inlet piping between the pressurizer and the valve located in the valve room.
3 The pressure drop created by the long inlet piping could have caused valve instability. Instability is when the valve opens and shuts rapidly pounding the discand seat.
- 2. The piping and supports down stream of the SRVs and PORV may have had stresses larger than allowable. The EPRI test pipe and support loads for conditions similar to Davis-Besse were larger than the original Davis-Besse 3 system design loads.
It was decided the valves would be left where they were in the valve room, but the discharge of the SRV would be cut and the SRVs would 3 vent to the containment atmosphere. That would solve the problem of
() high SRV discharge piping loads. To solve the problem of possible unstable valve operation, a spare Davis-Besse Crosby 4M 16 SRV was tested D
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h in the Cro.sby ster test facility using different springs that would allow a higher bu, .n . This would allow the pressure to drop enough so the valve would not chatter (L 15% blowdown). The test was successful and data was also obtained with normal blowdown (25%). The
) approach was considered rather than moving the valve to the top of the pressurizer because it was believed the hard stellite valve seat and disc material used with loop seals would allow leakage without a loop seal. Some softer stainless steel seal material was obtained and
) installed. The following modifications were performed as an interim modification:
- 1. The two safety relief valves that were located in the valve room with about 20 feet of inlet piping from the
) pressurizer with a loop seal, were moved to the top of the pressurizer and mounted on the nozzles (No loop seal). They relieve to containment through a tee which has rupture discs. The rupture discs prevent airborne
} j contamination if the valve leaks, but will allow valve discharge because the rupture discs will burst at 75 psig and the quench tanks rupture disc is set for 100 psig.
This method essentially eliminates blowdown loads, the
) possiblity of unstable valve operation, and any discharge piping backpressure concerns.
Appendix A of this report gives the qualification of the valves located on the pressurizer. The qualification
) includes testing on a Davis-Besse valve and compares tests of other similar valves done by EPRI to insure Davis-Besse valves were bounded by EPRI test conditions.
- 2. The interim modification for the power operated relief
) valve (PORV) did not eliminate the discharge piping and lef t the valve in its original position. The PORV and SRV discharges were the same line and moving the SRV changed the pipe support system. Also blowdown loads per j the requirements of NUREG 0737 Item II D.1 were not used
' uf] because the version of the RELAP computer code had not been developed at the time the analysis was done. The blowdown loads previously used in Reference 10 were used for an interim modification.
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) 3.2 Final Modification The final modificatio'is are similar to the interim modifica-tions with the following explanation:
) 1. The SRVs will remain mounted on the pressurizer no7zles discharging to containment through rupture discs. (See Drawing E-5986 Rev. 4 Section 7). The discharge piping will not be connected because the SRVs have not actuated
) due to plant operation for the life of the plant. If they do actuate they will contaminate the area over the pressurizer. Jet impingement, subcompartment pressuriza-tion, and local area temperature have been considered.
) If the SRV discharges were connected to the quench tank, as before, and the valves were to actuate for a period of time, the quench tank rupture disc would rupture. Con-tamination would result in this case also, but in the
)(] lower containment below the pressurizer.
- 2. The PORV will remain in the valve room as in the interim modification and the original design. The RELAP 5 MOD 1 Cycle 14 calculations have been completed as explained in
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Section 4.0 and the loads were applied to the piping as explained in Section 5.0 and 6.0. The PORV piping and support analysis allow for the following options:
) a. The piping analysis shows stresses are within code allowables, but some of the piping supports on PORV dis-charge require modifications to have the supports be within the allowable stresses. The supports requiring
) modification are listed in Section 5.0.
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V 4.0 THERMAL FLUIDS ANALYSIS O
4.1 Introduction The following analysis determines the fluid forces which act O on the pressurizer PORV discharge piping. These forces are generated by the sudden opening of the pressurizer relief valve during the pressurizer transients described in the nuclear steam system supplier report (Ref. 2)
O These forces. the resulting stresses they apply to the piping system, the resulting loads they inflict on the pipe supports, and the loads they transmit to the safety and relief valves became of increased O concern following the incident at Three Mile Island.
Following the Three Mile Island incident, the NRC issued huREG 0578 and NUREG 0737 which required that each utility determine the g
3 () effect of safety / relief valve operation upon the valve and the discharge piping. An elaborate program was established under the general management of the Electric Power Research Institute (EPRI). This program involved both testing and analysis. Intensive testing of safety
'O and relief valves was performed at several locations across the country.
A full scale model simulating the pressurizer and discharge piping was built at Combustion Engineering in Connecticut.
O Simultaneously, an analytical program was initiated to choose and test a computer program which would predict the fluid forces. The code that was selected was RELAP5 MOD 1 CY14. This is one of the latest in the family of RELAP programs developed at the Idaho National O Engineering Laboratory. (Ref. 5).
i The structural response of the system to the transient fluid forces was analyzed by TMRSAP which is a structural program developed by O Teledyne Engineering Services (TES) (Ref. 9.) Modeling of the system a
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Technical Report 'RTELED(NE TR-5639-2 ENGINEERING SERVICES I
includes PORV discharge line beginning from pressurizer and ending with the quench tank. Since the safety valves were separated from the discharge piping system, their operation was not included in this present work.
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Technical Report TR-5639-2 4.2 RELAP Model The fluid transient forces were determined using the RELAP5 M001 computer program. RELAPS MOD 1 is the latest in the RELAP series of programs developed by the Idaho National Engineering Laboratory. (Ref.
5)
RELAPS MOD 1 was used by EPRI to predict the full scale blowdown tests at Combustion Engineering in Connecticut The RELAP predictions showed good agreement with the test data.
TES used the RELAPS M001 CYl4 version available at University Computing Company (UCC) in Dallas. This version is accessed using the following file names:
RELAP5FORCEV1A,ID=GAUCC h STH2XT,RELAP5M001CY14H20LIBLARGE,ID=UCC The UCC version of RELAP5 MOD 1 allowed for computation of the fluid forces internal to the program without the need for a post processor (Ref. 4). The forces were calculated using the control system capability within RELAP.
The safety valve discharges were disconnacted from the system, so only PORV discharge line was modeled as it exists at the present time.
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Technical Report "RTri prWNE TR-5639-2
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- 1. Saturated Steam Discharge @ 2450 psig with 175 psi /sec pressure ramp.
- 2. Saturated Steam discharge including hot loop seal @ 500 F upstream of valve with pressurizer conditions @ 2450 psig with 175 psi /sec pressure ramp.
- 3. Subcooled water discharge @ 400 F @ 2450 psig.
From' these three cases the third gives the highest transient loads (Ref. 1), so only the third case was analyzed. A sensitivity study was done on the existing model by introducing more control volumes and thus smaller control volume lengths. As a result of this analysis, the results of the existing model were found to be satisf actory. The following program names were used:
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- 1. PORVDB,ID=DAVISBESS (Used as the main program)
Output ID as a result of the run: BAI205K
- 2. NEWDB,ID=DAVISBESS (Used as finer model to prove the results from PORVDB were accurate).
Output ID as a result of the run: BAI18YO In RELAPS the valve is modeled as an orifice with one dimensional two phase flow through it. The piping includes functional loss coefficients as well as losses due to bends and sudden expansions and contractions. The quench tank was modeled as continuous piping with one dimensional flow. Lengths and flow areas were chosen by taking into consideration the real quench tank geometry and spargers. Loss coefficients were selected in order to approximate the losses through different sections of the quench tank. The PORV Discharge piping has a l
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heat traced hot loop seal with 500 average temperature. (Ref. 8). It U
is modeled as a subcooled water column at 500 F contained in the upstream part of valve up to control volume 8217 and then with increasing temperatures up to control volume 8213, such that the pressurizer end of the loop seal reaches the temperature of the pressurizer. Tre piping geometry and the RELAP model are drawn on the following pages. Detailed RELAP input is given in the input section.
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"RTB m(NE ENGINEERING SERVICES Technical Report h TR-5639-2 4.3 PLOTS As a result of the RELAP Run BAI205K the following plots were generated and presented in the following sections.
4.3.1 Force Time History Plots 4.3.2 Steam Quality-Time History Plots 4.3.3 Junction Massflow Rate-Time History Plots 4.3.4 Pressure - Time History Plots The locations of the data points from which these plots were generated are shown in the corresponding model drawings of each section. I ) 1
St' F W NE ENGINEERING SERVICES Technical Report h TR-5639-2 4.3.1 Force Time History Plots The following force versus time history plots represents the transient forces on each segment. These plots were obtained from the RTLAPS run BAI205K which is an output from the program PORVDB with 0 .448 n c run. The forces are calculated by the RELAP5 FORCE Program using the control system capability of RELAP5. These forces are the
" wave forces" which are derived from the unsteady part of the momentum equation. Duration time of the transients for the program was long enough so that transient forces became insignificant at the end of the run.
l There are 27 force versus time plots on 27 segments of the PORV line numbered from 501 thru 527. Peak forces and the times at which they occur are indicated on each plot. I
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4%9 M ENGNEERNG SBNCES Technical Report D TR-5639-2 4.3.2 Steam Quality-Time History Plots The following plots represent the steam quality versus time change in various parts of the PORV discharge piping. Corresponding location of each plot is indicated on a sketch for PORV discharge piping. The behavior of the loop seai can be followed by these plots in each corresponding location since lower quality represents the evidence of the loop seal at that time. The last plot is from the tip of the sparger which is submerged in water in the quench tank (Control Volume 6410). As it is seen from this last plot, compressed air in front of the pressure wave clears the spargers and then wet steam arrives. All these plots are from the computer run BAI205K dated November 27, 1982. l l l 1 l l
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"-5639-2 "RTF1 FrVNE ENGINEERING SERVICES
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] TR-5639-2 4.3.3 Junction Massflow Rate Plots The following plots represent the mass flow rate through selected junctions of the PORV discharge piping. Data point locations are shown on the sketch and plots were created as a result of the computer run BAI205K. I l
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Technical Report { D TR-5639-2 ' 4.5 Transients As a part of the EPRI program each of the Nuclear Steam System Supplier (NSSS) provided a report which identified the inlet conditicns for the pressurizer safety valves (PSV) and power operated relief valves (PORV). For the Davis Besse Nuclear Power Plant this report was provided by Babcock and Wilcox (Valve Inlet Fluid Conditions for Pressurizer Safety / Relief Valves for BLW 177-FA and 205-FA plants, EPRI NP 2352-LD Project V102-17) (Ref. 2). At the time when this report was prepared Safety Valves were disconnected from the Davis Besse pressurizer discharge piping system so I only the power operated relief valve inlet fluid conditions are of interest. These are summarized below: POWER OPERATED RELIEF VALVE INLET FLUID CONDITIONS VALVE MODEL: CROSBY, HPV-SN, PORV CASE LIMITING VALVE FLUID ASSUMED RAMP RATE MAX. NO. EVENTS OPENING CONDITION PORV OPENING OF PRESSUR. PRESSUR. TIME (SEC) PRESS. PSIA PSI /SEC PSIA 1 Rod 0.05 Saturated 2464.7 175 2676.7 Ejection Steam W/0 at HZP Hot Loop Seal 2 Rod 0.05 Saturated 2464.7 175 2676.7 Ejection Steam with at HZP Hot Loop Seal 3 Steamline 0.05 Subcooled 2464.7 N/A 2514.7 U Break Water @400 I
'RTn PTVNE ENGINEERING SERVICES Technical Report D TR-5639-2 From these three cases the second case gives the worst loads. T51s has been determined from reference " Evaluation of RELAP5/M001 for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads" prepared by Intermountain Technologies Inc., 1400 Benton, P.O.
l Box 1604, Idaho Falls, Idaho 83401(Reference 1). This reference indicated that the hot loop seal created fluid loads significantly greater than the steam or subcooled case. Therefore only the second case is considered for this analysis since it bounds the other cases.
