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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled ML20098A4861995-09-22022 September 1995 Proposed Tech Specs,Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20086G5691995-07-0606 July 1995 Proposed Tech Specs Section 3.8.3.1,Page 3/4 8-15 Re Footnote & Bases & Expansion ML20085G7171995-06-14014 June 1995 Proposed Tech Specs,Clarifying in Revised Bases of 3/4 Chapter 8,that Alignment of Standby Auxiliary Transformer Intended to Be Temporary Alignment & Will Be Utilized When Normal Preferred Offsite Power Source,Rat Unavailable ML20083M0731995-05-12012 May 1995 Proposed Tech Specs Revising SR 4.1.6.2 to Support Exemption from 10CFR50,App J Type a Test Schedule ML20083A1391995-05-0202 May 1995 Proposed Tech Specs,Adding Automatic Load Sequencer to Plant TS ML20082D9881995-04-0404 April 1995 Proposed Tech Spec Page 6-7 Reflecting Corrected Terminology Re Composition of Plant Review Board ML20081J5031995-03-17017 March 1995 Proposed TS 3.9.4 Re Containment Airlock Doors to Be Open During Fuel Movement ML20081D1591995-03-17017 March 1995 Proposed TS Table 3.3-8, Accident Monitoring Instrumentation, Deleting Loop Numbers 551,552,553 & 554 ML20082E7731995-03-0404 March 1995 Proposed Tech Specs Re Plant Review Board Composition ML20080N2451995-02-28028 February 1995 Proposed Tech Specs Pages Re Accident Montoring Instrumentation 1999-09-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] |
Text
.._ _._.____ _.._ _ _._. _ _ _ _ - - _._ _ _._._ __
CONTAINMENT = SYSTEMS 3/4,6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERAT]ON l
3.6.3 The containment isolation valves shall be OPERABLE.*
'APPLICABillTY:' MODES 1, 2, 3, and 4.
ACTION:
With one or more _of the containment isolation valve (s) 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 one-deactivated automatic valve secured in the isolation position, or c.. Isolate'ench 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
- 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 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. The provisions of Specification-3,0.4 are not applicable provided L -
that the affected penetration is isolated in accordance with ACTION b or e above, and provided that the associated system, if applicable,
- is declared inoperable and the appropriate ACTION statements for that system are performed.
SVRVElltANCE RE001REMENTS 4.6.3.l' The containment isolation valves 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.
l L
l'
- *lsolation valves associated with the containment hydrogen monitors may be opened on an intermittent basis under administrative control.
- j. lV0GTLE. UNITS--1&2 3/4 6-16 .
-9105080092 910503 L
PDR ADOCK 05000424 P- PDR g.
. _ _ . _ . . _ . _ _ . . _ . , . _ . . , . _ _ _ . . _ . . _ -_.2,_._
CONTAINMENT SYSTEMS O / 5 9 T~
. 3/4.6.3 CONTAINMENT ISOLATION VALVES )
LIMITING CONDITION FOR OPERATION
E 3.6r3 The'contairnent isolation valves shall be OPERABLE. ~)
APPLICABILITY: MODES 1, 2. 3, and 4. ,
ACTION:
Witn one or more of the containment isolation valve (s) inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is cpen 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 one deactivated automatic valve secured in the isolation position, or .
- 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
- 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 SHUT,DOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,
- e. The provisions of Specification 3.0.4 are not applicable provided that the af fetted penetration is isolated in accordance with ACTION b or e above, and provided that the associated system, if applicable, is declared inoperable and the appropriate AC110N statements for that system are performed.
SURVElLtANCE REQUIREMENTS 4.6.3.3 The containment isolation valves shall be demonstrated OPERABLE prior to returning the valve to service af ter 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.
- bOL4DOJVdlV&S 45306/472-b WITH TM- C&fl2lAJMer/T MA/hulli7b6 Ms} Bs- cPar/ED &J AU / YTe2M/YTes.fr BMt3 u2?&2 RMidiST2snV6-OQLIT5DL ,
n
, ... . . . ~ . - .. . .. .
- - - - - - - - ~ _ - _ _ _ _ _ _ _ _
9 4 4
> ENCLOSURE 4 VOLTLE ELECTRIC GENERATING PLANT TECHNICAL SPECiflCATION CHANGE OPENING Of CONTAINMENT ISOLATION VALVES TO FACILITATE CALIBRATION Of THE CONTAINMENT HYDROGEN MONITORS MARK-VP Of AffECTED FSAjLPJ1(S l
~ - - - - - - - - . _. _
O
TABLE 16.3-4 (SHEET 8 0F 15) .
