Similar Documents at Salem |
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5171999-08-25025 August 1999
Marked-up Tech Spec Pages Deleting Footnotes That Were Added as One Time Changes & Proposing Change Identified Subsequent to 971114 Submittal That Corrects Error Issued in Amend 69 for Salem Unit 2
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A4961999-08-23023 August 1999
Proposed Tech Specs,Modifying 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys.
ML18107A4671999-07-29029 July 1999
Proposed Tech Specs Replacing Surveillance 4.6.1.1a with Appropriate NUREG-1431 Requirements
ML18107A4601999-07-23023 July 1999
Proposed Tech Specs Pages Changing TS Surveillance Requirement 4.8.1.1.2 D 7 by Removing Restriction to Perform Test Every 18 Months During Shutdown
ML18107A4241999-07-0202 July 1999
Proposed Tech Specs,Relocating TS 3/4.3.4 Lco,Surveillance Requirements & Bases from TS to UFSAR
ML18107A3811999-06-10010 June 1999
Proposed Tech Specs 3/4.6.1, Containment Integrity, Clarifying When Verification of Primary Containment Integrity May Be Performed by Administrative Means
ML18107A3601999-06-0404 June 1999
Non-proprietary Tech Specs Pages Re Transfer of PSEG Ownership Interests & Licensed Operating Authorities to New, Affiliated Nuclear Generating Company,Pseg Nuclear LLC
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML18107A2131999-04-14014 April 1999
Proposed Tech Specs 3/4.9.12, Fhavs, Revised to Ensure Consistency Between TS Requirements for Fhavs & Sys Design Basis,As Well Better Alignment to Bases Provided in NUREG-1431
ML18106B1591999-03-31031 March 1999
Proposed Tech Specs Allowing Plant Operation to Continue to Thirteenth Refueling Outage (1R13),currently Scheduled to Begin on 990918
ML18106B0801999-02-22022 February 1999
Proposed Tech Specs Re CR Emergency Air Conditioning Sys
ML18106B0641999-02-0808 February 1999
Proposed Tech Spec Pages,Modifying ECCS Subsystems Surveillance 4.5.3.2.b by Adding Option of Providing Necessary Isolation Function When Testing
ML18106B0611999-02-0808 February 1999
Proposed Tech Specs SR 4.8.1.1.2.f Re Hot Restart & Definition of Standby Conditions.
ML18106B0531999-02-0202 February 1999
Proposed Tech Specs 5.6.1.1,revising Max Permissible Enrichment of Stored New Fuel
ML18106B0431999-01-19019 January 1999
Proposed Tech Specs Bases Section 3/4.1.2 Re Boration Sys
ML18106B0241999-01-15015 January 1999
Proposed Tech Specs Re Deferral of Surveillance Requirements for Salem Generating Station,Unit 1
ML18106A9231998-10-12012 October 1998
Proposed Tech Specs Re Inserts & Marked Up Pages for LCR S98-03
ML18106A9181998-10-12012 October 1998
Proposed Tech Specs Re one-time Changes to Certain Unit 2 TS SR for Fuel Cycle 10
ML18106A8941998-09-29029 September 1998
Proposed Tech Specs Section 3/4.9.2,modified to Permit Use of Equivalent Methods to Obtain Containment Closure During Refueling Operations for Containment Equipment Hatch
ML18106A8781998-09-17017 September 1998
Proposed Tech Specs Modifying 3/4.8.2.2,3/4.8.2.4 & 3/4.8.2.6 to Address Movement of Irradiated Fuel & Deleting LCO Re Requirement to Establish Containment Integrity
ML18106A8371998-08-12012 August 1998
Proposed Tech Specs Modifying Allowed Continued Operation W/Inoperable Air Lock Door Provided That Operable Door Is Closed & Unlocked & Making Requirements for Inoperable Air Lock Door
ML18106A7931998-07-30030 July 1998
Proposed Tech Specs,Revising Acceptance Criteria for CR Emergency Air Conditioning Sys from Maintaining CR at 1/8-inch Positive Pressure W/Respect to Adjacent Areas to Stated Phrase
ML18106A6961998-07-0707 July 1998
Proposed Tech Specs Section 4.2.1 Re Aquatic Monitoring of App B for Environ Protection Plan
ML18106A6631998-06-17017 June 1998
Proposed Revised Tech Specs Bases Pages 3/4.1.3,3/4.1.2, 3/4.5.5 & 3/4.9.1,ensuring Acceptable Power Distribution Limits Are Maintained,Providing Operational Flexibility & Clarifying Statements
ML20216B0641998-05-0101 May 1998
Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page
ML18106A5571998-04-16016 April 1998
Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents
ML20239A1251998-03-31031 March 1998
Rev 11 to Salem Nuclear Generating Station Odcm
ML18106A4241998-03-26026 March 1998
Proposed Tech Specs Incorporating Note at Bottom of Salem Unit 2 T3/4.8.2 Into Salem 1 TS & Adding Asterisks to Word Inverters.
