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
. .: -... **: . ':t
.-... ~ -~
\***
'. ~.. - .. ..*.. .
REACTOR VESSEL HEAD VENT OPERATION
(
REVISION 0 FEBRUARY, 1981
/
\
.. JjJ070*20 Jo2.. *
. **. **-~* ~.... " REACTOR VESSEL HEAD VENT OPERATION A. PURPOSE .
The objective of these instructions is to specify required operator actions and precautions necessary to remove gases from the reactor vessel head by operation of the Reactor Vessel Head Vent.
- C.A.UTION~ This .venting. guidelin~ should not_ be used as_ the primary means to mitigate an Inadequate Core Cooling event.
Refer to Inadequate Core Cooling Guidelines for appropriate operator actions and precautions.
CAUTION: This venting guideline assumes that the reactor containment conditions are near normal conditions and that any venting operation is performed prior to throttling safety injection flow during a POST-LOCA cooldown and depressurization operation. _
B. SYMPTOMS For plants with a RV level indication
- l. Reactor vessel level is less than (insert plant specific value which_ includes an allowance for normal channel accuracy) percent of span.
- For plants with/without a RV level indication
- 2. Abnormal reactor coolant system conditions such as large variations in pressurizer level during normal charging of spraying operations have occurred.
- 3. If available, reactor vessel head temperatures equal to or greater
(
than saturation temperature.
Revision 0 Page 1 February, 1981
- ra.pi d RCS*: c~ql?o~jn'., _or* ~o.~e' ~Dcove.ry events) 'that may result
...... :: in the ~re~en~e of a gaseous ~aid in the.vessel head .
C. IMMEDIATE ACTIONS None D. SUBSEQUENT ACTIONS CAUTION: Do not trip any running or start any non-operating reactor coolant pumps during the performance of the following actions.
NOTE: lf the safety injection system is in operation, then the actions of steps marked by an asterisk will not be applicable.
(
I
'-* l. Terminate any changes to the reactor coolant system that may be in progress and bring the RCS to as close to a steady-stat~
condition as possible.
- 2. Attempt to recombine any condensible gases by increasing RCS pressure through the use of the pressurizer backup heaters and increased charging flow. If this step is successful in condensing the gas volume in the vessel head (as indicated by a r_eturn to normal readings in those parameters used to determine the presence of the gases) then return to the appropriate operating instruction.
CAUTION: Increased charging flow with condensible gases in the RCS may result in a decreasing pressurizer level~ 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 EOI-0, Immediate Actions and Diagnostics.
February, 1981 Revision 0 Page 2
- 3~ 'tri *p~eparation for.-:venting, isolate the containment purge and
-. *
- exh~~st:* system and the pressure vacu~m relief 1 ine and start all available _containment air circulation equipment .
- 4. Increase the RCS sub-cooling to .{insert plant specific value_
which is 50°F above the value which is the sum of the errors for.the temperature measurement system used, and for the pressure measurement system translated into temperature using the
- saturation *tables)* by *either initiating *an RCS pressurization or by dumping steam from the non-faulted steam generators.
- 5. If required, perform the actions of Appendix B to determine the maximum allowable time period for venting {only for plants which vent directly to containment).
- 6. Isolate letdown and initiate an RCS makeup by the chemical volume and control system to increase pressurizer level to greater than
(.... 50% of span.
1
- 7. If not already performed, manually block the low pressure SI initiation if the permissive is energized.
CAUTION: The venting operation may result in pressure decreasing below the SI setpoint. Action should be taken to manually block the automatic SI signal when the permissive is energized.
- 8. Increase charging flow to maximum to limit the pressurizer pressure and level decrease during the venting period.
NOTE: Observe the pressurizer level trend during the venting and, from the following conditions, determine the probable status of the reactor coolant system.
(
February, 1981 REVISION 0 Page 3
,;;~~~.(; .. . *'*',\
- .~ .
~ : :*__... .:':'*
~.:: *.** ~' .
a) iricreas*1*rig* pr'~;s*suriz~r 1,~vel - Gaseous vo.ids exist in the RCS other -tti-~n *th:~. rea*~*t-or ~essel hea.d or pressurizer.
b) Constant pres~urfzer level - No significant gaseous voids exist in the reactor coolant system.
c) . Decreasing pressurizer level - Gaseous void exists in the reactor vessel head.
- 9. Open the vent isolation valves in one head vent flow path.
NOTE: If one or both valves fail to open, close both valves and open the isolation valves.in the parallel flow path.
- 10. Close both vent isolation valves when: .
Reactor vessel level indication stabilizes, OR The time period determined in Step 5 is met, OR Pressurizer pressure decreases by 200 psi, OR Pressurizer level decreases below 20 percent of span OR Reactor coolant sub-cooling decreases below (insert plant specific value which is the sum of the errors for* the temperature measurement system used, and for the pressure measurement system translated into temperature using the saturation tables).
OR f) *The reactor vessel head is refilled as indicated by a decrease in the rate of a depressurization or a change in the rate of the pressurizer level trend.
February, 1981 Revision 0 Page 4
. )
- . *.. CAUTI-ON:. ***.If duri'.~~** the . v.en~*i ng._peri od, a 1ass of reactor coolant pump ope~at~o~ occ~rs;* continue the venting and allow natural.circulation to establish itself.