)
1%P WNE Technical Report ) TR-5639-2 4.6 RELAP Input The following pages are reproductions of the actual input to RELAPS for run ID=BAI205K. The complete oputput is provided in the Appendices. A brief discussion of the modeling follows:
- 1. The pressurizer was modeled as a single time dependent control volume initially at 2450 psig with a pressure ramp fo 175 ps1/sec (Ref. 2).
- 2. The power operated relief valve was modeled 'as a flow junction with an orifice whose area varied linearly from zero to full open in 50 msecs. (Ref. LBS Handcalculation dated 7/15/82). The flow area for fullopen was found from a simple RELAP run so that the ASME rated flow was delivered (Ref. LBS Handcalculation dated 6/21/82 and BAI Handcal dated 11/30/82).
- 3. The discharge pipe walls were assumed to be thermal insulated. This assumption is conservative and it was necessary because of program limitations. The great number of control volumes in this model did not allow for the use of RELAP's heat transfer capability at the same time.
- 4. Friction factors were taken from Crane's Technical paper
#410. (Ref. 7)
- 5. The quench tank was modeled as an integral part of the piping system with proper dimensions for spargers, water and air volumes in the quench tank.
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'RTA 1:rVNE Technical Report ENGNE951G SERVICES TR-5639-2 D -108-5.0 STRUCTURAL ANALYSIS 5.1 Piping The PORV piping as shown in TES Drawing D-7171 Rev. 1 in Section 7.0, was analyzed in accordance with ASME Section III subsection NB (Inlet) and ND (Discharge)-3600,1971 Edition to Summer 1973 Addenda (Reference 6). The TMRPIPE computer code (Reference 9) was used with the following loading conditicns.
Weight Operating Conditions Thermal Thermal 1 - 650 from Pressurizer to PORV valve decreased to 450 over one ti.armal Attenuation length. g Thermal 2 - 650 from Pressurizer to PORV valve d&reased to 150 U over one thermal Attenuation length. Seismic Shock (The Seismic curves used are on the following pages) X - Direction Y - Direction Z - Direction Seismic Anchor Movements X - Direction Y - Direction Z - Direction I
Technical Report "R F W NE
-109- ENGINEERING SERVICES D
Blowdown The blowdown time history forcing functions from RELAPS FORCE were used in the piping models. Section 4.0 explains the forcing functions. The model used previously in Reference 10 was used as the pressurizer model for this report. The nozzles on the pressurizer (1 PORV and 2 SRV) were checked for stress using Reference 14. The stress due to all the loading combined was not significant (c 2 Ksi) and is below the allowable. The stress in the quench tank nozzle was also calculated and found not to be significant. Reference 14 was used on the quench tank nozzle which was very conservative because it is a pipe passing into the tank and the pipe is supported inside the tank. A detailed calculation would show
) lower stress than the approach of Reference 14.
The nozzle to flange weld, and flange below the SRVs have acceptable stress values. Moving the valves to the pressurizer nozzle from the valve room eliminated any thermal stress fatigue problems that were a factor before, (Reference 10), which was the reason the SRV loop seal was trace heated originally. The fatigue usage factor was considered per ASME NB (Safety Class 1) requirements and was found to be (G.10). The SRV discharges have flanged tees with rupture discs. They were considered in the analysis of the SRVs for blowdown, deadweight and seismic loads. The PORV piping between the pressurizer and the ' JRV valve is ASME Section III Subsection NB. (Safety Class 1) Reference 10 analyzed the thermal transients and required the PORV loopseal be heated for thermal stress consideration and the analysis is still valid. This is true because the thermal transients and pipe route did not change.
) Also, the blowdown loads did not exceed support allowable loads.
Technical Report "RTF1RVNE TR-5639-2
-110-NRW S I
5.2 Pipe Supports The pipe supports were analyzed using the Reference 6 ASME Section III Code, but the 1974 Edition Subsection NF was used. There are no supports on the SRVs. The supports on the PORV are listed in Section 5. The new loads are compared to the old loads. Each support was analyzed and several have loads higher than the original loads. All supports pass except the following:
- 1. 30-GCC-8-H2 Snubber on PORV discharge. The support analysis shows the support does not exceed the allowable stresses but it is required that the support location on the pipe be moved, which will require a modification to the attachment to the pipe.
I
- 2. 30-GCC-8-H17 Struts on the PORV discharge. The hanger was modified from snubbers to struts during the interim modifications. The struts were manufactured on site and are pinned at one end only. New struts should be added and other minor modificaitons are required.
- 3. 30-GCC-8-45 Snubber on the PORV discharge. The piping analysis shows small thermal movement 1/16" and the snubber can be replaced by a rigid support. Also an additional beam is required for strength. i 1
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Technical Report it' N NE TR-5639-2 ENGNEERING SERVICES I -114-6.0 ANALYTICAL RESULTS The following section gives the results of the piping analysis done using the Reference 9 code with Section 4.0 blowdown loads and Section 5.0 deadweight, thermal and seismic loads. All piping stresses shown are within the allowable for ASME Section III 1971 with Addenda to Summer 1973 Subsection NB or ND. , The support load summary sheets are given as taken from the piping analysis. The new loads are compared with the old loads. Analysis has been done on all the supports but is not included in this report. The analysis results are discussed in Section 5.0. The analyses for the pressurizer and quench tank nozzles are shown I with acceptable results. I
......____-.....................---/M..................................___...
I DALF: TSR PkhJr_CT: I i 10 / Tl / H 2 P1Pl Hi A.lgl.Y S15 SUPPora Su *Awy PknGkA4 HHH 5639 1 ' I REV b 1 I
SUBJECT:
Pkt.SS R E t, SYS 5639 STRESS St);m AN Y ,f 1 I . I I DR A 41'4GS : DAVIS RESSE PRESSul<ISEP kEL1EF SYSTEM I I l'ECliTEL DRAWING Hb-230A 1 1-------~~~--~=-~~--=-------------==---=~~-------~~----------.-------~~~---.1 BY g _ DATE/ 83 CHKD. BY pHB DATE l-3-83 1, O A D CA S ES tit i . OF STATIC 1.OAD CONDITIdh5 = 1 .' M'. OF TbEkHAL LOAD CONDITIO;.S = 2 SEISMIC 1hERTIA OBE SHUC6 OIRECIIONS =X YZ SEISMIC INERTIA DISPL ACEMEr.TS = bEIS IC ATTAChhEST D I S P1, A C Ei@'T S =A i Z SEIS*IC tiuLTIPl.tER FOR D6E = 1.87 X OEE DYN A.* [C LO ADS 1HPUT = (P=PHIi. ARY , S=S ECo r* 0 A R Y ) , l ! Cri .f I-ito SEIS* J C rFTION = ? I = S G R 'l ( X *
- 2 + Z**2) + (Y) 2 = SCR1(X**2 + Y**2 + Z**2)
CobHOTHAIE S r S I Dt : INPUT X i 7 REPORTED X Y Z PWE Sui'k V S'lWh.F.S OPT 10D = 1 I = P(00)/(4*T) 2 = P(10)**2/(UD**/-lo*+2)
-//6 -