ML18106A4291998-03-26026 March 1998
Proposed Tech Specs,Changing Applicability Statement from Mode 3 to Modes 1 & 2
ML18106A3921998-03-13013 March 1998
Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency.
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML18106A3221998-02-18018 February 1998
Marked-up TS Pages for Section 4.2.1 of App B
ML18106A3091998-02-0202 February 1998
Revised TS Bases Pages for Specs 3/4.3.3.1,radiation Monitoring instrumentation,3/4.3.3.8,radioactive Liquid Effluent Monitoring Instrumentation & 3/4.3.3.9,radioactive Gaseous Effluent Monitoring Instrumentation
ML18106A2541998-01-0808 January 1998
Proposed Tech Specs Pages,Adding Asterisk to Word Operable in LCO & Associated Note at Bottom of Page
ML18106A2141997-12-15015 December 1997
Proposed Tech Specs Pages,Revising TS to Adopt Option B to 10CFR50,App J,For Type B & C Testing & Modify Existing TS Wording for Previous Adoption of Option B on Type a Testing
ML18106A1961997-12-11011 December 1997
Proposed Tech Specs Re one-time Exemption to Allow Containment Purging in Modes 3 & 4
ML18102B6791997-11-14014 November 1997
Proposed Tech Specs Providing Surveillance Requirements to Codify Existing Procedural Commitments for SW Accumulator Vessels
ML18102B6751997-11-14014 November 1997
Proposed Tech Specs Re Administrative & Editorial Corrections
ML18102B6591997-11-0404 November 1997
Proposed Tech Specs,Revising Surveillance Requirement 4.6.2.1.b to Verify That on Recirculation Flow,Containment Spray Pumps Develop Differential Pressure of Greater than or Equal to 204 Psid
ML18102B6631997-11-0404 November 1997
Proposed Tech Specs,Deleting 4.8.1.1.2.d.1,which Calls for Diesels to Be Subjected to Insp Based on Vendor Recommendations at Least Once Per 18 Months During Shutdown
ML18102B6431997-10-29029 October 1997
Proposed Tech Specs Revising SR 4.8.1.1.2.d.2 Proposed in 960925 Request to Change EDG Voltage & Frequency Limits as Result of Updated EDG Load Calculations & Ambiguity in Testing Methodology for EDG Start Timing
ML18102B6391997-10-29029 October 1997
Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10
ML18102B6491997-10-24024 October 1997
Proposed Tech Specs Pages,Modifying TS 3/4.7.7, Auxiliary Building Exhaust Air Filtration Sys & Bases
ML18102B6461997-10-24024 October 1997
Proposed Tech Specs Revising Containment Hydrogen Analyzer SRs of TS 4.6.4.1
ML18102B6321997-10-21021 October 1997
Proposed Tech Specs,Extending Applicability of Power Range Neutron Flux TS Trip to Require Operability & Surveillance Testing in Mode 3,when Reactor Trip Sys Breakers Are in Closed Position
ML18102B6201997-10-14014 October 1997
Proposed Tech Specs Modifying Pressure Isolation Valves LCO, LCO Action Statement,Surveillance Requirement & Table 4.4-4 to Be Consistent W/Salem Unit 2
1999-09-10
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML18107A5291999-09-10010 September 1999
Revised Event Classification Guide,Including Rev 18 to Table of Contents,Rev 10 to Attachments 6 & 7 & Rev 11 to Attachment 9
ML20211Q8771999-08-27027 August 1999
Rev 0 to Inservice Testing Manual for Pumps & Valves Program
ML18107A5121999-08-23023 August 1999
Procedure 71151, Performance Indicator Verification.
