Proposed Tech Specs 3/4.6.1.7 & 4.6.1.2f Re Leakage Testing Requirements for Containment Purge Supply & Exhaust Isolation ValvesML20097H207 |
Person / Time |
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Site: |
Vogtle |
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Issue date: |
06/17/1992 |
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From: |
GEORGIA POWER CO. |
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To: |
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Shared Package |
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ML20097H200 |
List: |
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References |
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NUDOCS 9206240375 |
Download: ML20097H207 (5) |
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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
ENCLOSURE 3 V0 GILE ELEGRIC GENERATING PLANT REQUEST 10 REVISE TECHNICAL SPEClflCATIONS 3/4.6.1.7 AND 4.6.1.2f IldlBEllDMU_0LEOFDRATIDH lhe proposed change to the Vogtle Unit I and Unit 2 Technical Specifications would be incorporated as follows:
Benove Pang insert.P L qe 3/4 6-3 3/4 6-3 3/4 6-4' 3/4 6-4*
3/4 6-11 3/4 6-11 3/4 6 12 3/4 6-12 B 3/4 6 3 8 3/4 6 3 8 3/4 6-4* B 3/4 6-4*
4
- 0verleaf page. No change.
E3-1 9206240375 920617 PDR ADOCK 0S000424 P PDR t
' CONT /JNMENT SYSTEMS 5URVEILLANCE P J IREMENTS (Continued)
- b. any perioaic Type A test fails to meet 0.75 L, the test schedele for subsequent Type A testr, shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet 0.75 L,, a A test shall be performed at least every 18 months ntil two
- utive Type A tests meet 0.75 L, at which time the ovE test a
may be r?sumed; h, c. 'e 2 1 racy of each Type A test shall be verified by a supplemental
+
ch: -
5
'wifirms the accucacy of the test by verifying that the
- ,olute value of the supplemental test result, L c, minus the
s a of the Type A and the superimposea leak,gL , is aqual to or less than 0.25 L ;
a
- 2) Has a duration suf ficient to establish accurately the change in r leakage rate between the Type A test and the supplemental test; and
- 3) Recoires that the rate at which gac is injected into the contain- ,
ment or bled from the containment during the supplemental test is Letween 0.75 L3 and 1.25 La '
- d. Type ' and C tn b y all be conducted with gas at a nressure not less taan Pa , 45 psig, at intervah i.. Creater than 24 months except for tes'- involving:
l
- 1) Air locks and S Purgesupp[yandexhaustisoiatienvalveswithresilientnaterial ,
seals.
- e. Air locks shall be tested and demonstrated OPERABLE by the require-ments of Specification 4.6.1.3; a
- f. Purgesupplyandexhaustisol)tionvalveswithresilie, material seals shall be tested anc g &anstratedJPERABLE by the requirements of Specification 4.6.1.7.2 {n F M D .3)
- g. The provisions of Specif:'.ation 4.0.2 are not applicable.
t V0GTLE UNIU - 1 & 2 3/4 6-3
CONTAINMENT SYSTEMS CONTAINMENT VENTILATION SYSTEM n
LIMITING CONDITION FOR OPERATION 3.6.1.7 Each containment purge supply and exhaust isolation valve (HV-2626A&B, HV-2627A&B, HV-2628A&B, HV-2629A&B) shall be OPERABLE and:
- a. Each 24-inch contair. ment purge supply and exhaust isolation valve shall be closed and sealed closed, anu
- b. The 14-inch containment purge supply ar.d exhaust isolation valve (s) shall be closed to the maximum extent practicable but may be open for surge system operation for pressure control, for ALARA and respirrble air quality considerations for personnel entry and for surveillance tests that require the valve (s) to be open, j
/
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTION:
- a. With a 24-inch containment purge supply and/or axhaust isolation valve open or not sealed closed, close and seal that valve or isolate the penetration (s) within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, otherwise 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 00WN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- b. With the 14-inch containment purge supply and/or exhaust isolation 3
valve (s) open for reasons other than given in Specification 3.6.1.7b o above, close the open 14-inch valve (s) or isolate the penetratior.(s) b within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, ctherwise Le 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 SHOTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, _
- c. U't', a centcinacnt purg ;upply and/cr ;xhaust i;clatica valvc(;)
-having-e m;;sured leakag; rate in excess of the limits-of-E9ecifi
- tion 4.5.1.7.i', restorc the inapeceble valva (s) ta OPEIiAOL status i#"24h"" "h"" ';i""""
fNSERTP*t "C hours, and in COLO $UUTOOWN .ithin the fel's.in; 00 huwcs.
s~ -^
Q _ _
SURVEILLANCE REQUIREMENTS
. 4.6.1.7.1 Each 24-inch containtr.ent purge supply ar.a exhaust isoiation valve (HV-2626A, HV-2627A, hV-2628A, HV-2629A) shall be verified to be sealed closed at least once per 31 days.
