Rev 1 to Improved Dynamic Vacuum Breaker Valve Response for Peach BottomML20072H162 |
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Peach Bottom ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
09/30/1982 |
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From: |
CONTINUUM DYNAMICS, INC. |
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To: |
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Shared Package |
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ML20072H155 |
List: |
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References |
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82-10, 82-10-R01, 82-10-R1, NUDOCS 8303290305 |
Download: ML20072H162 (21) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20199J6981997-11-11011 November 1997 Rev 2 to 10CFR50.59 Review for Jet Pump Thermal Sleeve Cracking ML20202H1231997-09-30030 September 1997 Small Project Joint Permit Application & Attachments for PECO Energy Co,Peach Bottom Atomic Power Station,Rock Run Creek Low Flow Crossing, to Satisfy PA Dept of Environ Protection & Us Army Corps of Engineers ML20129E8711996-09-26026 September 1996 Rev 0 to 10CFR50.59 Review for Ncr Pb 96-03414,Core Spray T-Box Cracks for Peach Bottom Atomic Power Station,Unit 2 ML20117E6251996-05-31031 May 1996 Seismic Safe Shutdown Equipment List for PBAPS Units 2 & 3 ML20117E6321996-05-31031 May 1996 USI A-46 Relay Evaluation Rept for PBAPS Units 2 & 3 ML20117E6351996-05-31031 May 1996 Seismic Evaluation Rept for Pbaps ML20129A4511996-01-11011 January 1996 Core Spray Sparger Downcomer Modification ML20129A4731995-12-11011 December 1995 Fabrication of Core Spray Line Downcomer Clamp ML20098B1211995-09-30030 September 1995 Residual Stress Analysis of Peach Bottom Unit 3 Core Spray Pipe to Sleeve Fillet Weld ML20098B1141995-09-30030 September 1995 Evaluation of Peach Bottom Unit 3 Core Spray Line ML20092M8921995-09-30030 September 1995 Shroud Vertical Team Weld Evaluation ML20092J8151995-09-15015 September 1995 Core Spray Line Tee-Box Analysis Rept for Peach Bottom Atomic Power Station Unit 3 ML20094H0521995-06-30030 June 1995 Pyrolysis Gas Chromatography Analysis of 21 Thermo-Lag Fire Barrier Samples ML20092K9871995-06-13013 June 1995 Rev 3 to Shroud Stabilizer Hardware ML20083K6611995-04-26026 April 1995 Rev a to Upgraded Eals ML20077M0951995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for ECCS Actuation Instrumentation for Pbaps,Units 2 & 3 ML20077M0861995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for RPS for PBAPS, Units 2 & 3 ML20073J7501994-09-30030 September 1994 Shroud Mechnical Repair Program,Peach Bottom Shroud & Shroud Repair Hardware Stress Analysis ML20079S0911994-09-29029 September 1994 Rev 0 to Application of Screening Criteria ML20073J7411994-09-24024 September 1994 Rev 0 to Stress Rept 25A5607, Shroud Stabilizers ML20072P5791994-08-26026 August 1994 Power System Harmonic Study for Peach Bottom Nuclear Power Plant, Final Rept ML20072L9631993-12-13013 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit-2 Shroud ML20064K4291993-12-0303 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit 3 Shroud Indications ML20059L1391993-11-30030 November 1993 Core Spray Crack Analysis for Peach Bottom Unit 3 ML20059G0901993-10-27027 October 1993 Evaluation & Screening Criteria for Peach Bottom Unit-3 Shroud Indications ML20149G0401993-05-30030 May 1993 Fatigue Evaluation of Peach Bottom II & III Reactor Vessels ML20073D0221991-04-30030 April 1991 Full Structural Weld Overlay Design for Peach Bottom Unit 2 RWCU Weld 12-I-1D ML20073E5881991-04-30030 April 1991 Revised Station Blackout Analysis ML20055J3231990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3291990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3271990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML18095A3791990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co. ML20044H3281990-02-23023 February 1990 Rev a to 30-Month Stability Spec for Rosemount Models 1152, 1153 & 1154 Pressure Transmitters. ML20247N3951989-05-16016 May 1989 Methods for Performing BWR Reload Safety Evaluations ML20236A8501989-01-31031 January 1989 Voltage Regulation Study ML20236A8351989-01-31031 January 1989 Rev 1 to Peach Bottom Atomic Power Station Units 2 & 3, Verification of Calculated Auxiliary Distribution Sys Voltages by Test ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20151M5501988-07-15015 July 1988 Security Problem Root Cause Assessment ML20147A7971988-02-23023 February 1988 Root Cause Investigation of Shutdown Cooling Isolations Peach Bottom Atomic Power Station ML20148H1211988-01-15015 January 1988 Rev 0 to Peach Bottom Atomic Power Station,Units 2 & 3, Response to IE Bulletin 85-003 ML20149D6981988-01-13013 January 1988 Methods for Performing BWR Steady-State Reactor Physics Analyses ML20196K0311987-12-31031 December 1987 1987 Annual Plant Mod Rept,Per 10CFR50.59 ML20236V3311987-11-20020 November 1987 SAR for Peach Bottom Atomic Power Station Spds ML20236J7141987-10-28028 October 1987 Commitment to Exellence Action Plan Status Rept ML20235H5601987-09-0909 September 1987 Methods for Performing BWR Sys Transient Analysis ML20236D1271987-09-0303 September 1987 Rev 0 to Safety Evaluation for Mod 2085,Peach Bottom Unit 3 ML20236K6081987-07-15015 July 1987 Rev 1 to Evaluation of Insulated Blind Barrel Splices on Dual Voltage Motors in Limitorque Actuators 1998-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
[Table view] |
Text
. .