ML18107A5091999-08-23023 August 1999
Attachment 21 to Procedure 71111, Safety Sys Design & Performance Capability.
ML18107A2961999-05-12012 May 1999
Revised Event Classification Guide,Including Rev 16 to Table of Contents,Rev 8 to Attachment 6,rev 8 to Attachment 7 & Rev 9 to Attachment 9
ML20216B0641998-05-0101 May 1998
Rev 1 to ECG-ATT 14, Four Hour Rept - NRC Operations & Rev 7 to ECG-HECG-TOC, Hope Creek Event Classification Guide Table of Contents/Signature Page
ML18106A5571998-04-16016 April 1998
Rev 21 to EOP-CFST-1, Shutdown Margin Status Tree & Rev 10 to Table of Contents
ML20239A1251998-03-31031 March 1998
Rev 11 to Salem Nuclear Generating Station Odcm
ML18106A3921998-03-13013 March 1998
Rev 9 to ECG-SECG-TOC & Rev 2 to ECG-ATT.04, General Emergency.
ML18106A8281998-03-0404 March 1998
Rev 1 to Reactivity Manipulations Documentation Guide.
ML18102B6681997-10-0101 October 1997
Rev 8 to Inservice Testing Manual for Pumps & Valves Program.
ML18106A8291997-09-0404 September 1997
Rev 2 to Reactivity Manipulations Documentation Guide. Page to Training Manual NC.TQ-TP.ZZ-0302,encl
ML18102A7941997-01-21021 January 1997
Event Classification Guide,Technical Basis, for Hope Creek Generating Station & Salem
ML18102A7931997-01-21021 January 1997
Event Classification Guide,Technical Basis, Salem Generating Station
ML18102A6661996-11-19019 November 1996
Rev 2 to Pse&G Simulation Facility Certification Program.
ML20115B7791996-07-0303 July 1996
Final Draft, Hope Creek Event Classification Guide, Sections 1-9
ML18101B1141995-11-14014 November 1995
Revised Salem Generating Station Event Classification Guide, Including Rev 46 to Table of Contents,Rev 37 to Attachments Signature Page,Rev 26 to Attachment 6,Rev 25 to Attachment 7 & Rev 24 to Attachment 9
ML20091M9911995-10-15015 October 1995
Event Classification Guide HCGS, Including Revised Eals, Technical Basis Document & NUMARC EAL-to-Hope Creek Comparison Summary
ML18101A6911995-05-31031 May 1995
Nbu Issue Mgt & Prioritized Action Plan, Dtd May 1995
ML18101A7711995-05-11011 May 1995
Rev 1A to Vol a of Salem Generating Station Unit 2 Second 10-Yr Insp Interval ISI Program Plan.
ML20134K0831995-02-27027 February 1995
Pse&G/Nuclear Business Unit Organizational Effectiveness Assessment Plan,
ML18101A6751995-02-16016 February 1995
Rev 11 to EOP 1-EOP-TRIP-1, Reactor Trip or Safety Injection.
ML18101A6761995-02-16016 February 1995
Rev 12 to EOP 1-EOP-TRIP-2, Reactor Trip Response.
ML18101A5381995-01-27027 January 1995
Revised Salem Generating Station Event Classification Guide.
ML18101A2111994-08-17017 August 1994
Revised Salem Event Classification Guide.
ML18101A6771994-07-11011 July 1994
Rev 10 to EOP 1-EOP-TRIP-3, Safety Injection Termination.