- 11. Re-establish normal charging and letdown to maintain the pressurizer water level in the operating range.
- 12. Evaluate the response of the pressurizer level trend to determine if a gas bl!bbl~ ~)!:.is_ted in ~he. vessel h~ad. If a gas bubble existed.and the venting was terminated prior to the vessel head being completely refilled, then return to Step 4.
NOTE: If multiple venting operations are required and the con-tainment hydrogen concentration is equal to or. greater than 3 volume percent, ti-en provisions must be made to
- remove or reduce the volume of hydrogen from the
. containment prior to re-opening the reactor vessel head vent.
- 13. Return to the appropriate operating instruction following the successful completion of the venting of the reactor vessel head.
February, 1981 Revision 0 Page 5
(-***
. -~* . . I \ :_; .
. ~ " .. ' ,. - ' *.' ,_.
. RCS GAS:EOUS VOID DETECTION AND SIZING
- 1. Achieve a constant pressurizer level and pressure condition.
- 2. P)ace ~he RCS ~ide range or pressurizer pressure and the pressurizer level on trend recorders. T~e-sc~l~ should be 150 psig pressure and 10% of span for level.
- 3. Record the follow.ing parameters.
RCS Pressure =
- - - -PSI PZR Level = %
Charging Rate
=
- - - -GPM Seal Injection Flow =
c** - - - -GPM Seal Leakoff Low = GPM Time =
- 4. 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.
- 5. Allow the RCS charging flow to either increase RCS pressure 100 psi or increase pressurizer level 5% of span.
- 6. Record the RCS pressure, pressurizer level and time.
RCS Pressure =
PSI PZR Level = ----%
Time = ----
- 7. Reinitiate RCS letdown flow and restore normal pressurizer-pressure
( and level control.
February, 1981 Revision 0 Page 6
. ~* .
Calculate the initial and final pressurizer vapor
.-.e_.
~pace volumes.
Initial Vapor Volume= (1-PZR Level % X Total Cylindrical PZR Volume FT 3) +
(Upper Spherical Volume FT3)
= n3 Final Vapor Volume = (Initial Volume) (~ PZR Level X Total Cylindrical Volume)
=
FT3
- 9. Determine the total charged volume into the RCS.
Charqed Volume = (Charging + Seal Injection - Seal Leakoff GPM) X l
(Time) X (7 45 GPM)
. ITT
= - - - -FT 3
- 10. Determine the expected-pressurizer level change.
Expected ~ level = (Charging Volume FT3) X (Total PZR lOO%Volume FT3)
= - - - -%
- 11. If the actual pressurizer level change is less than the xpected level change then a gaseous void exists in the reactor coolant system. Perform the following step to determine the volume of the RCS void.
- 12. The initial and final RCS gaseous void volumes can be calculated from the following equations.
(
February, 1981 Revision O Page 7
. ~>.,,..*.*...;. ~;.'," ,_.-;- :*... .". ,* . :_ *: .
I ~ . ~ ,;
~
.__ .' : '* ~
-. * * * *l_ - *
'; . ' < ~*; ' ,, ..
- ~
' .~ .. ' .. ' '
Initial RCS Void= (Initial Vapor Volume) {Final Vapor Volume) -(Charged Volume)
. Initial Pressure)
(1 - Final Pressure 3
=
- - - -FT Final R~S Void = (Initial RCS Void) X (Initial Pressure)
(Final Pressure)
=
- - - -FT3 -
February, 1981 Revision 0 Page 8
.APPENDIX 6 11 11 RV HEAD VENT GUIDELINE VENTING TIME PERIOD
- 1. Convert the containment free-volume to containment volume at standard temperature and pressure conditions.
Cont. Volume (STP) = (Cont. Volume FT 3) x (Cont. Pressure**)x( 492°R )
14.7 PSIA Cont. Temp.*
= FT 3. -
- Temperature in degrees Rankine (°F + 460)
- If containment pressure has increased above 14.7 psia then use 14.7 psig as pressure for conservatism.
- 2. Determine ~he containment hydrogen concentration in volume percent units.
( .- NOTE: The containment- hydrogen concentration will be insigificant
\:___ '
if there has been no leakage from the RCS to the containment.
- 3. Calculate the maximum hydrogen volume that can be vented to the containment wh1ch will result in a containment hydrogen concentration of less than or equal to 3 volume percent.
Maximum H2 Volume = (3.0%-Cont. H2 Concentration100%
%) X (Cont. Volume [STP])
=
- 4. From Curve #1 {RCS Pressure vs. H2 Flow Rate) determine the allowable venting period which will limit the containment hydrogen concentration to 3 volume percent.
Venting Period = Max. Hz Vented {From Step 3)
H2 Flow Rate
= Mins.
(
February, 1981 Revision 0 Page 9
' ' *.~ ' , ._.-
- ~ -' . ':' "- . _: ~
... :*.' ' .* . ,: . : APPENDIX' -B .
2000 1500 RCS Pressure
)PSI)
(
~--*
1000 500 I
r i------****
r*----, .
( II . '
t r**:: :*-: --*.
_: _.:___l ___ .:. __ _:_. ______ _: _____ - **--------- --
1000 2000 3000 4000 5000 HYDROGEN FLOW RATE (SCFM)