,- - C.D.~I. TECH NOTE NO. 82-10
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IMPROVED DYNAMIC VACUUM BREAKER VALVE RESPONSE FOR PEACH BOTTOM Revision 1 Prepared by CONTINUUM DYNAMICS, INC.
for GENERAL ELECTRIC COMPANY September 1982 l
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l 8303290305 830325 PDR ADOCK 05000277 P PDR
. C.D.I. TECH NOTE NO. 82-10 l
IMPROVED DYNAMIC VACulN BREAKER VALVE RESPONSE FOR PEACH BOTTOM .
REVISION 1 PREPARED FOR GENERAL ELECTRIC COMPANY ,
175 CURTNER AVENUE
~
SAN JOSE, CALIFORNIA 95125 UNDER PURCHASE ORDER NO. 205-XJ102 BY _
CONTINUUM DYNAMICS, INC.
P.O. B0X 3073 PRINCETON, NEW JERSEY 08540 APPROVED BY b^_xb Lx_
ALAN J. BILANIN PRINCIPAL INVESTIGATOR SEPTEMBER, 1982
DISCLAIMER OF RESPONSIBILITY Neither the General Electric Company nor any of the contributors to this document makes any warranty or representation (express or implied) with respect to the accuracy, completeness, or usefulness of the information contained in this document or that the use of such information may not infringe privately owned rights; nor do they assume any responsibility for liability or damage of any ,
l kind which may result from the use of any of the information contained in this document.
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SUMMARY
1mproved' plant-unique expected and design vacuum breaker impact velocities have been calculated for the Peach Bottom plant, i The valve displacement time history was predicted using -
a valve dynamic model which takes credit for the reduction of
- hydrodynamic torque across the vacuum breaker as a consequence of valve actuation. As a result of this study the vacuum breakers in Peach Bottom are predicted to not actuate during the chugging transient.
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Revision 1 1
SLNMARY OF THE METHODOLOGY USED TO DEFINE PLANT-UNIQUE WETWELL TO DRYWELL MARK I VACULM BREAKER FORCING FUNCTIONS FROM FSTF DATA During the Mark I FSTF test series, wetwell to drywell vacuum breaker actuation was observed during the chugging phase of steam blowdowns. As a result of this observation, a metho-dology was developed which can be used to define the loading function acting on a vacuum breaker during chugging (Ref. 1).
The methodology developed uses FSTF pressure time history data and adjusts the vent system and wetwell pressures to account for plant-unique geometry. For plants with internal vacuum breakers, the most critical parameter controlling the magnitude of the vacuum breaker forcing function is the drywell volume per vent area. Vacuum breaker forcing functions are specified as a time history of the differential pressure across the valve disc.
The steps taken in the development of the plant-unique forcing function model are shown in Figure 1. Step 1 involves the development of analytic dynamic models for the unsteady motion in the steam vent system (see Figure 2), at the steam l
l water interface (see Figure 3) and in the suppression pool (see Figure 4) assuming that the condensation rate at the steam water l
interface is known. The dynamics in the vent system are assumed to be governed by one-dimensional acous tic theory and jump con-i ditions across the steam water interface are the Rankine-Hugoniot relations. A one-dimensional model of the suppression pool was developed which accounts for compression of the wetwell airspace 2
l l
l STEP ;
Develop a dynamic model of the vent system,l steam water inter-
- I face and poo slosh with the l condensation raic of the inter- -
f ace unknown.
o 2 Use measured ~drywell pressure to determine the condensation rate.
U With the condensation rate 3 predict unsteady determined, pressures a t other vent locations to validate the model.
o Use the condensation source of the vent exit to drive dynamic 4 models of Mark I plants to determine unique vacuum l
breaker forcing functions.
Figure 1. Steps in determining plant unique vacuum j breaker forcing functions.
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10 " ~ D'II External Vacuum ___
Breoker Piping
_9_ _ - Jet Deflector Plate
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Main Vent 1 ll I--
2 . . ... . .... ....
7 Wetwell l 6 l 5 l 4 12 Airspace -- -- --
3 2 I W ~ a -_ .
Downcomers l
( Figure 2. Schematic model of the vent system depicted by 12 dynamic components.
i Steam Side
_ _ _ _ _ _ " , _ _ ~_ _ _ _ Steam Water _ _ _
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I I"W dh, Water Side dt Figure 3. Details of the steam water interface.
