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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS ML20115J0181996-07-18018 July 1996 Proposed Tech Specs 3/4.7.7,3/4.9.13 & Corresponding Bases Re Charcoal Test Methodology for Emergency Exhaust Sys ML20107H3931996-04-17017 April 1996 Proposed Tech Specs 3/4.3 Re Adding Ms & FW Isolation Sys Actuation Logic & Relays to Functional Units 4.b & 5.a of Tables 3.3-3,3.3-4 & 4.3-2 & Revising Table 3.3-3 by Adding Action Statements 27a & 34a ML20107F0791996-04-12012 April 1996 Proposed Tech Specs 3/4.4 Re Changing TS, RCS & Associated Bases to Address Installation of Electrosleeves in Callaway Plant SGs ML20107E3251996-04-12012 April 1996 Proposed Tech Specs 3/4.4.5, SGs & 3.4.6.2, Operational Leakage & Associated Bases,Addressing Installation of Laser Welded Tube Sleeves in Plant SGs ML20101R4211996-04-0909 April 1996 Revised TS Pages That Adhere to Testing Methods of ASTM Std D2276-78,Method a for Diesel Fuel Oil Particulate Concentration ML20101J0381996-03-22022 March 1996 Proposed Tech Specs,Implementing Containment Integrated Leakage Rate Program That Would Allow Ilrt,Presently Scheduled for Refuel 8,to Be Rescheduled ML20106G4351996-02-28028 February 1996 Proposed TS 3/4.8.1,ac Sources ML20106G4131996-02-23023 February 1996 Proposed Tech Specs Paragraph 1.A. Re Operating License Change to Reflect Union Electric as wholly-owned Subsidiary of Ameren Corp ML20097D5801996-02-0909 February 1996 Proposed Tech Specs Allowing Use of Alternate Zirconium Based Fuel Cladding Material ML20097D6151996-02-0909 February 1996 Proposed Tech Specs & Bases Re Containment Systems ML20097D6341996-02-0909 February 1996 Proposed Tech Specs Re AFW Sys ML20097F8991996-02-0404 February 1996 Proposed Tech Specs 4.6.1.2.a Re Containment Sys ML20097C2791996-02-0202 February 1996 Proposed Tech Spec 3/4.6.3, Containment Isolation Valves ML20096B1891996-01-0202 January 1996 Proposed Tech Specs 3.9.4, Containment Bldg Penetrations & Associated Bases Section to Allow Containment Personnel Airlock Doors to Be Open During Core Alterations ML20094A1721995-10-23023 October 1995 Proposed Tech Specs,Relocating Audit Frequencies in Former TS 6.5.2.9 to Operational QA Manual 1999-09-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q5411999-09-0808 September 1999 Proposed Tech Specs Reflecting USQ Associated with Increases in Offsite Dose Consequences Reported in FSAR for SGTR & MSLB Accidents ML20195C5191999-05-28028 May 1999 Proposed Tech Specs Sections 3.9.1,revised to Maintain CTS Requirements on Refueling Pool Boron Concentration Limits & 5.6.5,revised to Delete Item 5.6.5.a ML20207F4801999-05-27027 May 1999 Proposed Improved TSs & ITS Bases ML20206G3621999-04-30030 April 1999 Proposed Conversion Tech Specs Section 1.0/ITS Section 1.0 ML20205S9141999-04-21021 April 1999 Proposed Tech Specs Sections 1.0,3.3,3.4,3.6,3.7 & 3.9, Converting to ITS ML20205L0901999-04-0707 April 1999 Proposed Tech Specs Section 3.3,3.4,3.5,3.6,3.7,3.8 & 4.0, Converting to ITS ML20207L1061999-03-0909 March 1999 Proposed Tech Specs Re Conversion to ITSs Sections 