ML20147B1601994-04-23023 April 1994
Rev 3 to S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A8081994-01-0707 January 1994
Rev 30 to Salem Generating Station Event Classification Guide.
ML20147B1491993-11-0202 November 1993
Rev 2 to Procedure S1.OP-SO.CW-0001(Z), Circulating Water Pump Operation
ML18100A4201993-06-15015 June 1993
Justification for Sgs Units 1 & 2 Restart & Operation Rod Control Sys Failures.
ML18100A3771993-05-0505 May 1993
Rev 27 to Salem Generating Station Event Classification Guide.
ML18100A3661993-04-27027 April 1993
Rev 8 to Section 18 to Event Classification Guide, Correcting Typo on Pages 3 & 5 of 6
ML20147B1171993-04-13013 April 1993
Rev 1 to Procedure NC.NA-AP.ZZ-0015(Q), Safety Tagging Program
ML18096B3251993-02-26026 February 1993
Integrated Scheduling Program.
ML18096B2911993-02-10010 February 1993
Revised Event Classification Guide,Including Rev 25 to Table of Contents,Rev 14 to Attachment 6,Rev 13 to Attachment 7, Rev 8 to Attachment 8,Rev 13 to Attachment 9,Rev 3 to Section 10,Rev 4 to Section 17 & Rev 7 to Section 18
ML20147B1021993-01-21021 January 1993
Rev 5 to Procedure NC.NA-AP.ZZ-0009(Q), Work Control Process
ML20135B6521992-12-29029 December 1992
Rev 0 to Loss of Overhead Annunciator Sys
ML20147B1371992-12-22022 December 1992
Rev to Procedure SC.RP-TI.ZZ-0209(Q), Release of Items from Rca
ML20147B2051992-09-21021 September 1992
Rove Time Keeping Procedure
ML18096A9601992-08-28028 August 1992
Electrical Distribution Sys Functional Insp (Edsfi) Methodology & Plan.
ML18100A3151992-07-28028 July 1992
Rev 1 to Process Computer Maint & Mod Control Program.
ML18096B3191992-07-17017 July 1992
Rev 8 to Salem Nuclear Generating Station Odcm.
ML20147B1691992-05-0707 May 1992
Rev 1 to Procedure NC.NA-AP.ZZ-0013(Q), Control of Temporary Modifications
ML18096A6791992-04-30030 April 1992
Vols A-D of Salem Generating Station Unit 2 Inservice Insp Program (Second Insp Interval) Long-Term Plan.
ML18096A4421992-01-15015 January 1992
Rev 17 to Salem Generating Station Event Classification Guide
ML18096A3211991-10-0404 October 1991
Rev 13 to Event Classification Guide,Including Table of Contents,Section Signature Pages,Spill/Discharge Notification Form & Related Pages
ML18096A1431991-06-28028 June 1991
Rev 12 to Salem Generating Station Event Classification Guide.
ML18095A9661991-05-30030 May 1991
Artificial Island Salem Event Classification Guide, Rev 11
ML18096A1191991-05-28028 May 1991
Rev 2 to NFU-0039, Salem Reactor Physics Methods.
ML18095A9391991-05-16016 May 1991
Revised Replacement Pages to Facility Inservice Testing Program
1999-09-10
[Table view] |
Text
~~*~-.-. *~:___ - - . -*-*--*-* .. ***-*-*- *- ... -SALEM GENERATING STATION-
.. - ' e PROCEDURE APPROVAL cov&HEET Procedure Number TITLE REACTOR VESSEL HEAD VENT OPERATION REMARKS : LAST OTSC INCORPORATED NEW PROCEDURE OPERATING Er.-l7INEER STA. M:;R.
REV. ~UffiOR SRO REVIEW QA REVIEW APPROVAL SORC MEEl'ING NO. APPROVAL/DATE 0 IF.Kenned~ -.. NA 1 8201110437 811230 l
- 1. PDR ADOCK 05000272 . I
' :P .. 1PDEt, .;:_ __ *,
1.0 PURPOSE 1.1 This instruction provides the steps required to remove gases from the reactor vessel head by operation of the Reactor Vessel Head Vent during Accident and Transient conditions.