*** Th9 PJPING ArAI,fSIS SUPPub'r su r* A H F.9 t, BY ,[/8 DATE / 83 h PRESS R El, SYb 56.59 6 tw ESh
SUMMARY
RE O n9 1.0 1.0 1.0 1.9 1.0 1.C RE o 1s0 0.0 0.0 1.0 0.0 0.0 0( RE O lbo 1.0 1.0 1.0 0.0 0.0 0.( RE Y5n0h o 190 0.0 3.0 0.0 0.0 0,0 0.( RE o 715 0.0 1.0 1.0 0.0 0.0 0.( RE X'I Sbu6 0 255 3.0 0.0 3.0 0.0 0.0 0( RE X Shuo 0 296 3.0 0.0 0.0 0.0 0.0 0.C R E ta e o 340 0.0 1.0 0.0 0.0 0.0 0.C RE X M UH O 66% 3.0 0.v 0.0 0.0 0.0 0.t RE X Sb to$ 0 's o 5 3.0 0.0 0.0 0.0 0.0 0.( RE X Shub 0 720 3.0 0.0 1.0 0.0 1.0 0.t RE Y St bh 0 739 0.0 1.0 0.0 0.0 0.0 0.C RE o 770 1.0 1.0 1.0 1.0 1.0 1. . C RE '/, b 1230 0.0 0.0 1.0 0.0 0.0 0.0 RE V O 1710 0.0 1.0 0.0 0.o v.o 0.C RE X 0 1209 1,0 0.0 0.0 0.0 (.o 0.C RE Y St+hb o 1140 0.0 3.0 0.0 0.0 0.0 0.c RE O 1060 1.0 1.0 1.0 1.0 1.0 1.C SEC110A 0 0 0.0 0.0 0.0 0,0 0.0 0.C PIFE % 25 90.2 6.4 27.9 0.0 0.0 0.C RU G 25 0.0 0.0 0.5 0.0 0.0 0.C RU 25 10 0.0 -Fi. 7 0.0 0.0 0.0 0.C Ril 10 8 0.0 -4.2 0.0 00 0.0 0.C RU 25 27 0.0 11.6 0.0 0.0 0.0 0.C
- 7. 7 42 0.0 H.5 0.0 0.0 0.0 0.C
) RU RU 42 i. 4 0.0 5.5 0.0 0.0 0.0 0.C RU <4 100 1.3 0.0 -0.6 0.0 0.0 0.0 RU 100 105 0.0 0.8 0.0 0.0 0.0 0.0 RU 100 105 3.5 0.4 2b.3 0.0 0.0 1.e EL 105 110 0.0 0.0 0.0 4.5 0.0 0.0 RU 110 115 1.9 0.0 0.0 0,0 0.0 0.0 RU 115 123 1.9 0.0 0.0 0.0 0.0 0.0 EL 120 125 o.0 0.0 0.0 4.5 0.0 0.0 RU lib 13a 0.0 0.5 -e.1 0.0 0.0 0.0 RU 130 135 0.0 0.5 -0.1 0.0 0.0 0.0 EL 13S 138 0.0 0.0 0.0 4.5 0.0 0.0 RU 138 140 0.9 0,0 0.0 0.0 0.0 0,0 RU 140 145 4.1 0.0 0.0 0.0 0.0 0.0 RV 14% 1So 0.9 0.0 0.0 0.0 0.0 0.0
- t. t . Ito 139 o , r. o.o t. . b q.4 4.o n.o EL 15v 157 u,C O.0 0.0 0.0 0.0 1.0 RU 155 160 0.0 -1.2 -1,2 0.0 0.0 0.0 RU 1% 165 0.C -1.2 -1,2 0.0 0.0 0.0 EL 165 170 0.0 0.0 0.0 4.5 0.0 0.0 RU 1 19 1/5 1.6 0.0 0.0 0.0 0.0 0.0 RU 175 Ino 1.6 0.0 0.0 0.0 0.0 0.0 RU 180 IS5 3.0 0.0 0.0 0.0 0.0 0.0 RU IF5 1he 3.0 0.0 0.0 0.0 0.0 0.0 RU lbH 1xh1 0.0 0.7 -0.7 0.0 v.e 0,0 F0EX 1>8 1bs199999999.0 0.0 0.0 0.0 0.0 0.0 RU 19e Iv> 0.4 0.0 0.0 0.0 n.e 0.0 h RU 19v Ivs 0.3 0.0 0.0 0.0 0.0 0.0 RU 195 299 0.3 0.0 0.0 0.0 0.0 0.0 RU 195 200 2.9 0.4 0.0 0.0 0.0 1.0 RU 700 205 0.5 0.0 0.0 0.0 0.0 9.0 RU you Pon 4.9 1.4 0.0 0.0 0.0 0.0 RU 2 )t 7to 0.6 0.0 <>.0 3.0 0.6 ') O RU Plo 7/i - 1. f 1.9 o.o 0.0 0.0 o.O
c e, eiv eto ssa.v se i- vov -e. . - - RU 210 212 0.k 0,0 0 0,0 RU RU 712 215 215 2/5 C.S 0.3 0.0 0.0 0 0 BY h DATE /-J-83 %0 0.0 RU 715 725 7.9 0,4 0 CHKD. BY 9ttB DATE P3-A3 1,0 225 0,0 0 O.0 ] EL 235 240 0.0 0 0,0 ) RU 235 0.0 0.3 RU 240 245 0.0 0.5 0,0 0.0 0.0 0.0 RU 740 745 4,9 1.4 0.0 0.0 0.0 0,0 ; RU 245 259 0.0 0.8 0.0 0.0 0.0 0,0 RU 250 20) 0,7 0.1 0.0 0.0 0.0 0,0 WE 259 760 550,0 0,0 0.0 0.0 0.0 0,0 RU 250 255 0.0 0.8 0.0 0.0 0.0 0,0 RU 255 765 0.0 0.9 0.0 0.0 0.0 0,0 RU 255 265 4.5 0.1 0.0 0,0 0.0 0.5 EL 265 7H0 0.0 0.0 0.0 6.0 0.0 0.0 RU 280 285 0.0 0.0 1.0 0.0 0.0 0.0 EL 265 247 0.0 0.0 0.0 6,0 0,0 0,0 , RU 287 290 0.0 -0.5 0.0 0.0 0.0 0,0 RU 290 295 0.0 -0.5 0.0 0.0 0.0 0.0 RU 295 296 0.0 -1.0 0.0 0,0 0.0 0.0 RU 29e 300 0.0 -1.1 0.0 0.0 0.0 0,0 EL 300 305 0,0 0,0 0.0 6,0 0.0 0.0 RU 305 310 -2.9 0.0 0.0 0.0 n.0 0.0 RU 310 315 -7.4 0.0 0.0 0.0 0.0 0,0 EL 315 320 0.0 0.0 0.0 6.0 0.0 0,0 RU 320 330 0,0 0,0 0.9 0.0 0.0 0,0 RU 330 335 C.0 0.0 0,5 0,0 0.0 0.c RU 335 340 0.0 0.e 0.0 0,0 0.0 0.0 RU 335 340 8,6 0.3 0.0 0.0 0.0 1.5 RU 340 34S 0.0 0.7 0.0 0.0 0.6 0.C EL 345 350 0.0 0.0 0.0 12.0 0.0 0.0 350 355 1,6 1.6 0,0 0,0 0.0 0.C h RU RU 355 995 0,4 0.4 0.0 0.0 0.0 0,C RU 355 493 0,0 0.3 0.0 0.0 0.0 2.4 RU 995 A/5 0.0 0,0 -1,6 0.0 0.0 0,C EL n75 670 0.0 0.0 0.0 17.0 0.0 0.C RU e70 A61 -1.5 0.0 0.0 0.0 0.0 0.C RU 670 667 6,6 0.3 0.0 0.0 0.0 1.6 RU 667 A65 -0.4 0.0 0.0 0.0 0.0 0.C RU nos 652 -1.0 0,0 0.0 0.0 0.0 0.C RU M2 hol -0.6 0.0 0.0 0.0 0.0 0.C RU 661 6 6 .) -0.4 0,0 0.0 0.0 0.0 0.C RU 660 65% -0.6 0.0 0.0 0.0 0.0 0,C RU 660 655 8.6 1.3 0.0 0,0 0,0 24.4 RU 993 975 0.0 0.0 1,6 0.0 0.0 0.C RU 995 975 R.6 0.3 0.0 0.0 0.0 2.4 EL 975 973 0.0 0.0 0.0 12.0 0,0 0.C RU 970 901 -1.5 0.0 0.0 0.0 0.0 0.C RU 970 957 6.6 0.3 0.0 0.0 0.0 1,6 RU 961 9e5 -0.4 0.0 0.0 0,0 0.0 0,C RU 965 %2 -0.-1 v.0 0.0 0,0 0.0 0.C RU 952 46i -0.7 0.0 0.0 0.0 0.0 0.C RU 961 %a -1.0 0,0 0.0 0.0 0.0 0 . t. RU 4% 955 -0.6 0.0 0.0 0.0 0.0 0( RU 960 95S R6 1.3 0.0 0.0 0.0 24.4 RU 335 720 0,0 -1.9 u,0 t: ,0 0,0 0.C RU 315 771 8.6 0.3 0.0 0.0 0.0 3.1 RU ??v 734 0.0 -1.6 0.0 0.0 0.0 0( D EL 730 735 0.0 0.0 0.0 11.0 0,0 0.C RU 735 737 0.0 0.0 -?.0 0.0 0.0 0.C EL 737 73n 0.0 0.0 0.0 12.0 0.0 0( HU 7% 733 -1.0 0.0 0.0 0.0 0,0 0,C R9 739 747 -7.3 0.0 0.0 0.0 0.0 0.( RU 74^ 145 -3.3 0.0 0.0 0.0 0.0 0.( EL 145 7v 0.0 0.0 0.0 17.0 0.0 0.(
~
tt u sou so3 u,e ,,_gjg. v,o 4.4 sv u,v v,s RU 753 755 0.0 0.0 2,1 0.0 0.0 OeC RU 755 757 0.0 0.0 2.1 0.0 0.0 0.C RU 757 760 0.0 0.0 2.1 0.0 0.0 0,( EL 76u 765 0.0 0.0 0.0 17.0 0.0 0,C RU 765 770 -1.7 0.0 0.0 0.e 0.0 0.C RU 770 12n0 -2.0 0.0 0.0 0.0 0.0 0.C RU 1260 1255 -2.0 0.0 0.0 0.0 0.0 0.C RU 125S 1252 -2.0 0.0 0,0 0.0 0.0 0,C RU 1252 1250 -2.0 0.0 0.0 0.0 0.0 0.r RU 1250 124S -2.0 0.0 0.0 0.0 0.0 0.C EL 1245 1240 0.0 0.0 0.0 12.0 0.0 0,C RU 124u 1230 0.0 -1.1 0.0 0.0 0.0 0.C RU 1230 1225 0.0 -4.9 0.0 0.0 0,0 0.C RU 1225 1220 0.0 -3.0 0.0 0.0 0.0 0.C RU 1220 1215 0.0 -3.0 0.0 0.0 0.0 0,C RU 1215 121a 0.0 -3.0 0.0 0.0 0.0 0.C RU 1210 1704 0.0 -1.6 0.0 0.0 0.0 0.C RU 120S 1205 0.0 -1.8 0.0 0.0 0,0 0.C RU 1205 2705 -0.5 0.0 0.9 0.0 0.0 0.C FLEX 1205 220594999999.0 0.0 0.0 0,0 0.0 0.C RU 1205 1200 0.0 -0.5 0.0 0.0 0.0 0.C RU 120u 1195 0.0 -1,2 0.0 0.0 0.0 0.C EL 1195 1110 0.0 0.0 0.0 17.0 0.0 0.C RU 1190 1185 -2.2 0.0 0.0 0.0 0.0 0.C RU 1185 1175 -7.2 0.0 0.0 0.0 0.0 0.0 RU 1175 1165 -2,2 0.0 0.0 0.0 0.0 0.0 EL 1165 1190 0.0 0.0 0.0 12.0 0.0 0.C RU 1160 1ts5 0.0 -2.7 0.0 0.0 0.0 0.0 RU 1155 1130 0.0 -2.7 0,0 0.0 0.0 0.0 EL 1150 114S 0.0 0.0 0.0 12.0 0.0 0.0 RU 1145 114a -0.3 0,0 -1.3 0.0 C0 0.0 l RU 1140 1131 -0.5 0.0 -2.1 0.0 0,0 0.0 RU 113R 113S -0.5 0.0 -2.1 0.0 0.0 0.0 EL 113S L130 0.0 0.0 9.0 17.0 0.0 0.0 RU 1130 1125 0.0 -2,3 0.0 0.0 0.0 9.0 RU 1175 2125 0.9 0.0 0.5 0.0 0.0 0.0 FLEX 1125 212599999999.0 0,0 0.0 0.0 0.0 0.0 RU 1125 112') 0,0 -0,5 0.0 0.0 0.0 0.0 RU 112') 212-) -0.5 0.0 0.9 0.0 0.0 0.0 FLEX 1120 212099999999.0 0.0 0.0 9.0 C.0 0.0 RU 1170 1115 0.0 -3.6 0.0 ') . O 0.0 0.0 RU 1115 11to 0.3 -3.6 0.0 0.0 0.0 0,0 RU 1110 1105 0.0 -3.6 0.0 0.0 0.0 0.0 EL 1105 1100 0.0 0.0 0.0 12.0 0.0 0.0 RU 1100 1090 2.0 0,0 0.0 0.0 0.0 0.0 EL 1090 10n3 0.0 0.0 0.0 12.0 0.0 0.0. RU lodS lod s n.1 -1.7 0.0 0.0 0.0 0.0 RU todu 1075 0.0 -3.7 0.0 0.0 0.0 0.0 RU t o 7 'i 1065 0.0 -3.7 0.0 0.0 0.0 0,0 R tl 1065 loca 0.0 -0.8 0.0 0.0 0.0 0.0 EN D.IlH XX BY M _ DATE / ,3 @ CHKD. BY pfp_ DATE LtB3 I
-/M-
*** rmy PIPING A !' A li y S 15 SUPPukT .;U n n A H Y P H f h.R Aid ***
HEV h l PRESS hKL SYS 5639 STRESS
SUMMARY
BY [M ,_ DAIE/- $--5J ulKD. BY pt6"~ DATE t 3 e,3_
~ ~ ~
^1EABER DATA B E.4 0 COMPUMrXi SECTine- MEP6E4 0.D. 1 HICK. RADIOS ,