3.3,3.4, 3.6,3.7.3 8,3.9 & 5.0 ML20196G1731998-11-25025 November 1998 Proposed Tech Specs Section 3.3, Intstrumentation, Converting to Improved Tech Specs ML20196D0011998-11-23023 November 1998 Proposed Tech Specs Pages Re follow-up Items Related to 970515 Request for Amend to License NPF-30 ML20155B5791998-10-27027 October 1998 Proposed Tech Specs for Use of Electrosleeves on Two Cycle Basis ML20154S2371998-10-21021 October 1998 Proposed Tech Specs Sections 3.1,3.2,3.4,3.5 & 5.0 Re Reactivity Control Sys,Power Distribution Sys,Rcs,Eccs & Administrative Controls,Respectively ML20154F8311998-09-29029 September 1998 Proposed Tech Specs Revising ESFAS Functional Unit 6.f Re Loss of Offsite power-start turbine-driven Pump ML20154A2901998-09-24024 September 1998 Proposed Tech Specs Converting to Improved TS Re Section 3.4, RCS, Consistent w/NUREG-1431 ML20151U1031998-08-27027 August 1998 Proposed Tech Specs Sections 1.0,2.0 & 3.0,converting to Improved Tech Specs ML20236Y1721998-08-0404 August 1998 Proposed Tech Specs Re Conversion to Improved STS Sections 3.1,3.2,3.5,3.9 & 4.0 ML20198D3201998-07-31031 July 1998 Rev 20 to Inservice Testing Program at Callaway Nuclear Plant ML20236W3721998-07-30030 July 1998 Proposed Tech Specs Revising Table 4.3-2 by Adding Table Notation to Clarify That Verification of Time Delays Associated W/Esfas Functional Units 8.a & 8.b Is Only Performed as Part of Channel Calibr ML20236J0821998-06-29029 June 1998 Proposed Tech Specs 3.7.1.7,4.7.1.7.1,4.7.1.7.2 & Bases 3/4.7.1.7 Revising to Address All Four Atmospheric Steam Dump Lines ML20236E9651998-06-26026 June 1998 Proposed Tech Specs Pages Re Conversion to Improved STS, Section 3.6 ML20216F3791998-03-0909 March 1998 Proposed Tech Specs SR 3/4.5.2b.1 Adding Clarification in Regard to Venting ECCS Pump Casings & Accessible Discharge Piping High Points ML20195B5651998-03-0202 March 1998 Rev 22 to QC Procedure QCP-ZZ-03003, Matl Receipt Insp ML20217P8161998-02-23023 February 1998 Proposed Tech Specs Replacement Page B 3.8-34 Re AC Sources Shutdown ML20198T3521998-01-16016 January 1998 Proposed Tech Specs 3/4.3,revising Ms & Feedwater Isolation Sys Slave Relay Surveillance from Quarterly Actuation Logic Test to Monthly Actuation Logic Test on Staggered Test Basis ML20197D6461997-12-16016 December 1997 Proposed Tech Specs Table Revising Lift Setting Tolerance for Main Steam Line Safety Valves ML20199B4261997-11-10010 November 1997 Proposed Tech Specs Re Page 5 of 8 for FW Isolation Changes ML20198P3361997-10-31031 October 1997 Proposed Tech Specs Reducing Repeated Alarms,Rod Blocks & Partial Reactor Trips That Continue to Manifest,During Beginning of Cycle Operation Following Refueling Outages ML20198P4141997-10-31031 October 1997 Proposed Tech Specs,Revising ESFAS Functional Unit 6.f, Loss of Offsite Power-Start Turbine-Driven Pump, in Tables 3.3-3,3.3-4 & 4.3-2 ML20217B3261997-10-22022 October 1997 Procedure MPE-ZZ-QY128, Operational Test Sequence of 4.16KV Diesel Generator NE02 Air Circuit Breaker 152NB0211 ULNRC-03664, Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits1997-10-17017 