CAUTION: This venting instruction should not be.used as the primary means to mitigate an Inadequate Core Cooling event.
CAUTION: This venting instruction assumes that the reactor containment conditions are near normal.
2.0 INITIAL CONDITIONS 2.1 Abnormal reactor coolant system conditions such as reactor vessel level deviation from normal as indicated by the .
I Rv.LIS or large variations in pressurizer level during normal
- I charging or spraying operations.
2.2 The core exit thermocouples are equal to or greater than the RCS saturation temperature.
2.3 Plant events have occurred (such as accumulator tank discharge.
rapid RCS cooldown, or core uncovery eventsl that may result in the presence of a gaseous void in the Reactor Vesse-1 Head.
2.4 Appendix A has been performed if desired.
3.0 IMMEDIATE ACTIONS 3.1 None 4.0 SUBSEQUENT ACTIONS CAUTION: Do not trip any running *or start any*non-operating Reactor Coolant Pumps during the performance of the following actions.
~: If the Safety Injection System is in operation, then the actions of steps marked by an asterisk will not be applicable.
Rev. 0
4.1 Termina*a' changes to the React.A.ant system. that may be in progress and bring the RCS to as close to a steady-state condition as possible.
CAUTION: Increased charging flow, with condensible gases in the RCS may result in a decreasing pressurizer level, since the increase in pressure will collapse the bubble.
- 4.2 Attempt to recombine any condensible gases by increasing RCS pressure through the use of the pressurizer *backup heaters and increased charging flow. ~f this step is successful in condensing the gas volume in the vessel head, then return to the appropriate Emergency Instruction.
4.2.1 If pressurizer level decreases to less than 20%
of span, then attempt to restore level by continuing the charging flow or manually starting Safety Injection Pumps. If level cannot be restored, then manually initiate Safety Injection and proceed to EI I-4.0, Safety Injection Initiation.
4.3 In preparation for venting the Reactor Vessel Head, isolate the containment purge and exhaust system and the pressure vacuum relief line and start all available containment air circulation equipment.
4.3.l Close 1(2) VC 1,2 The Containment Purge Supply 1(2) vc 4,3 The Containment Purge Exhaust 4.3.2 Close 1(2) VC 5,6 The Containment Pressure Relief System 4.3.3 Start the following fans:
- a. 11,12 (21,22) Reactor Shield Vent Fans
- b. 11-14 (21-24) Reactor Nozzle Support Fans
- c. 11-15 (21-25) Containment Fan Coil Units in FAST 4.4 Ensure 50 degrees subcooling is indicated.
4.4.1 Initiate CRT Test No. 41 to monitor subcooling, or, Rev. 0
4.4.2 Ref~o the 50°F-Subcooled lireon the
~ssure-Temperature Curve.~
- 4.5 Isolate letdown and initiate RCS makeup from the Chemical and Volume Control System to increase pressurizer level to greater than 50% of span.
- 4.6 If pressurizer pressure is* <1915 psig, manually block the low pressure SI initiation.
CAUTION: The venting operation *may result in pressure decreasing below the SI setpoint. Action should be taken to manually block the ~utomatic SI signal when pressurizer press.ure decreases to below* 1915 psig.
- 4.7 Increase charging flow to' maximum to limit the pressurizer pressure and level decrease during the venting period.
CAUTION: If during the ~enting period, a loss of reactor coolant pump operation occurs, continue the venting and allow natural circulation to establish itself.
4.8 Open the vent isolation valves in one head vent flow path.
4.8.1 Open 1(2)RC40,41.
4.8.2 If 1(2)RC40, or 1(2)RC41 fail to open, then close both valves and open 1(2)RC42,~3 4.9 Observe the pressurizer level trend during the venting and, from the following conditions, determine the probable status of the Reactor coolant System.
4.9.l Increasing pressurizer level. - Gaseous voids exist in the RCS other than the Reactor Vessel Head or pressurizer.