(IN) (10) (14) ; RU 1 n9 25 90.233 d.360 RU 1 25 19 90.233 o.360 RU 1 10 4 90.233 n.3n0 i HU 1 25 27 90.233 6.360 RU 1 27 42 90.233 6.360 RU 1 42 44 9u.233 6.360 RU 1 44 100 90.233 6.360 RU 1 100 105 3.500 u 438 EL i 105 110 3.500 0 . 4 354 4.500 RU t 110 115 3.50C o.446 , RU 1 115 120 3.500 0.438 EL 1 120 125 3.500 0.438 4.500 RU 1 125 130 3.500 0.438 RU 1 130 135 3.500 0.438 EL 1 135 13R 3.500 0.438 4.500 RU 1 l is 140 3.500 0.438 ' RU 1 140 145 3.500 0.438 RU 1 145 150 3.500 0.438 EL 1 150 155 3.500 0.438 4.500 g RU l 155 160 3.500 e.438 RU ! 160 16% 3.500 0.439 Eu 1 165 170 3.500 v.439 4.590 RU 1 170 175 3.50u O.438 RU 1 175 1HO 3.500 0.438 , RU 1 1H0 18% 3.530 0.436 RU 1 185 188 3.500 0.436 R tl 1 1Hb 164 H 1 3.50u 0.438 90 1 188 190 3.50c o.418 HU 1 190 195 3.500 0.438 RU i 195 200 2.675 0.375 RU 1 200 205 4.675 1.375 RU L 205 210 4.675 1.375 RU t 210 220 4.675 1.375 RU 1 210 21/ 4.b75 1. 3 ~/ 5 RU $ 212 215 4.875 1.375 RU 1 215 225 2.875 0.315 EL 1 225 235 2. b 15 0.375 3.750 ; RU 1 235 240 2.e75 0.375 Rd 1 240 245 4. b 15 1.315 RU 1 145 250 4.875 1.375 ' R ') 1 250 266 4.b75 1.375 Rd 1 250 255 4.875 1.375 HU 1 255 265 4.500 0.120 Et, 1 265 260 4.500 0.110 6.000 RU 1 260 285 4.500 0.120 h
~/XO-
*+* r%R PIPl=G AGALYSIS SUPPnHT 50"%ARY PROGRAM ***
HFV G BY DAIE j(:sf-j[3 ll PRESS HE0 SYS 5639 STHESS SUMNARY M di4 B ER DATA o t:m COMPUNEat SECrlai r4 EN R E R O . ts , fHICK. R A D 1 'J S (IN) ( I .N ) (IN) EL 1 285 287 4.500 0.120 6.000 RU 1 2R7 290 4.500 0.120 RU 1 290 295 4.500 0.120 RU 1 295 29e ,4,500 0.120 RU 1 296 300 4.500 0.120 EL 1 300 305 4.500 0.120 6.000 RU 1 305 310 4.500 0.120 . RU 1 310 315 4.500 0.120 EL 1 315 320 4.500 0.120 6.000 RU 1 320 330 4,500 0,120 RU 1 330 33S 4.500 0.120 RU 1 335 340 6.625 0.250 RU 1 340 345 8.625 0.250 EL t 345 350 e.e25 0.250 12.000 RU t 350 355 8.625 0.250 RU 1 355 995 e.o25 0.322 RU 1 995 675 8.625 0.322 Et, 1 675 670 8.625 0.322 12.000 g RU 1 670 667 6.625 0.2b0 RU 1 667 665 6.625 0.260 RU 1 665 662 6.625 0.280 RU 1 662 651 6.o25 0.2e0 RU 1 661 660 6.625 0.260 RU 1 660 655 8.625 1.280 RU 1 995 975 8.625 0.322 EL 1 975 970 8.625 0.322 12.000 RU 1 970 967 6.e25 0.2s0 RU 1 967 965 6.625 0.260 RU 1 965 962 6.625 0.200 RU 1 962 961 6.625 0.290 RU 1 961 960 6.625 0,200 RU 1 960 955 8.625 1.280 HD 1 335 720 8.625 0.250 RU 1 720 730 6.625 0.250 E t, 1 730 735 8.625 0.250 12.000 RU 1 135 737 8.625 0.250 Et, 1 737 734 H.o25 0.250 12.000 RU 1 73H 739 8.625 0.250 Ru 1 739 740 0.625 0.250 HU i 740 745 8.625 0.250 El, 1 745 750 6.625 0.250 12.000 Rb 1 750 753 8.o25 0.250 RU 1 753 755 d.625 0.250 RU 1 755 757 8.625 0.250 RU 1 757 760 b.625 0.250 l EI. 1 760 765 8.625 0.25u 12.000
-/ 2 /-
*** T4R PIPItG AMALYSIS SUPRnNT 30*VANY. PROGRA.* *** i REV G PRESS MEL SYS 5639 STRESS SUoARY -- - --
CHKD. BY ptQ DME t-3-8.5 ! M E'4 B E R DATA 3 BEw0 COMPhai4T SECTI9r MEMBER 0.D. THICn. RADIUS (IN) (13) (14) RU 1 765 770 e.625 U.250 RU 1 770 1260 e.025 0.250 j d.525 0.250 R0 1 1260 1255 RU 1 1255 1252 8.t?L 0.250 RU 1 1252 1250 8.625 0.250 RU 1 1250 1245 8.625 0.250 EL i 1245 1240 8.625 0.250 12.000 RU 1 1240 1230 8.625 0.250 R tl 1 1230 1225 6.625 0.250 RU 1 1225 1220 d.625 0.250 RU 1 1220 1215 H.625 0.250 RU 1 1215 1210 8.625 0.250 RU 1 1210 1208 8.625 0.250 RU 1 1206 1205 6.625 0.250 RU 1 1205 2205 8.625 0.250 RU 1 1205 1200 H.625 0.250 RU 1 1200 1195 e.625 0.250 EL 1 1195 1190 8.625 0.250 12.000 RU 1 1190 1185 8.625 0.250 ; RU 1 1185 1175 8.625 0.250 RU 1 1175 1165 6.625 0.250 EL 1 1165 1160 e.625 0.250 12.000 RU 1 1160 1155 8.625 0.250 RU 1 1155 1150 8.625 0.250 EL 1 1150 1145 b.625 0.250 12.000 Ril 1 1145 1140 8.625 0.250 RU 1 1140 1138 U.625 0.250 R t1 1 1138 1135 8.625 0.250 EL 1 1135 1130 8.625 0.250 12.000 RU 1 1130 1125 6.625 0.250 RU 1 1125 2125 e.625 0,250 RU 1 1125 1120 9.625 0.250 P il 1 1120 2120 0.625 0.250 R i! 1 1t20 1115 d.625 0.250 RU 1 1115 1110 o.625 0.250 RU 1 1110 1105 6.625 0.250 EL 1 1105 1100 8.6/5 u,250 12.000 RU 1 1100 1090 6.625 0.250 Eb 1 1040 1085 e.625 0.250 12.000 l Ril 1 10H5 lobo 6.625 0.250 , RU 1 1080 1075 8.625 0.250 RU 1 1075 lota 8.525 0.250 RU 1 1065 1060 8.02d 0.250
...____............___ ._______:.L6dC........................................
I DATE: TFP PROJECTE I . I 10/27/82 PI31NG ANALYSIS SUPPOWT SUMMANY PHOGRAM RHH 5639 I . I PEV G I l I SUBJECI: PRESS REL SYS 5639 STRESS
SUMMARY
I t I I f I DRAnINGS: DAVIS PESSE PRESSORISER NELIEF SYSTEM I i I REChTEL DRAWING HL-230A . _ _ _ I l I-------------------------------------------------- BY , _ DA fE /--J-J$) li SrHESSES CllKD. BY M Q DATE j-3 _83_ STRES$ ANALYSIS INPOT DATA PIPE DESIG4 PEAK RHANCH ALLUW. SERESS(PSI) INTENS. STRESS INDICES NODE CLAS5 PRESS. PRESS. POlhTS SC SH SF FCTR. B1 B2R B2B 69 i B 2500, 2500 18600 15900, 16700, 100 1 B 2500, 2500, 18600, 15900, 16700, 105 1 6 2500 250u. 18600, 15900, 16700 110 1 n 2500 2500, 18600 15900, 16700 115 1 6 2500 2500 18600, 15900 16700 120 1 B 2500, 2500, 18600 15900, 16700, 125 1 K 2500 2500, 18600, 15900 16700. 130 1 h 2500, 2500, 18600, 15900 16700 135 1 8 2500 2500. 16600, 15900. 16700, 138 1 6 2500. 2500 18600 15900 16700 140 1 6 2500. 2500, 18600, 15900, 16700, i 145 1 B 2500. 7500, 18600 15900, 16700, I 150 1 4 2500, 2500 18600 15900 16700
) 155 1 6 2500. 2500, 18600, 15900 16700, 160 1 3 2500 7500 18600 15900, 16700 :
165 1 a 2500, 2500 18600 15900, 16700, 170 1 e 2500, 7500. 16600, 15900, 16700, 175 1 6 2500. 2500 18600 15900 16700 180 1 e 2500. 2500, 18600, 15900, 16700, i 185 1 b 2500 2500, 18600, 15900, 16700, 18d 1 b 2500 2500, 18600, 15900, 16700 , 190 1 6 2500 2500. 16600, 15900 16700, 195 1 t' 2503 2500 16600 15900 16700, 200 1 b 2500 2500, 18600, 15900 16700 215 1 9 2500 2500. 18600 15900 16700, ' 225 1 e 2500. 2500, 18600 15900, 16700 235 1 6 2500 2500 18600 15900 16700. 255 2 e 500 500, 18800 16050, 16700 ; 265 2 6 530 500, 1b800 16050 16700 ; 280 26 500 500, 18A00 16050, 16700 j 285 2 6 500. 500 16800. 16050, 16700 .' 281 2 B 500, 500, 18800 16050, 16700, 290 2 H 500 500. 1E800 16050, 16700 ! 295 2 n 500 500 16900 16050, 16700 ! 296 2 6 500 500, 16800, 16050, 16700 l t I
.I 1
................................::t3}:......__ ..............................
PROJECT 3 I DATE: THR I I 10/27/b2 PIPING ANALYSIS SiiPPORT Sudh ARY PROGWAM PHP 5639 I I REV G I > I
SUBJECT:
PRESS REL SYS 5639 STRESS
SUMMARY
I I , I I DRAW 1oGS: DAVIS bESSE PRESSURISEN RELIEF SYSTEM I I BECHTEL DPAn1hG hL-230A 1_ < I------------------------------------------------- 1 8 #'0868 CHKD. BY DWB DATE /.3 % STRESS ANAbiSIS 1hPUT DAT. , PIPE DESIGN PEAK PRANCH ALLOW. STRESS (PS]) INTENS. STHESS INDICES NODE CLASS PRESS, PRESS. P0lblS SC SH SM FCTR, bl B2R B23 300 2u 500 500 16H00. 16050, 16700, 305 2 6 500, 500 18R00, 16050, 16700 315 2 B 500, 500 18900 16050, 16700 320 2 a 500, 500. 16900 16050 16700, 335 2 B Suo, 500, e 16800, 16050 16700, 335 2 B Suo. 500, R 16800. 16050, 16700 340 2 h 500, 500, 18800 16ubu. 16700 345 2h 500, 500 1b800, 16050, 16700. 350 2 h 500 500 18800 16050 16700 995 2 h 500 500, b 18800 16050 16700 995 2 6 500 500, F lb800 16050 16700, 675 2 H 500, 500, 18800, 16050, 16700 670 2 3 500 500 18800 16050, 16700
) 667 2B 500, 500, 18800, 16050 16700.