October 1997 Proposed Tech Specs 3/4.4.9 Re Pressure/Temp Limits ML20217B3001997-09-14014 September 1997 Procedure ETP-NF-00001, MDAFW Pump (DPAL01A) Start Inhibit Circuit Test,Lsels Relay K1102 ML20217B3081997-09-0404 September 1997 Procedure ETP-BF-00002, Mdaew Pump (DPAL01B) Start Inhibit Circuit Test,Lsels Relay K4102 ML20217H8031997-08-0808 August 1997 Proposed Tech Specs 3/4.3 Re Instrumentation ML20210H2151997-08-0808 August 1997 Proposed TS Revising SRs 3/4.7.4, Essential Svc Water Sys by Removing Requirement to Perform SRs 4.7.4.b.1, 4.7.4.b.2 & 4.7.4.c During Shutdown ML20198F3411997-08-0808 August 1997 Proposed Tech Specs,Revising Table 3-7.2 to Specify That Lift Setting Tolerance for Main Steam Line Safety Valves Is +3/-1% as-found & +1% as-left.Table 2.2-1 Revised by Reducing Sensor Error for Pressurizer pressure-high Trip ML20198F3911997-08-0808 August 1997 Proposed Tech Specs Changes,Revising Feedwater Isolation ESFAS Functions in TS Tables 3.3-3,3.3-4 & 4.3-2 ML20195B5261997-05-20020 May 1997 Rev 6 to EDP-ZZ-03000, Containment Building Coatings ML20154Q1191997-05-15015 May 1997 Proposed Improved TS Section 3.7, Plant Sys ML20198J7301997-05-15015 May 1997 Proposed Conversion to ITS Sections 1.0,3.1,3.2,3.3,3.4,3.7, 3.9 & 5.0 for Plant ML20138B7421997-04-24024 April 1997 Proposed Tech Specs 6.0 Revising Title Senior Vice President,Nuclear to Vice President & Chief Nuclear Officer ML20141D9331997-04-14014 April 1997 Rev 18 to Inservice Testing Program for Callaway Nuclear Plant ML20141C3401997-04-14014 April 1997 Rev 18 to CNP IST Program ML20137N6111997-04-0101 April 1997 Proposed Tech Specs Table 3.3-3 Re Engineered Safety Features Actuation Sys Instrumentation ML20195B5581997-03-11011 March 1997 Rev 12 to Matls Engineering Procedure WEP-ZZ-00015, Preparation of Procurement Documents ML20195B5491997-01-31031 January 1997 Rev 22 to Administrative Procedure APA-ZZ-00400, Procurement of Parts,Supplies,Matls & Svcs ML20135E7351996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt One H Replacement Matl ML20135E7391996-12-11011 December 1996 Tests to Determine Ampacity Derating Factors for Electrical Conductors Installed in 1 & 4 Diameter Rigid Steel Conduits Encapsulated by KM1 Darmatt Three H Replacement Matl ML20135E7431996-12-11011 December 1996 Test to Determine Ampacity Derating Factor for Electrical Conductors Installed in 600mm X 101mm X 3650mm Long Cable Tray Encapsulated by KM1 Darmatt Three H Replacement Matl ML20140G2331996-10-31031 October 1996 Rev 6 to Callaway Plant Offsite Dose Calculation Manual ML20217B2951996-10-0303 October 1996 Procedure ISP-SA-2413A, Diesel Generator & Sequencer Testing (Train a) ML20117K6431996-09-0505 September 1996 Proposed Tech Specs,Revising TS 3/4.4 Re RCS 1999-09-08
[Table view] |
Text
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CONTAINMENT SYSTEMS ,
3/4.6.3 CONTAINMENT ISOLATION val.VES l LIMITING CONDITION FOR OPERATION W h.
3.6.3 -TheAcontainment isolation valve)(;;;;ifhd in T;bh 2.0-1 shall be OPERABLE. itt, t eebt.ie.. ;;..,. ee 4,e a i.. T.th :.0 1. %
' APPLICABILITY: NODES 1, 2, 3, and 4.