4.9.2 Constant pressurizer level - No significant gaseous voids exist in the Reactor Coolant System.
4.9.3 Decreasing pressurizer level - Gaseous void exists in the Reactor Vessel Head.
Rev. 0
'I -
4.10 e-Close ~ vent isolation valves ~ any e ot the following exist:
4.10.l Reactor vessel level indication stabilizes, OR 4.10.2 Pressurizer pressure decreases by 200 psi, OR 4.10.3 Pressurizer level decreases below 20 percent of span OR 4.10.4 Reactor coolant sub-cooling decreases below the S0°F-Subcooling line on the Pressure -
Temperature curve.
OR 4.10.S The reactor vessel head is refilled as indicated
- by a decrease in t~e rate of depressurization or a change in the rate of the pressurizer level trend.
- 4.11 Re-establish normal charging and letdown to maintain the pressurizer water level in the operating range.
- 4.12 Evaluate the response of the pressurizer level trend to determine if a gas bubble existed in the vessel head. If a gas bubble existed and the venting was terminated P.~ior to the vessel- head being completely refilled, then return to Step 4.4.
NOTE: If multiple venting operations are required and the containment hydrogen concentration is equal to or greater than 3 volume percent, then provisions must be made to remove or reduce the volume of hydrogen from the containment prior to re-opening the reactor vessel head vent.
4.13 Return to the appropriate Emergency instruction following the successful completion of the venting of the reactor vessel head.
c-------------------
Rev. 0
1
)*
e
.~
APPENDIX "A" RV HEAD VENT RCS GASEOUS VOID DETECTION AND SIZING
- 1. Achieve a constant pressurizer level and pressure condition.
Isolate the RCS letdown flow, turn off all pressurizer heaters, and terminate the pressurizer spray by placing the spray control in manual and zeroing the demand signal.
- 2. Record the following parameters.
RCS Pressure = PSI PZR Level = %
Charging Rate = GPM Seal Injection Flow = GPM Seal Leakof f Flow = GPM Time =
- 3. Allow the charging flow to either increase RCS pressure 100 psi or increase pressurizer level 5% of span.
- 4. Record the RCS pressure, pressurizer level and time.
RCS Pressure = -----PSI PZR Level = -----%
Time =
- 5. Reinitiate letdown flow and restore normal pressurizer pressure.
and level control.
- 6. Calculate the initial and final pressurizer vapor space volumes.
6.1 Upper Head 180 FT 3 eyl,i.ndX".i.cal 1440 FT 3 Initial Vapor Volume = (l~PRZ.lv1)(1440 FT 3 ) + (180 FT 3 ) = I FT 3 Rev. 0
~. *.~
_, * (I ..
)
6.2 Final Vap~Volume =
(
~.....----------
Initial Vapor
) - (
6 PZR Level Xl440) =
FTJ Volume Step 6.1
- 7. Detenriine the total charged volume into the RCS.
Charged Volume =
{( + )-( )}X( )X(.134ft.)=
~ Flow Seal Flow Seal teak Tine QU' - - -
Off Min.
- 8. Determine the expected pressurizer lever change*.
Expected level change =
( )X(l00% ~ = _ _ _ _%
Chg Vol 1800FT Step 7
- 9. If the actual pressuri~er level change is less than the expected level change then a gaseous void exists in the reactor coolant system. Perform the following step to determine the volume of the RCS void.
- 10. The initial and final RCS gaseous void volumes can be calculated from the following equations.
Initial RCS Void =
(._- ________ -
Initial Vapor Volume
) (
Final Vapor
) - (
Charged Volume
)
Step 6.1 Volume Step 7 Step 6.2 '
=
FT 3 PSIG Initial Pressure Step 2 1 - PSIG Final Pressure Step 4 Final RCS Void =
( )X( PSIG)
~I-n~i~t~i-a~1-=v~o~i~d- Initial Pressure Step 10 Step 2 3
=
FT
( PSIG)
Final Pressure Step 4 -END-Rev. 0