665 2 h 500, 500, 1bR00 16050 16700, 995 2 a 500 500 k IbA00, 16050 16700, 975 2 6 500 500 18800, 16050, 16700, 970 2 6 500 500 16800. 16050, 16700, 967 2 6 500. 500. 16800 16050, 16700, 965 2 B 500 500, ibH00, 16050, 16700, 335 2 o 500 500 P lb800 16050, 16700, 720 2 n 500, 500, 16R00 10050 16700 730 29 500 500 1b900 16c50, 16700, 735 2h 500, 500. 18800, 16050 16700 737 2 H $00 500, 18800, 16050, 16700, 738 2 n 500, 500, 16H00, 16050 16700, 739 2 8 500, 500 lea 00 In050, 16700, 745 2 a 500 500. 18800 16ubo, 16700, 750 2 S 509 500. 1bAut. 16050 16700, 760 2 S 500, 500 16000 16050 16700, 765 2 H 500 500 18800 16050 16700, 770 2 6 500, 500 16600, 16050 16700 1260 2 h 500, 500 1b800 16050 16700 1245 2 n 500 Suv. IP800, 15050, 16700, 1240 2 n 500 500. 16800 16050 16700 1230 2 6 500, 500, 16800 16050, 16700 k
........__ .......................c........................
f I DATE: ThH PROJECTI I I 10/27/87 PIPING ANA1.YSIS SUPFUMT
SUMMARY
PROGHAM HHH $b39 I I I REV G I {
..................__......________........ .................................. j
)I
SUBJECT:
PHESS REL SYS 5639 STRESS
SUMMARY
I T I I ? I DRAWINGS: DAVIS BESSE PRESSURISER HELIEF SYSTEM I I BECHTEL DEAWING HL-230A _ _ ._I l I--------------------------------------------------- BY' DATE/-J '8) STRESSES CHKD. BY pHEE DATE l-3963~ pj STRESS ANALYSIS INPUT DATA !I i-t PIPE DESIGo PEAK bkAhCH ALLOW. STRESS (PSI) IwTENS, SIRESS INDICES ( NODE CLASS PRESS. PRESS. POINTS SC Sh SM FCTR, bl b2h B2B t
}
1210 26 500, 500. 16700 18800, 1o050 1205 26 500, 500 16800 16050, 16700, 1200 2 k 500 500, 18800 1e050, in700, 1195 2 6 500 500 18000 16050, 16700 [ 1190 2 b 500, 500, 18800, 16050, 16700 -, 1165 26 500, 500, 16800 16050, 16700 1160 2 6 500, 500, 16800, 16050, 16700 , 1150 2 B 500, 500, 16000, 16u50, lo700, 1145 2H 500 500 18800 16050, 16100, 1140 2e 500 500. 18900 30050, 16700 2B 18800 1138 500, 500, 16050 16700 1130 2 B 500, 500, 18800 16050 16700, j 1125 2 6 500, 500 18800 16050, 16700 ; 1120 2 6 500. 500, 18800 16050 16700 I 1110 ? B 500 500. 16800 16050 16700 , 1105 2 6 500 500 18800. 16u50, 16700, ! 1100 2 6 500, 500 16800 16050 16700 l 1090 2B 500 500, 18800, 16050, 16700 1085 2 6 500, 500 18800. 1o050, 16700 ' 1075 2 6 500, 500 16800, 16050, 16700, i 1060 2 n 500, 500. 18800, 1e050, 16700 3 i I l I e E I
..................................A7.1....................................... ,
I DATE: TMH PWOJECT! I i I 10/27/67 PIP 1f4G ANAbYSIS SUPPORT SUtHARY PHf1GR A S. WhH S639 I REV G I , I I PRESS REL SYS 5639 STRESS
SUMMARY
hI
SUBJECT:
I I + i 1 DRAWINGS: DAVIS BESSE PRESSURIStR RELIEF SYSTEM I BECHTEL DRAWING HL-t30A
~- - - - - -
l_ i I I------------------------------------------------ BY M DATE /-J -83 I S tl P P O RT SYS TE M OY M .DATE l t g H ES1 d A I 14 I SUM M A H Y PothT DIRECTION TYPE 69 ALL ANCHOR 770 ALL ANCHOR 1060 ALL ANCHOR '{' 140 Z RIGID 4 ( 1R0 X RIGID 1d0 Y RIGID i I' 180 Z RIGID i 190 Y SNOBBER 215 Y HIGID 215 Z RIGID 255 X S H U B e r.H 1 255 Z ShUBbbR 4 . I 296 X S h 0 B B r.R , 340 Y RIGID i 665 X SNUBBEH g 9ns X SNUMBER 720 X SNUBBEn 720 Z HIGIO {- 770 Y ROTATIONAL 739 Y RIGID 1230 Z RIGID 1210 Y RIGID 1200 X RIGID 114v Y ShuBHER , b i t l' 8 I' i h h
I D A f t: T tA R P R UJ t.C T ! I I 10/27/81 PIPING A'. ALYSIS SUPPORT SUMM ARY PROGRAS RHH 5o39 I I REV G I l SU6dECT: PkESS REL SYS 5639 STRESS
SUMMARY
hII DRAwIwGS: I DAVIS BESSE PRESSURISER REL: BY /A4 DATE /-3-8.7 i BECHTEL DRAnING HL-230A .CHKD. BY DN8 DATE l-3-005 : I I-------------------------------------------------' H A N GER / R ESTR A I N T R E A C T I U N 6 ! THERMAi, LOAD WEIGHT SEISMIC 10A0 UESIGN LOAD , (LBS) I,0 A D (LBS) (LES) ' P 01 a l' TIPS (+) (-) (LbS) OBE max (+) (-) 140 Z HIGID 0 479 -120 321 603 603 1203 i 180 X HIGID 0 2850 -100 252 473 473 3 23 ,; 180 Y HIG10 0 130 470 197 745 1215 745 180 Z RIG 10 049 0 80 4'.99 936 1666 936 . 190 ( S.UJ6HEs 508 954 954 954 215 Y HIGID 390 0 950 94 177 1517 177 215 4 RIGID 0 80 -10 370 695 695 785 I 255 x SMl66ER 33 62 62 62 255 7, S.066ER 312 585 595 585 296 4 S a J 3 B r.R 64 121 121 121 340 Y RIGID 0 1500 640 1074 2014 2654 2874 665 ( SNUBHER 194 364 364 364 965 X SdO6hER 124 232 232 232 720 A S406sER 170 320 320 320 l 720 4 FIGIO 140 170 -10 Su3 943 1273 1123 720 f PorAilau 9190 1030 280 7832 14695 24755 15435 739 i RtGID 1100 0 340 1023 1918 3558 1918 1230 Z RIGID 40 0 -50 170 320 320 370 1210 'i RIGID 940 0 700 d2 153 1693 153 1200 A RIGID 0 819 0 207 386 388 1208 1140 f SausHER 221 414 414 414 m ) 1' E : Un A')S fin R < 1 l A l' l O N A L, HESTHAldTS art. 14 tl NITS OF IN-LeS. l d
i 1 I O A CE : TMR PwoJECI: 1 1 10/27/87 P1' JING AWAI,VSLS SUPPnRT SovvAWY PRDGRAM dnh bo39 I I HEV G 3-l
. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . BY DATE /-3 -8 3 l I SUBJECf: PRESS REL SYS 5639 SCRESS SuaMAxY
> g CHKD BY CH8 DATE t-3-83 o I DHAvlNGS: DAVIS 4 ESSE PRESS 0HISER HE I IlECNTEL Di4A4IdG 4L-230A
- I-------------------------------------------------------------------------- 4 ,
i 4 A '4 GER / RES T R A 1 N T U 1 S P LA CEM EN 'I S
****** fHtHMAL ****** **** MAX StISMIC **** ;
Pol 4f '40 OX UY OZ DX DY DZ 140 (t) 0.353 1.556 0.000 0.040 0.062 0,000 (-) 0.000 0.000 0.000 180 (+) 0.000 0.000 0.000 0.000 0.000 0.000 (-) 0.000 0.000 0.000 190 (+) 0.132 0,000 0.000 0.000 0.0v0 0,002 (-) 0.000 -0.149 -0.034 215 (+) 0.655 0.000 0.000 0.000 0,000 0,000 (=) 0.000 0.000 0.000 255 (+) 0.i41 0.168 0.000 0.000 0.000 0,000 (-) 0.000 0,000 -0.150 296 (+) 0.eH6 0.179 0.000 0.000 0.006 0.023 I (-) 0.000 0.000 -0.119 340 (+) 0.517 0.000 0.241 0.005 0.000 0,165 (-) 0.300 0.000 0.000 55b (+) 9.607 0.219 0,402 0.000 0.128 0.377 (-) 0.)00 0.000 0.0v0 965 (+) 0.512 0.005 0.542 0.000 0.126 0.377 (-) 0.000 -0.020 0.000 720 (+) 0.427 0.000 0,000 0.000 0.000 0,000 (-) 0.000 -0.122 0.000 h
.............................. .....J.'."..................... ................
I DATE: TMR PROJECT: 1 1 10/21/82 PIPI'JG A.J AbYS IS SOPPodT S u v .e. A H Y PHnGkAM RHH 5639 1 I REV G 1 BY - l I SilBJECT: PfMS S REL SYS S639 STRESS
SUMMARY
DATE/ S d_3 DRA41aGS: DAVIS BESSE PRESSud1SEH HEL
~ D83 I BECurEL JRAWI:dG HL-23uA t.................................................
H A 'J GEH / R ES TR A I N T D ISPLA CE M EN TS
****** THERMAL ****** **** NAX SEISHIC ****
POIuT au. OX DY UZ DX DY DZ 7 19 (+) 0.345 0.000 0.000 9.012 0.000 0.064 (~) 0.0u0 0.000 -0.245 1230 (+) 0.000 0.604 0.000 0.032 0.000 0.000 (-) -0.474 0.000 0.000 1210 (+) 0.000 0.000 0.000 0.021 0.000 0.014 (-) -0.075 0.000 -0.054 1209 (*) 0.000 0,000 0.009 0.000 0.000 0.003 () 0.000 -0.181 0.000 1140 (+) 0.000 0.535 0.382 0.03e 0.000 0.014 (-) -0.260 0.000 0.000 I 4 l l l l 1 l l l f l ) I
l
......._...........................!4 M._. ..___................. ...........