ACTION:
With one or more of the containment isolation valve (s) ;;;;ifh d h Tet h 2.0-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and:
- a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, -
or
- b. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least N one deactivated automatic valve secured in the isolation position, l
- c. Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange or cAccK.j va/re wi+4 f/otd
~
- 4royA Me valve secused,&or x a
- d. Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD '
T SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. **
)
- e. 7%e y re vittcAf o f .5,*oeetScaf%s 2.o.4 are no/ csh' cable .
SURVEILLANCE REQUIREMENTS 4.6.3.1 ontainment isolation valves ;p;;ifhd h T;t h 2.0-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test, and verification of isolation time. "
W loc. red or realed elosed contsinmed it'I*h'o^ Yol **Y b' 9**d on in ferm,6+ f,a.nr ander admintrWwe don 4*I.
W /^t s'Ce T' l-/ E A s-
.W' l.
-- /
3/4 6-16
) CALLAWAY - UNIT 1
= . ;.
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9602080175 960202 PDR ADOCK 05000483 p PDR .. . . .
l ATTACHMENT 3 Insert to TS 3/4.6.3 (** footnote)
- i For penetrations with parallel containment isolation valves, the penetration is considered isolated if the flowpath with the inoperable valve has been isolated. The penetration may still have flow through it utilizing a parallel flowpath.
For the motor operated valves associated with reactor coolant pump cooling, automatic isolation valves (EGHV58, 59, 60, 61, 62) and remote manual isolation bypass valves (EGHV127, 130, 131, 132, 133), 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> are allowed to conduct _ actuator diagnostic evaluations which are required for post maintenance testing to restore a motor operated valve to an OPURABLE condition, during which time, the valve may be energized for short periods of time for the purpose of cycling.
1 l
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O I i l 2 l 3 1 4 l 5 I
CALLAWAY M. ANT - FAULT TREE r0 !
N00EL OF PENETRATION P-76 IU !
ANALYST: K6C l CMATION DATE: 10-27-95 REVISION : 11-01-95 CAILURE OF PEN P-76 70150. WHEN WORK-ING ECHV61 OR 62 I GTrito I
WORKING ON VALVE NORKING ON VALVE l' ECHV61 EGHV62 E
GTF120 GT8P200 PAGr. 2 I
BAEAK IN PIPE BREAK IN P]PE SEGNENT X (PSX) SEG8ENT Y (PSV), !
3 GIF 130 GTSP134 i r3 r \
~
I I I I DFEAK IN PIPE VALVES E0HV61 CR BREAK IN PIPE EGHV62 AND $
SEGMENT X. EGHV133 FAIL TO SEGNENT Y. EGHV61 GR 133 CLOSE. FAIL TO CLOSE.
d 8 REAM-PSX GTOP141 8REAK-PSY GT8P145 t .72-006 A "g 5 I' l l I I EQHV133 FAILS TO EGHV61 IS OPEN AND VALVES EGHV61 OR MOTOR OP, VALVE CLOSE. FAILS TO CLOSE. EGHV133 FAIL TO EGHV62 CLOSE. FAILS 70 CLCM-NOF0 5 Gip sso GTOP 52 GTOP141 EG-Mov-00-EGHY62 1.4 4 -003 THIS PAGE i I I EGHV61 IS OPEN E0 FAILS TO CLOSE EGHV61 FAILS T0 mi!LE IN T.S. ACT EGHY61 DN CONNAM) CLOSE WHILE IN I.S.
FRON CONTROL RN. A01.