~~
Valve *
' valve Time (s)
Num.ber Function Remote Manual (continued)
ACCW Supply N/A HV-1978 ACCW Supply N/A HV-1979 N/A HV-1974 ACCW Return N/A HV-1975 ACCW Return Safety injection to cold leg N/A HV-8835 Safety injection to hot leg N/A HV-8802B Safety injection to hot leg N/A HV-8802A HV-9002D Containment spray emergency sump suction N/A HV-9002A Containment spray emergency sump suction N/A Reactor coolant pump seal water supply N/A HV-8103D Reactor coolant pump seal water supply N/A HV-8103B Reactor coolant pump seal water sup;ty N/A HV-8103C Reactor coolant pump seal water supply N/A HV-8103A RHR pump discharge to hot leg N/A HV-8840 RHR loop into cold leg N/A HV-8809A RER loop into cold leg N/A HV-8809B RHR suction from hot leg N/A HV-8701A RHR suction from hot leg N/A
[ HV-8702A N/A
! HV-5278'b' Chemical addition Chemical addition N/A HV-5279'b' U Containment H y monitor suction N/A HV-2791A )
Ed2
e . .
VEGP-FSAR-16
.. 1 TABLE 16.3-4 (SHEET 9 or 15)
~ ,
Valve ,
Closure
Time (s)
Number Function l Remote Manual (continued)
HV-2790A containment H 2 m nitor suction N/A HV-2790B Containment H2 "'"It'# ""'ti"" N/A l HV-2793A N Containment H 2 monitor discharge N/A f HV-2192BI " Containment H2 **"it # ""'*A*" N/A HV-2791B Containment H 2 monitor suction N/A HV-2792A N Containment H 2 m nitor suction N/A HV-2793B b Containment H 2 monitor discharge N/A HV-5194 Auxiliary feedwater N/A
.HV-5197 Auxiliary feedwater N/A HV-5195 Auxiliary feedwater N/A HV-5196 Auxiliary feedwater N/A HV-9556A Steam generator secondary side sample N/A HV-9556B' Steam generator secondary side sample N/A HV-9555A Steam generator secondary side sample N/A HV-9555B Steam 9enerator secondary side sample N/A-HV-9554A Steam generator secondary side sample N/A HV-9554R Steam generator secondary side sample N/A 4-HV-9553A Steam 9enerator secondary side sample N/A HV-9553B Steam genefator secondary side sample 'N/A HV-3009 Main steam to auxiliary feedwater pump N/A ;
driver
, 6*W 3
l I
ew .
VEGP-FSAR-16
(
TABLE 16.3-4 (SHEET 15 or 15) .
P
~
( a. See FSAR Section 6.2.4 for discussion of the c66teinment isolation system.
- b. Air supply valves closed and enclosed in lockable boxes to provide sealed, closed barrier, i c. Locked closed. <
- d. These valves are included for table completeness. The requirements of Technical Specification 3/4.6.3 do not apply; instead 'he requirements of Technical Specification 4.5.2.e.1 apply. Valve stroke times where specified will be tested pursusat to specification 4.0.5. I
- e. These-valvea are included for table completeness. The l requirements of Technical Specification 3/4.6.3 do not apply; l instead the requirements of Technical Specification 4.7.4 !
apply. Valve stroke times where specified will be tested s l
pursuant to specification 4.0.5.
These valves are included for table completeness. The f.
requirements of Technical specification 3/4.6.3 do not apply; instead the requirements of Technical Specification 4.6.2.1 apply. Valve -terme times where specified will be tested cification 4.0.5.
pursuant to s[ STROKE
- g. These valves are included for table completeness. The requirements of Technical Specification 3/4.6.3 do not apply; instead the requirements of Technical Specil'4 cation 3/4.7.1.5 and 3/4.3.2 apply to the main steam isolation and bypass valves and main feedwater isolation valves, respectively.
The
. h. These valves are included for table completeness.
requirements of Technical Specification 3/4.6.3 do not apply; instead the requirements of Technical Specification 3/4.7.1,2 apply. Valve stroke times where specified will be tested pursuant to specification 4.0.5.
- i. Th Vkves Md Se OPeJeo od m nJreeMITudT 86 sis I udihR somir/t,5resrtVE &>UTeot..
(
.