I DATE: TMR PROJECT I ; I 10/27/d2 P191NG A4Al,YSIS SiiPPORT Sda4AHY PROGPAM RHH 5639 I j I HEV G I )I Sus.iECf: PRESS REL SYS 5639 STRESS
SUMMARY
I I DaAwinGS: I DAVIS BESSE PRESSURISt.H kEL BECHTEL UNAWING HL-23uA BY M
, DATE /d -f_.3 I-------------------------------------------------
0 DATE /-3-63 , STRESS INTE4SIFICATIni4 FACTORS Arid STdESS T l4 DIC ES FIG. ti C - 3 6 7 2 . 9 4 - 1 1'AbLE o8-36s3.2-1 CD iPokr'dT II.T t,r.S I F IC A1 ION STRESh 1* JUICES r:0D t TYPE /CbASS FACTOR B1 t< 2 R r2B 69 3 1 1.000 0.500 1.000 0.000. 100 3 1 3.000 0.500 1.'s00 0,000 , 105 9 1 1.010 1.000 1.642 0.000 1 110 4 1 1.010 1.000 1.642 0.000 115 3 1 1.000 0.500 1.000 0.000 120 9 1 3.010 1.000 1.642 0.000 J75 9 1 1.010 1.000 1.642 0.000 130 3 1 1.000 0.500 1,000 0.000 135 4 1 1.010 1.000 1.642 0.000 13b 4 t 1 010 1.000 1.642 0.000 140 3 1 1.000 0.500 igd 00 0.000 145 3 1 1.000 0.500 1.000 0,000 150 9 1 1.010 1.000 1.642 0.000 g 155 9 1 1.010 1.000 1.642 0.000 100 3 1 1.000 0.500 1.000 0.000 165 V 1 1.010 1.000 1.642 0.000 170 4 1 1.010 1.000 1.642 0.000 ': 175 4 1 1.000 0.500 ?.000 0.000 180 3 1 1.000 0.500 1.000 0.000 185 3 1 1.000 0.500 3.000 0.000 18e 3 1 1.000 0.500 1.000 0.000 190 3 1 1.000 0.500 1.000 0.000 195 3 1 1.000 0.500 1.00n 0.000 200 3 1 1.000 0.500 3.000 0.000 715 3 1 1.n00 0,500 1.000 0,000 225 4 1 1.000 1.000 3.569 0.000 235 4 1 1.000 1.000 1.569 0.000 755 4 2 1.000 0.500 1.000 0.000 265 9 2 3.166 1.000 5.178 0.000 2H0 9 7 3.186 1.000 5.17e 0.000 2H5 a 2 3.186 1.000 5.176 0.000 287 9 2 3.186 1.000 5.178 0,000 290 3 2 1.000 0.500 J.000 0.C00 295 5 7 1.000 0.500 1.000 0.000 296 4 2 1.000 0.500 1.000 0.000
...............................lW~ .... ... .. . ......... ... ...... ... .
I DATP : 'l ! . it P Pl!.)k(:T 5 I l' 0 6 i l I. h Hi4 56.19 1 10//7/67 /. ' n!,/ Sib S t.P h i o< l .'.i. . i t. n Y P r< f t . L e i . j I bhV h 1 I b u b.J EC'l : PHLSS H El. NYS $634 STkE.SS SunmANY ] t>H Ab l oGh : 1AVib SEbbE Ph hSSilb l SEb hhb1 BY DATE/ .3 '8.3 1 PLCbTF1 he<AviAG r41,- 2 3 0 t. CHKD. BY P85 DATE l-36.3 1-------------------------------------------------- STWESS l i.'1 E..S I F I C h'110 e F A C'f u R S Aii STkFSS IliICVS t 16 C .4 6 7 2 . 9 i. - 1 i A r$ L E. tF-3nb3.2-1 cr .PAEgT isjF Sl>ICA1104 STHE66 fuu1Cc5
.d ll: h ti?F./CI.uS$ VACTUk el n2R F?B 300 'a 2 3 . t r$ 6 1.000 5.17 h _ o.000 305 o 1. 3.166 1. u . t' 5.17F 0.000
.41 5 9 / 3.lbn 1.000 5.17n ( 000 32( 9 2 1.1hh 1. t. o r 5.1 't F 0.000 345 10 2 ?.194 1 . s o f. - 3./96 3.290 335 ~4 7 7.194 0.500 1. o t. 0 0.000 340 3 / t.ooo 0.5eb 1, t:( o o.e00 345 o / 2.970 1.000 4.74h 0.006 350 " 7 ~).w/o 1.veo 4 . 7 o. 0.000 945 lo 's 1."43 1.obe 7 . 7 t' 3 2.763 995 J 2 6 a43 0. % D ).000 0.000 675 4 2 2.439 1. o e t' 3.463 0.000 670 4 7 7.439 1. t10 0 3.963 0.000
) 667 ~4 / 1.000 0.500 1. h t o 0.000 6n5 4 7 1.ooO 0.500 1.000 0.000 995 3 / 1.943 U.Soe 1. t+ 0 0.000 9 15 0 2 2.444 1.000 3.963 0.000 970 >
'< 2.434 1.voo 3.ch3 0.000 967 I 7 1.000 o.500 1. t b o 0.000 965 .I y 1.000 tc,5hD 1. t b U O.090 335 i ? 2.194 '. . % o 1. t - L o G t. v 0 7)t 3 '/ 1. ot o '.5tD 1. t oo 0.000
/ it u / 7.420 1. 0 :o c . 7 @. 0.000 7 45 '. 7 ?.920 1.000 4.7c6 0.000 737 o 7 7. 'd 7 0 1. o'; o /' 7 s. 6 0.000 73h o 7 ?.970 1.000 4.74. 0.000
~$9
/ -4 7 '.000 0.50D 1.000 0.000
'95
/ / . . 82 0 1.000 4 . 7 *. h 0.000 750 .
7 2.970 1.000 c.7*6 0.000 76b -
'/ ?.920 1.000 4.746 0.000 765 *. 7 2 . c,2 0 1. con 9.746 0.v00 770 3 2 1.000 0.500 1 l' t. o 0.000 17 n t 4 / 1.'a o t,.5ao 1. i D e 0.000 174S -
7 / . 'W o 1.000 4.79k o.0Vo
!?al o / ?.9/0 1.000 4 . 7 4 r- U.000 12 4 4 7 1.000 0.500 1.009 U.000 k
................................----)<l...................................... -;
Te H l'l4 00 Ffl : 1 I DI. I E : 1 10 / / 7 / ts ) P i P l t (, ta i e 1. Y r 1 b h o 6- 6 t 'P i h o
- e 4 r t'i P l< t ( . 6 10 P tsu Sb39 )
iM t. 1 I pI ...........................--............................................-... Silt'.lF CT : PkESS PEL SYS 5634 S'l W55 S o e' N A t< Y 1 1 bk A r i t'Gh: l' A V i n I F.SS E. e) F ICS S t> H I S t h n t.I. I SY . DATE /- 3 -H_5 1 1.t (.tvi r L !!b Av.'II. G HL-23ti. 1 - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - . . Cl ! KD . B Y DP S D AT E I 65 ST i< F.S$ I N 'I t . t s l F I C I. T l i o- F A L'l lI9 S mar h 6 455 11' L I C t. S FIG. C-3 t 7 7. 9 /t- t i A rsi. h I i - 3 r s .s . 2 - 1 Co va.rr 6 1 *. l F SI F IC A) lina M %55 1. 01C t.h
.. t il t, 'l ) P t /Cl.nhh t A C Y D e* b) D/P t 2 f.
l?ti 4 7 1.000 o . M t. 1.000 0.000 1205 3 2 1.000 o . b' D 3 . o b ts 0.00G 12G0 -' ? 1. " .i d 5. 5 t' D 1.oLo U.voO 1195 9 / 7.920 1. ' 0 ( <, . 7 4
- 0.000 1190 ' 2 7.920 1.etd- 4 . i c t- 0.000 1165 4 2 i.9?o 1.000 /. 7an 0,000 1160 4 2 2.920 1. 0 0 f' 4.746 0.000 115l 4 2 S.920 1.000 4.746 0.000 IL45 5:- 2 7.9/0 1.006 4.740 0.000 114( a './ 1.000 0.500 1. t + " U.000 11 % 3 2 1,0a0 0.500 1.oro 0.000 1130 C 7 2.970 1.000 4.748 0.000 1125 4 2 1.000 0.t u0 1.000 0.000 1126 4 2 1.000 0.5Jo 3 . t' OO 0.000 1110
~
3 ? I . o e o.500 1.000 0.090 1105 o 2 1.'320 1.000 4.7 r 4.000 1100 '4 2 7.920 1.000 4.74a 0.000 1690 ' 2 >.970 1.000 4.746 0.000 10k5 t- 2 2.9/0 1.000 4.74a 0.ve6 1075 1 > 1.ovo 0. 5t.0 1.000 0.006 1000 3 7 1. o u f' ' .500 1. L (ce 0.000 h
.____________ .... ........____./3_2.....__..
I is A J L : IW PkUJECT: 1 1 10/27/n2 PJE1"G Fli VSIS bbP6 KT Su ^ *.aoi un r GF A's FnF 5639 1 1 FM b I I SubJtC1: PFFSS REL sis 5639 81HESb S O 4 ** aa H Y I 1 1 I DRAe1NGS: DAVIS F E:SSE PPE.SSliblSLP t L I. I E F S Y S'I r.*i j I E'P Ch1 M ob Ah lH. n L = 2 3 01, I=================================================' ~ BY DATE / 7J @ ST F F S S S Il e , A F ac - 3eby l 60.(9) 80.l9) EO.(o) 1.OSH W / r. . h: . w/O F. . e, . 1. 2 S r.
. b n E. PSI ESL PSI P61 PSI 69 b424 15900 9455 190bo.
100 94H0 15900, 10e 54 190EO. 105 5609. 15900, 7766 19080, 110 5776. 15900, 1135 14uhu. I15 3170, 15900, 5952, 19 oho, 120 54R6 1%o0 b712 19060, 125 5532. 15500, o6441. 19 0 t v . i 139 % 23 15900 bkO9 I'so*0 135 %>n. 1%ao, c197, l '* u t o . 1 ib 5isi. 154i 0, 7 0 tfl . l 's o 5 0 140 5716 15900 73ni. luo80, 145 5575 15900, 7070 19050, 150 56H9 15960 7217 19000 1% % 49 1 % 00 7220. 199EO. 160 5297, l%ho. 7747. 190Fu. I65 5 7 2 'i . 1%ou. o529 190h0, 170 5658, 1 %D0, h237 190 f10 175 5 3 <e 2 . 1596o. 5498 19080 I80 66x7 1590G. 9543. I9080 185 55??. 1 % o' . oh57. 19080 IbH 6xyh. 159eo. /w46 140PO. 190 5 9 a. :1 15900 6708 190:50. 195 b5' 5 1 % 00 10578 19000 200 h477, 159ho. 19667 19060 215 6797 15960 11016 190HO. 225 6792, 1 % 00 I l fil e . 190w0 e35 56%. t %00, 93/.4 2 0 0510 255 5996, 16050, 5576. 14760. 265 5764 10050, n480 19260. 240 5m94, 16050 /016 19260
............................._...../ M.........._........____............... .