a V0GTLE UNITS - 1 & 2 3/4 6-11
INSERT 1
- c. With a Type C leakage test on the containment purge sg y and/or exhaust penetrations exceeding 0.06 La, but the combineo ,eakage rate for all-penetrations and valves subject to Type B and C tests less than 0.60 La, reduce the leakage to less than 0.06 La within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by either re;toring the affected valve (s) to OPERABLE status, or isolating each affected penetration by insertion of at least one blind flange outside of containment. Otherwise be in at least HOT STANDBY within the neit six hours, and in COLD $HJTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- d. Wit'; a containment purge supply and/or exhaust isolation valve (s) having a measured leakage rate by either the Type C test or the between valle test such that the combined leakage rate for all pentrations and valves subject to Type B and C tests is greater than or equal to 0.60 La. restore CONTAINMENT INTEGRITY within I hour or 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 COLD SHUTDOWN within the following 3J hours.
t l
l l-
--- - - . _ - - . .~ . - - - - _ _ - . - - - ___- . . - . . - - --
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.6.1.[ hat least once per 3 months the containment purge valves with resilient material seals in each sealed closed containment purge supply ind ,
exhaust penetration shall be demonstrated OPERABLE by verifying that +.he '
measuredpenetrationleakagerateislessthan0.06Lydcrp::n-f::dtoI,.
4.6.1.7h[)Each14-inchcontainmentpurgesupplyandexhaustisolationvalve (HV-26268, HV-26278, tiV-2628B, HV-2629B) shall be verified to be closed or apen in accordance with Specification 3.6.1.7b at least once per 31 days.
~-~m_ -
ypressuring be}weer1 Me valves to fh. Ira emlatninnf purge penetrafion exceccLs its requiralacfintimit, a Type C P Ica ka.1e com 6;ned leakales f s/n/l bc xtivemad wdhir) 24 /wurs g<wided f/n lofal
, ge rat [e rent ains less Ihari 060 La.
ll. (o..).l.) A tl leaJl 0ACL fer EYP106f$5 e4c}i crnfal4menf p;sege 4ypp j, .;e;c) uhaust peneMifurt sds// de 7)pe C k.cfed. Eech Trpe C /a?.rdsbut '
penc/mfion .j
~ /eatofe ei kss Men 0,OA la._-
V0GTLE UNITS - 1 & 2 3/4 6-12
l
-- -m '
f rvgutredacfwa limU fie & nmrkth l CONTAlNMENT SYSTEMS { S ut,rilmct yec Wicc/ in ij. g,f.1, 3 ls 1 main /aMed in Sefien 6 2.C, of M- FSM and cu /vv//ed l,4jpgfp,ecegy,y,
%~~a x
-s, BASES, CONTAINMENT VENTILATION SYSTEM (Continued)
The use of the containrent purge lines is restricted to the 14-incn purge supply and exhaust isolatior valves since, unlike the 24-inch valves, the 14-inch valves 3re capable of closirg during a LOCA ca steam line break accident. There-fore, the SITE BOUNDARY doso guideline of 10 CFR Part 100 would not be exceeded in the event of an accident during containment PURGING operation. Only safety-related reasons; e.g. , conta inment pressure control or t e reduction of air-borne radioactivity to facil itate personnel access for sui eillance and main-tenance activities, should t e used ta justify the opening of these isolation valves.
Leakage integrity tests with a maximum allowable leakage rate for containment purge supply and exhaust sup ply valves will provide early indication of resilient material seal degradation ar d will allow opportunity for repair before gross leak-age failures could develop.U The 0.60 L leakage limit of Specification 3.6.1.2b.
shall not be excteded when the leakage fates determined by the leakage integrity tests of these valves are added to the previously determined total for all valves and penetrations subject to Type B and C tests.
3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS i
3/4.6.2.1 CONTAINMENT SPRAY SYSTEM The OPERABILITY of the Containment Spray System ensures that containme;:
depressurization and cooling capability will be available in the event of a LOCA or steam line break. The pressure reduction and resultant lower containment ieakarle rate are consistent with the assumptions used in the safety analyses.
The Containment Spray System and the Contair.mant Cooling System both provide post-accident tooling of the containment atmosphere. However, the Containment Spray System also provides a mechanism for removing iodine from the containment atmosphere and therefore the time requirements for lastoring an inoperable Spray System to OPERABLE status have been naintained consistent with that assigned other inoperable ESF equipment.
2/4 6.2.2 SPRAY ADDITIVE SYSTEM ine OPERABILIT( of the Spray Addi*:ve System ensures that sufficient NaOH is added to the containment spray in tne event of a LOCA. The limits on NaOH volume and concentration ensure a pH value of between S.0 and 10.5 for the c!ution recirculated within containment after a LOCA. This pH Land minimizes the evolution ci iodine and minimizes the ef fect of chloride and clustic stress corrosion on mechanical systems anc components. The solution volaie limits (3700-4000 gallons) represent the required solution to be delivered (i.e., the del' m eu solution volume is that volume above the tanA discharge). Tnese assumptions are consistent with the iodine removal efficiency assumed in the safety analyses.
'GTLE UHTS - 1 & 2 E3 4 c-3 A