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p Pool
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Figure 4. Details of the pool dynamic model around each downcomer.
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with the lowering of the steam water interface in the-downcomer.
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Assuming a unit condensation source in frequency space, a trans-fer function is then developed between the condensation source and the pressure in the drywell. Once this transfer function has been established, the condensation time history at the steam ,
water interface can be extracted from a measured drywell pressure tLme history which is step 2 in Figure 1.
The model developed permits validation (step 3 in Figure 1) provided that an additional pressure time history, at another location in the suppression system, is available. With the con-densation rate determined at the vent exit using a pressure time history from the drywell, the pressure history in the ring header was predicted and compared against measured data. The comparison was very favorable (Ref. 1).
In order to predict plant-unique vacuum breaker forcing functions, the key assumption is made that the condensation rate is a facility independent quantity. This assumption is supported by the observation that the condensation rate is fixed by local conditions at the vent exit; i.e., steam mass flow rate, non-condensibles and thenmodynamic conditions, and that these local l
conditions vary slightly between plants. Using this condensation rate, the forcing function ptrameters given in Table 1 were used to compute expected and design loads across the Peach Bottom plant vacuum breakers (Ref. 1).
(7
TABLE _1 Forcing Function Parameters for Peach Bottom
~
Value Used Parameter In Computation
- Vent / pool area ratio 0.045 Drywell volume / main vent area ratio ** 532.87 ft Main vent area /downcomer area 0.99 Main vent length 37.32 ft Header area /downcomer area 1.47 Header length 15.0 ft Downcomer area 3.01 ft2 Downcomer length 10.8 ft Submergence head 4.0 ft water
- The modeled plant is FSTF.
< ** Group 2 value used even though Peach Bottom is 549.75 ft. .
4 8
SUMMARY
OF THE METHODOLOGY OF THE MARK I/ MARK II VACUUM BREAKER VALVE MODEL (INCLUDING HYDRODYNAMIC EFFECTS)
During the Mark I shakedown tests, the vacuum breaker displacement time history was recorded. Use of a simple single-degree-of-freedom valve model resulted in large overly conserva-tive predictions of the resulting valve dynamics. In an effort to reduce the conservatism in this test' series, and additionally to relax the prediction of valve impact velocities in expected Mark II downcomer-mounted applications during chugging, a metho-dology was developed which uses the differential forcing function across the vacuum breaker (computed by the vent dynamic model) but includes the effect of torque alleiiation as a consequence
~
of valve flow (Ref. 2). With the valve in an open position, the pressure difference across the valve is not the pressure dif-ference felt by the valve disc, because of flow effects across the open valve disc. This reduction in hydrodynamic torque is estimated by the following:
- 1. A linear analysis of the pressure field on either side of the closed valve permits the solution for pressure 4 and velocity in the vicinity of the valve disc without flow.
- 2. The flow effect is modeled as a mathematical source /
sink around the circumference of the open valve.
- 3. The local pressure and velocity fields permit evaluation of the strength of the flow source / sink.
9
- 4. The response of the valve to both flow and up and downstream pressure transients is computed as a super-position of these influences. In all cases flow tends to reduce the pressure load felt by the disc.
The 18" GPE valve characteristics for Peach Bottom are shown in Table 2.
i 10
TABLE 2 Vacuum Breaker Characteristics for Peach Botton Vacuum breaker type 18" GPE Internal System moment of inertia (1b-in-s 2) 20.08 System moment arm (in) 10.854 Disc moment arm (in) 11.468 System weight (1b) 49.84 2
Disc area (in ) 375.83 System rest angle (rad) . 0.0 Seat angle (rad) 0.0698 Body angle (rad) 1.391 Seat coefficient estitution 0.6 Body coefficient restitution 0.6 Magnetic latch set pressure (psi) 0.5 l Revision 1 11
RESULTS The. pressure time history shown in Figure 5 was used to drive a valve dynamic model with/without flow for the GPE valve with characteristics given in Table 2. Table 3 summar-izes the valve impact data for the expected response. No -
valve actuation is predicted for this valve during the chugging transient.
1 Revision 1 12
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TABLE 3 (REVISION 1)
Vacuum Breaker Valve Response for Peach Bottom Maximum Impact Number Maximum Opening Velocity of Angle -
(rad /sec) Impacts (2) (rad)(3)
Expected Loading Function (1)
No flow effects 0.0 0 0.0 Flow effects 0.0 0 0.0 (1) Submergence head is taken as 1.73 psi.
Vacuum breaker assumed to be mounted at the main vent-header junction.
(2) Seat impacts above 1 rad /sec.
(3) The v'alve does not actuate f
I Revision 1 17 l
t i
l REFERENCES
- 1. " Mark I Vacuum Breaker Dynamic Load Specification, Revision 3," C.D.I. Report No. 80-4, February 1980,
- 2. " Mark 1 Vacuum Breaker Improved Valve Dynamic Model -
Model Development and Validation," C.D.I. Tech Note No. 82-31, August 1982.
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