Phud r;CT : I DAlt: Ti1R 1 I 10/27/h/ Pi t'l' G A.Ahthlb SUPPlikY d ti . e. n e< Y Pks tw A< HnH 5639 I HFV G 1 1 I Siltu r C l : P k r.SS 9Ei,.SYS 5 6 3 'd Sl* Ebb SummANY I I I I ORAv.1:4GS: DAVIS hESSE PHESSONISrk kLi,1EF SYS*lta 1
~
i tsECb1 bl. UR Aw TM; al.-2 30 A 1---------------------------------------*---------- By DATE M W CIKD. BY CH8' DATE /-3-63 1 S rR ESS S h - a A 9- . NC - 3652 EG.(9) EG.(9) EO.(b) 1.nSH W/F.E. n/O F.E. 1,2SH MJUL PS1 PSI PSI PSJ PSI 285 5894, 16050 1015 19260. 287 57/1 1605'). n907 19260 290 5120 I6059 5616 19260 295 5056 16050 5591 1926u. 29e 4944, 16050, 5636 19260, i 30v 5185, 16050 6937 19260. 305 5159, 16050 64h3 19260 315 obO2. 160*0 e416 I9260 32v 7085 1605u. 9473 19260 335 5515 16050 o423. 19260 335 5560 16050 7643, 19260 349 9W3 loMo. 3839 19260 345 5473. 16U50. 74e3 19260 356 5kS2. 1Ae50, 740b. 19260 995 5157, 16 0 'i O . 0006 19260 495 4397 16050, 4H52. 19260. 675 4593. 1e050 53)2. 19260, n7c 5059, 16o56 o325, 19260, 667 3745 16650, 4335. 19260 665 3*26 I s t. 5 0 , 4133 L9260 495 3457 16050 4525 19260 475 4593 16050 5378 19260 4 10 5061. t h 0 5 tc . o337. 19260 957 3145 1n050 4339, 19260 905 3613 16050 914H. 19260 435 35i9 t6050 556A. 19260
'7e
/ 46/h. I69%d. r) 4 7 v . 19750, 13e 596+, Ino50 '/142 19260, 735 5991 16 0 's e . 196H. 19260 737 504/. 16050 7454 19260 73h 50H7 16050 e193 L9260, f
..___.._.....__........._...._..lf..._____..........____.................
I DAW : rtG P H UJ r.C r : 1 I 10/27/8/ Pielun a .. A ' Y .5 t s S U PP u x 's ht. ia 4 Pr<t w iv- wr0 5039 1 I PNV t. i I SubJEC1: PRKb5 ke:L SYS 56 39 STRh.SS SusiaHY d I I I I DRAi'llG3: DAVIS t4ESSM PHESSUHJStH N t. la l F F SYSTra J I dkCHfEL uRAulnG 41,-23lA T I----------~~------------------------------------- BY [AM DATE /--3 -83 sT u vsS su- a a , CHKD. BY DHB DATE /-3-83
<C- a n d '/
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!?45 4547 16050 5054 lu260 1240 46o1, i n o 'io . 51/1 11260 I130 4 ,4 InoSo, d706 19760 1210 4n77 1%obu. 5056 19/60
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SUBJECT:
PFESS R El; hyS 5639 SThESS SilhrANY l I 1 I DHA+1'JGS: DAVIS ILESSM PHES5t>H J 5r 3 k ht,I EF di STr'i. 1 I b t C Ws r 1, o x A n l i.G 6t t.- 2 3 t. A I----------------------------~~-------------------. BY M DATE/93 -83
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1/$0 4753. "Fk90 i L/1J 5260 /6e90 1 / -)') 5Lt3. 7kH90 1/"o 5191. /t890, 119S c 1 17 , 2er90 I190 611 f.; . 7Ee90 3 1155 6125. 26k90 ) 1150 594h. 2ee90 ' L150 5869 2bb90 I145 n355, 26890. I141 5752. 2ek90 1138 4913. '>p690 1130 5226 2ee90 L l '/ S 5791 28a90 11/4 S757 78-90
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1 110 4l05 77725. 0 - 1 115 2499 17275. 0 - 1 120 2105 27?25. o- 1 I?$ '4 4 / 6 . 27225. t' 1 130 S*0d. ?7225. 0 - 1 135 n945 ?1725 o - 1 13e Iv//D. 77??S. 0 - 1 140 10140 2722d. o- 1 145 17192. 27225. o - 1 D 150 1c214 27?25 0 0 1 154 lb/on. 2'I225. 1 160 1135 ?/725. o - 1 165 1/I47. 17/25. 0 - 1 U - 170 15/40 '/7725. 1 175 12856, 27??5. 4 - 1 180 l'il e 5 2/225 0 - 1 185 / 635 712/5 o - 2 18b 4/00, 27725. u - 2 l 190 4412. /77/5. O - 2 195 13 M* . 27/25. O - 2 l 200 n '4 5 4 , 27??5 O - 2 l 215 4/39 7/2/5, 1 - 2 225 4793. 7///5 i - 2 1 735 4 / ) .4 77??5. 1 / 255 3551 /1513. 1 - 2 265 i$672 21513. 1 - 2 l 280 16046 77513. 1 2 i l l l l l
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Technical Report i %' N TR-5639-2 ENGNEERING SERVICES . ) -154-7.0 DRAWINGS f 7.1 D-7171 Rev. 1 Isometric, Pressurizer Relief System 7.2 E-5986 Rev. 4 Pressurizer Relief Valve Modification s. p
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l Technical Report TME TR-5639-2 N SER\/lCES h -155-
8.0 REFERENCES
- 1. " Evaluation of RELAP5/M001 for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads", prepared by Intermountain Technologies, Inc 1400 Benton, P.O. Box 1604, Idaho Falls, Idaho 83401.
- 2. " Valve Inlet Fluid Conditions for Pressurizer Safety and Relief
~
Valves for B & W 177-FA and 205-FA Plants", prepared by Babcock and - Wilcox Co. Lynchburg, Virginia, EPRI NP-2352-LD, Project V102-17. .
- 3. "PWR Safety and Relief Valve Test Program, Valve -
Selection / Justification Report", prepared by MPR Associates participating PWR Safety and Relief Valve Manufacturers EPRI PWR h Safety and Relief Valve Test Program Staff EPRI NP-2292-LD, Project l, . V102.
- 4. "RELAP5/ Force Users Guide", prepared by Gilbert Associates Inc.,
Reading PA.
- 5. "RELAPS/M001 Code M=.nual", prepared by EG&G Idaho, Inc. Idaho Falls, Idaho 83415.
l
- 6. ASME Boiler and Pressure Vessel Cooe, Section III, 1971 Edition -
with Addenda to Summer 1973, 1974 Edition for Supports
- 7. Crane Technical Paper No. 410 _",,
- 8. TES/TECO Meeting at Davis Besse Site, May 4-5, 1982
) '
Technical Report TR-5639-2 SPTME
-156_ ENGNEERING SERVICES
- 9. TMRPIPE & TMRSAP - A System of Computer Programs for the Complete ,
Analysis of Nuclear Piping - April 1976 version.
- 10. TMR Technical Report No. E-1495-10c dated July 20, 1973. ,
- 11. Teledyne Engineering Services Technical Proposal PR-5700a, dated January 20, 1982 " Evaluation of Pressurizer Safety / Relief Valve Discharge Piping - NRCNUREG-0737. ,
- 12. NUREG-0737, Clarification of TMI Action Plan Requirements
- 13. " Secondary Stress Indices for Integral Structural Attachments to Straight Pipe," W.G. Dodge, E.C. Rodabough and S.E. Moore, Welding Research Council Bulletin 196 dated September 1974.
^
) 14. " Local Stresses in Spherical and Cylindrical Shells due to External Loadings," K.R. Wickman, A.G. Hopper and J.L. Mershon, Welding Research Council Bulletin 107, March 1979.
e Y o i 4
Technical Report h TR-5639-2 APPENDIX A PLANT SPECIFIC EVALUATION OF THE SAFETY AND RELIEF VALVE INSTALLATION Davis-Besse Nuclear Power Plant WTELEDYNE ENGINEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254
'~
617-890-3350
Technical Report "R TEL M NE TR-5639-2 h Appendix A ENGNEERING SERVICES A-1 PLANT SPECIFIC EVALUATION OF THE INTERIM SAFETY AND RELIEF VALVE INSTALLATION The following is Teledyne Engineering Services' evaluation of the two safety valves and the one power operated relief valve (PORV) installed in the Davis-Besse Nuclear Power Plant. The conclusion is that the valves are acceptable and will operate properly when needed. It was possible to arrive at the acceptable conclusion for the safety valves (2) partly because they wer moved from the valve room to the top of the pressurizer with no discharge piping. This eliminated the long inlet piping, the loop seal, backpressure, and the possibility g of unstable operation. Unstable operation is defined as rapid opening and closing of the valve due to pressure occillations in the inlet or discharge piping. Test results of the valve by Crosby and similar ones by EPRI show acceptable operation. These results are discussed further in this report. The PORV was not moved and the discharge piping to the quench tank was left in place. The PORV was tested as part of the EPRI test program. The results are discussed further in this report. ,. This submittal follows a format similar to the one suggested by the EPRI Guide for application of the valve test program results to plant specific evaluation. The PORV block valve was not tested, but a similar design was tested with satisfactory results. this report. The results are discussed further in )
l n Report "9 t M N E Appendix A A-2 I. Description of Safety and Relief Valve Installation . 1.1 Description of the Safety Valve Installation A. Valve Parameters
- 1. Two valves
- 2. Crosby 4M1 6 Style HB-86 BP
- 3. 347,042 lbm/hr capacity
- 4. Four inch 2500 pound ANSI inlet, six inch 600 pound ANSI outlet
- 5. Set pressure 2500 psig B. Inlet Piping Parameters
- 1. The valve is mounted on the pressurizer nozzle
- 2. There is no loop seal C. Actuation Transients (Reference NSSS Fluid Inlet Conditions, see Table 1) 1.2 Description of Pelief Valve Installation (PORV)
A. Valve Parameters
- 1. One valve
- 2. Crosby Model No. HPV-SN
- 3. 158K lbm/hr (steam)
- 4. 2-1/2 inch 2500 pound ANSI Inlet; four inch 600 pound ANSI outlet
- 5. Set pressure 2450 psig I
Report W N NE ENGNEstNG SERVCES Appendix A A-3 B. Inlet Piping Parameters
- 1. Valve is in t.he valve room approximately 20 feet from the pressurizer
- 2. There is a heated loop seal
- u. Actuation Transients (see Table 2 taken from Reference 4) 1.3 Description of P0RV ;
Block Valve A. Valve Parameters
- 1. One valve g
- 2. Velan B9-354B-13MS
- 3. Gate valve - motor operated - Limitorque SMB-00-10
- 4. 2-1/2 inch 2500# ANSI B. Inlet Piping Parameters
- 1. Valve is in the valve room approximately 20 feet from the pressurizer
- 2. There is a heated loop seal t
C. Actuation Transients
- 1. The valve is normally open I
V c Report W TELEWNE ENGNEstNG SERVCES Appendix A A-4 II. Results of Plant-Specific Performance Evaluations l A. Safety Valve Performance The Davis-Besse safety valve (Crosby 4M 1 6) was tested at the Crosby facility with stcam with satisfactory results (Reference 5). The test was originally done to determine if a 15 percent blowdown could be achieved. This was to prevent possible unstable valve operation if it were not moved to the top of the pressurizer. The test was successful and also proved the valve was satisfactory with a normal blowdown of approximately five percent and mounted at the pressure source such as on top of the pressurizer. The test used a prorate spring which is one with a load deflection ) rate proportional to the standard spring, since the test facility pressure was approximately 400 psig. The use of a prorate spring is standard practice at Crosby who has reports showing a 1305 psig set pressure prorate spring is a 2500 psig set pressure with the standard spring. The test justified the ring set positions used in the instructici manuals by proving they were the proper ones for the desired blowdown. The Crosby 4M 1 6 (2.991n2 1 orifice) was not tested in the EPRI test series, but a smaller 3K6 (1.838 in2 orifice) and a t;9:e 6M6 (3.6 in2 orifice) were tested (Reference 1). The 3K6 v3be ; st key parameters are similar to the 4M16 valve and theref're. . Sarison is valid (Reference 3). 1
W TELEDYNE N'_$*} Report ENGINEERING SERVICES h Appendix A A-5 o Valve Ring Setting. The spare 4M 16 valve from Davis-Besse was tested at Crosby with the specified ring settings. The valve operated in a stable manner. The EPRI tests proved the similar valves achieved proper flow rate and operated in a stable manner. o Discharge Piping Backpressure. The modification at Davis-Besse is without discharge piping and 75 psi rupture discs at tha valve discharge. The 4M1 6 valve test at Crosby operated in a stable manner with greater than 75 psi backpressure. 75 psi back pressure is small h compared to a usual safety valve installation with discharge piping and several hundred psi backpressure. Therefore, backpressure is not a factor, o Inlet Piping Pressure Drop. The valves are now mounted = on top of the pressurizer nozzle, which is a larger Jiameter than the value and therefore the inlet prrssure drop is not a factor. o Inlet Conditions. The inlet fluid conditions for Davis-Besse are covered by the EPRI tests (Reference 1 and Reference 4). The inlet conditiens for the Crosby 4M16 test by Crosby are not identical to Davis-Besse, but are justified using pressure parameter stuaies. g
l i c Report WNNE ENGNEERING SERVICES Appendix A A-6 B. Crosby Safety Valve Model 3K6 (Short Inlet Configuration EPRI Test) o Steam Test
- 1. Valve behaved in a stable manner for all steam tests.