6 gasyss.0 PEN EO-x4-r0-E0HY61 EG-MOV-00-61A0f 1.00E+000 1.00E-002 S 00E-001 CPERATORS FAIL 70 N0 TOR OP. VALVE ClosE EGHVl33. EGHY133 FAILS TO CLOSE-NOF0 I
, OP-X440-HV133 EG-MOV-00-HV133 i . 00E -002 1.44E-003 B
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=
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, , O. I 1 1 2 1 3 1 4 1 5 l womE ON VALVE CALLAWAY PLANT - FAULT TREE N00EL OF PENETRATION P-76 TBP 2 GT8P200 EVISION : 11-01-95 ANALYST: K6C l CREATION DAT': 10-27-95 l rF a 10 /T 1 23
~
g l BREAK IN PIPE BREAK IN PIPE SE0 MENT R lPSX) SE0 MENT Y (PSY)
I GT8P210 GT8P213 r ,
l l l l BT(AK IN PIPE MOTOR OP VALVE BREAK IN PIPE VALVES EGHV62 OR BEGMEN! X. EGHV61 SEGMENT Y. 132. AND E0HV61 i I
FAILS TO CLOSE-NOF0 FAIL TO CLOSE.
2 SAEAK-PSX EG-MOV-00-EGHV61 BREAK-PSY GTOP224
- 1. 75E-006 $ . 44E-003 ~t .70E-006
~
l i MOTOR OP, VALVE VALVES EGHV62 OR 1 ECHV61 EGHV132 Fall T0 FAILS TO CLOSE-NOF0 CLOSE 3 EG-m0v-00-EsHv6 Gr8P234 1,44E-003 l I ,
k EGHV132 FAILS 10 E6HV62 IS OPEN AND CLOSE. FAILS TO CLOSE. !
d GT8P243 GiBP245 (
~
l OPERATORS FAIL TO MOTOR OP. VALVE CLOSE E6HV132, EGHV132 FAILS TO CLOSE4s0F0 l 5 OP-xm -r0-Hv132 EG-MOV-00-HV132
$.00E402 1. 4dE-003 6
~
l I E0HV62 IS OPEN EO FAILS k0 CLOSE E0HV62 F AILS TO WHILE IN 1.9. ADT EGHV62 04 COMMAND CLOSE WHILE IN T.S.
FROM CONTROL RW. A07 '
EGHV62-OPEN EO-XPE-FO-EGHV62 EG-MOV-00-62A0T s 00Ew- 1,00E *2 s.00E-00s 8
3~
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AG4C H W1 W & S W W ZWZ i m .
, ,s m , . . , _ - . . - . . , --..m. . . <
4 ,
, Page 1 NUPRA 2.2x FILE : TBPENET.FTP UE Minium Cut Set Solution for fault tree TBPENET , Serial no.= 9 Performed : 13:07 1 NOV 1995 Cut Set Equation produced is : TBPENET. EON CALLAWAY PLANT - FAULT TREE MODEL OF PENETRATION P 76 Top event GTBP110 Top event unavailability (r.ev appr)= 3.14E-08 Cutoff value used = 1.00E 20 Nurber of Booler i Indicated cut Sets = 10 Number of MCS In equation flle = 10 j MINIMAL CUT SETS SORTED BY UNAVAILABILITY
- 1. 1.75E 08 OP+XHE FO HV133 BREAK PSX I
- 2. 8.75E 09 BREAK PSX EGNV61 OPEN EO-XHE-FO-EGHV61 EG-MOV-00-61A0T
- 3. 2.52E 09 BREAK PSX EG MOV 00-EGHV61
- 4. 2.52E-09 EG MOV-00-HV133 BREAK PSX l S. 2.52E 11 OP XHE FO HV132 EG-MOV 00 EGNV61 BREAK PSY j
- 6. 2.52E 11 OP XHE-F0-HV133 EG-MOV 00-EGHv62 BREAK-PSY
- 7. 1.26E 11 BREAK-PSY EG MOV-00-EGHV62 EGHV61-OPEN EO-XHE FO-EGHV61 EG MOV-00-61A0T ;
- 8. 1.26E-11 BREAK PSY EG-MOV 00-EGHV61 EGHV62-OPEN '
EO-XHE FO-EGNV62 EG-MOV-00-62A0T
- 9. 3.63E 12 EG MOV 00-Hv132 EG-MOV 00-ECHV61 BREAK-PSY ,
- 10. 3.63E 12 EG MOV 00-HV133 EG-MOV-00-EGHV62 BREAK PSY l l
l l
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