- 2. The valve opened within +3 percent of the design set pressure on eight of the 11 steam tests and opened on all 11 tests.
- 3. Rated Dow was obtained at six percent accumulation on tests where it was measured.
I 4. Blowdown was at or exceeded five percent on all 11 steam tests. Performance is acceptable for the Davis- Besse application. o Transition Test. The valve opened during the high back-pressure steam to water transition test, but not within three percent of the valve design set pressure (-4 percent was achieved). The valve did have stable per-formance and an eight percent blowdown. o Water Tests. Two high back pressure water tests were performed at 5500F. The salve opened in both cases and was unstable in one case and stable in the second, With the Davis-Besse configuration there is essentially no back pressure after the rupture discs break which eliminates the high back pressure water possibility.
Technical Report TME l TR-5639-2 gg gg I Appendix A A-7 The fluid state is steam for all safety valve inlet conditions per the Plant Conditions Justif:;ation Report, l except for the feedwater line break where there is a l possible transition to subcooled water. ' C. Crosby Safety Valve Model 6M6 The Crosby 6M6 valve was not tested with the shcrt inlet con-figuration, but it was tested with the long inlet. The results of the non-loop seal steam test show stable operation. It can be concluded that a short inlet non-loop seal steam condition would show the same result. I D. Safety Valve Conclusions
- 1. It is concluded that the two Crosby 4M 6 1valves no.,
located on the pressurizer nozzle without loop seals or discharge pipes, will open and operate in a stable manner. Tests at Crosby and by EPRI show the present ring setting adjustments will meet or exceed the required flow rates.
- 2. T8:e backpressure is acceptable with the 75 psi rupture d!scs.
- 3. The valve may not be stable with subcooled water and high back pressure, but except for a conservative assumption of a feedwater line break, steam is the fluid. Also high back pressure has been eliminated because there is no discharge piping.
I
Technical Report TR-5639-2 h Appendix A A-8 l
- 4. The tested valves all opened within three percent of the set pressure and achieved rated flow within six percent accumulation. In all the tests done at Crosby the valve opened at set pressure il percent with three percent accumulation. The Davis-Besse technical specification calls for the valve to open at il percent of the rated set pressure. Therefore the valves will function per the technical specification requirements.
None of the tests exceeded 10 percent over pressure in the pressure vessel (maximum ASME Code allowable).
- 5. All blowdowns were five percent to 13 percent (ASME criteria is five percent). The maximum blowdown was with the 3K6 test with water. None of the pressures were low enough to initiate high pressure injection at Besse-Davis.
- 6. The 3X6 valve did not achieve rated flow in the high back pressure water lifts. One test was termiiated at 6.5 percent of flow and the second test 92 percent of flow was achieved, but the valve was not stable. Subcooled water is only a possible factor in the feedwater line break and the high back pressure is not a factor for the Davis-Besse application.
- 7. Overall the perfc 1 nance of the Crosby 4M1 6 is acceptable for the Davis-Besse plant application.
Tec Report "A'MNE ENGNEERING SERVCES k Appendix A A-9 E. Relief Valve Performance The Davis-Besse valve was not tested in the Marshall Steam Station, Wyle test. However, a similar valve with a 1-3/8 bore, versus the Davis-Besse 1-1/2 inch bore, was tested. Reference 2 states "from a functional standpoint the behavior of the two valves is essentially the same." o Marshall Steam Station Test. After an improperly machined part was corrected the valve fully opened and closed on demand with no bellows leakage. o Wyle Phase II. The valve fully opened and fully closed on demand during the six tests. However, the bellows 4 were leaking at the end of testing. The bellows leakage does not have an impact on valva operation. o Wyle Phase III. The valve fully opened and fully closed on demand during 10 tests. However, the bellows were leaking at the end of testing. The bellows leakage does not have an impact 04 valve operation. The test data shows a maximum steam flow of 158K lbm/ hour. F. Power Operated Relief Valve Conclusion A Crosby Model HPV-SN with a 1-3/8 inch bore will open and close on demand and meet the requirements of the Davis-Besse plant. G. Black Valve Performance The Davis-Besse valve was not tested in the Marshall Steam Station by EPRI. However, a similar valve made by the same manufacturer (Velan) was tested.
Report "MTELEDYNE ENGREstNG SERVICES I Appendix A A-10 The valve tested vos a Velan 3-inch B10-3054B-13MS with a Limitorque SB-00-15 operato. . The Reference 6 test report shows the valve opened and closed on demand for all tests. The Davis-Besse valve is a Velan 2-1/2 inch B9-3548-13MS with a Limitorque SB-00-10 operator. The valves are similar enough to make a direct comparison. H. Block Valve Conclusion A Valen B9-354B-13MS block valve will open anu close on demand and meet the requirements of the Davis-Besse plant. III. Inlet and Discharge Piping Adequacy l Teledyne Engineering Services performed the modification analysis for the PORV and SRV piping and supports. This is an appendix to the piping and support analysis report. Teledyne used the RELAP 5 MOD 1 Cycle 14 computer program with the EPRI suggested guide lines to perform the fluid analysis for the final modification. P
b Report 1 %' M E ENGNEstNG SERVCES ) Appendix A A-11 l 1 IV. References
- 1. Safety and Relief Valve Test Reports, EPRI Interim Report, April 1982.
- 2. Marshall PORV Interim Test Data Report, EPRI NP-2144-LD, February 1982.
- 3. PWR Safety and Relief Valve Test Program Justification Report, EPRI NP-2292-LD, March 1982 Interim Report.
- 4. Plant Conditions Justification Report, EPRI NP-2352-LD, April 1982
) for B&W 177-FA and 205-FA Plants.
- 5. Crosby Valve and Gage Company, Test Report 3992, September 29, 1982; Performance Test Program for Increased Blowdown on Crosby 4M,6 HB-BP-86 Pressurizer Relief Valve.
- 6. EPRI-Marshall Electric Motor-0perated Valve (Block Valve) Interim Test Data Report, EPRI NP-2514-LD, July 1982.
I
i Technical Report TME TR-5639-2 N MES Table 1.1 Boundin Safety Valve Inlet Conditions Resulting from FSAR Reload Events for 177-FA Plants Assumed PSV Maximum p Opening Possible Pressurizer Rate (psi /s) Setpoints Fluid State Pressure Limiting Events (psig) on Opening (psig) Max Min Rod Ejection at 2575 Steam 2662 175 N/A HZP h t
T WTE EDGE Technical Report NSERVICES TR-5639-2 Table 1.2 l Bounding Safety Operation of HPIValve Inlet Conditions for Davis-Besse Resulting)from (177-FA Plant Extended Surge Line Flow when PSV Assumed PSV Maximum Max / Min is Passing Liquid (1b/ min) Opening Possible Pressurizer Pressurizer Setpoints fluid Sta';e Pressure Liquid Temp At At At Limiting Events (psig) on OpeningLa) (psig) (F) 400F 602F 640F 1 177-FA Plants ! Steam Line Break 2500 Steam 2500 602/400 3295 6680 N/A l FW Line Break 2500 Steam 2500 640/602(b) N/A 5435 7005 (a) Initial opening of valve will be on steam. Subsequent openings could possibly be on sub-cooled liquid. j (b)Without thermal mixing of the surge line liquid with the 650F liquid normally in the pressur-izer, the pressurizer safety valves could open on 650F liquid.
Technical Report W M NE TR-5639-2 ENGNEERING SERVICES l I Table 2.1 Davis-Besse Bounding PORV Inlet Conditions Resulting from FSAR/ Reload Events i l i Maximum Possible Pressurizer Maximum / Minimum Fluid State Pressure Liquid Temperature Limiting Events on Opening (psig) at Valve Inlet Rod Ejection at Steam 2662 N/A HZP k i
W WTELEDGE Technical Report mg TR-5639-2 i Table 2.2 Bounding Safety Valve Inlet Conditions Resulting from Extended Operation of HPI for Davis-Besse (177-FA Plant) Assumed Maximum Minimum Relief Valve Maximum Liquid Temp Liquid Temp Opening Possible Pressurizer at Valve at Valve l Setpoints Fluid State Pressure Inlet Inlet Limiting Events (psig) on Openingta) (psig) (F) (F) Davis-Besse Plant l Steam Line Break 2450 Steam 2500(h) 602 400 FW Line Break 2450 Steam 2500(c) 640(d) 602 a) Initial opening on steam with possible transition to subcooled water. Subsequent openings possibly on subcooled liquid. (b)Up to the time of pressurizer fill, the steam relief capacity of PORV can maintain pressur-izer pressure below the PSV lift pressure. When water relief starts, pressurizer pressure would increase to PSV lift setpoint. (c) Surge flow exceeds the PORV capacity when HPI and system heat-up are considered. Valve inlet conditions would be those specified at the PSV lift setpoint of 2500 psig. (d)Without thermal mixing of the surge line liquid with the 650F liquid normally in the pres-surizer the PORV could open on 650F liquid. _ _ _ _ _ _ _ _ _ __-}}