Proposed Tech Specs,Changing Table 3.6-1, Containment Leakage Paths & Table 3.6-2, Containment Isolation Valves.ML17308A429 |
Person / Time |
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Site: |
Saint Lucie ![NextEra Energy icon.png](/w/images/9/9b/NextEra_Energy_icon.png) |
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Issue date: |
08/25/1987 |
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From: |
FLORIDA POWER & LIGHT CO. |
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To: |
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Shared Package |
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ML17308A428 |
List: |
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References |
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NUDOCS 8709010080 |
Download: ML17308A429 (20) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17228B5041996-06-0101 June 1996 Proposed Tech Specs Re Thermal Margin & RCS Flow Limits ML17228B3761996-01-0404 January 1996 Proposed Tech Specs Rectifying Discrepancy for Each St Lucie Unit & Providing Assurance That Admin Controls for Hpsip Remain Effective in Lower Operational Modes ML17228B3361995-11-22022 November 1995 Proposed TS 3/4.4.6.1 for RCS Leakage Detection Instrumentation,Adapting STS for C-E Plants (NUREG-1432) Spec 3.4.15 ML17228B2451995-08-16016 August 1995 Proposed TS 3.6.6.1, Sbvs. ML17228B2421995-08-16016 August 1995 Proposed Ts,Reflecting Relocation of Selected TS Requirements Re Instrumentation & Emergency & Security Plan Review Process,Per GL 93-07 ML17228B1891995-06-21021 June 1995 Proposed Tech Specs Re Safety Injection Tank Surveillances ML17228B1811995-06-21021 June 1995 Proposed Tech Specs Re Time Allowed to Restore Inoperable LPSI Train to Operable Status ML17228B1791995-06-21021 June 1995 Proposed Tech Specs Re Extended Allowed Outage Time for EDGs ML17228B1471995-05-17017 May 1995 Proposed Tech Specs,Extending Applicability of Current RCS Pressure/Temp Limits & Maximum Allowed RCS Heatup & Cooldown Rates to 23.6 Effective Full Power Yrs of Operation ML17228B1441995-05-17017 May 1995 Proposed Tech Specs Re Administrative & Conforming Update ML17228B0901995-04-0303 April 1995 Proposed Tech Specs Re Incorporation of line-item TS Improvements to TSs 3/4.8.1 & 4.8.1.2.2 for Licenses DPR-67 & NPF-16 ML17228B0591995-02-27027 February 1995 Proposed TS Re Sdcs Min Flow Rate Requirements ML17228B0521995-02-27027 February 1995 Proposed Tech Spec Tables 3.3-3 & 3.3-4 to Accommodate Improved Coincidence Logic & Relay Replacement for 4.16 Kv Loss of Voltage Relays ML17228B0331995-02-22022 February 1995 Proposed TS 4.6.1.3,reflecting Deletion of Refs to Automatic Tester for Containment Personnel Air Lock ML17228A9921995-01-20020 January 1995 Proposed Tech Specs,Relocating Operability Requirements for Incore Detectors to (TS 3/4.3.3.2) to Updated FSAR & Revising Lhr Surveillance 4.2.1.4 & Special Test Exceptions Surveillance 4.10.2.2,4.10.4.2 & 4.10.5.2 ML17228A9031994-11-0202 November 1994 Proposed Tech Specs 3/4.6.2.1 & 3/4.6.2.3,adapting Combined Spec for Containment Spray & Cooling Sys Contained in Std TS for C-E Plants ML17228A8911994-10-27027 October 1994 Proposed Tech Specs,Incorporating Administrative Changes ML17228A6521994-07-28028 July 1994 Proposed Tech Specs Re LTOP Requirements for Power Operated Relief Valves,Per GL 90-06 ML17228A6591994-07-25025 July 1994 Proposed Tech Specs Implementing Enhancements Recommended by GL 93-05, Line-Item TS Improvements to Reduce SR for Testing During Power Operation. ML17228A6561994-07-25025 July 1994 Proposed Tech Specs for Main Feedwater Line Isolation Valves to Be Consistent w/NUREG-1432,standard TS for C-E Plants ML17228A5771994-05-23023 May 1994 Proposed Tech Specs Removing Option That Allows HPCI Pump 1C to Be Used as Alternative to Preferred Pump for Subsystem Operability 1999-06-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0441999-03-0202 March 1999 Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A6751998-03-27027 March 1998 Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17309A9171997-11-26026 November 1997 Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A0951996-10-24024 October 1996 Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage. ML17229A0861996-10-18018 October 1996 Startup Physics Testing Rept. W/961018 Ltr ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17229A0961996-06-12012 June 1996 Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. 1999-06-30
[Table view] |
Text
{{#Wiki_filter:ATTACHMENT I Marked-up Technical Speci fication Pages:
3/4 6-5 3/4 6-6 3/4 6-7 3/4 6-8 3/4 6-2I 3/4 6-22 E JW2/0 I 3/2 8709010080 870825II PDR ADOCK 05000335 P PDRQ I
II L'
l, C
II
v-v-~S~NA Penetration 7
10 System c . rr Makeup Water Stat1on Air Instrigent'hir Conta1nment .
r>"3ZS)
Valve Check (,
Gl obe Gate a
Gate,.(I,;1 Numbe 5-1 TABLE
,-..
};:~'..
LI-V-18-947}...Outside Gl obe .(1-.'V -1 (IW-18 1Z M.te.a!R 3.6-1 CONTAINMENT LEAKAGE PATHS
<,
to Containment 8-947.j,.'.:. Outstde Butterfly (I-'FGY'45-4}
Location Outside inside Outside I-td.
Inside Service primary Makeup Mater Station Air Supply P
instrument Air Supply Containment Purge Test T~e~
Bypass Bypass Bypass Type C Purge Butterfly (I-FCV-25-5} . Exhaust Outside'utterfly Conta1reent (I-.FCY-25-3}. "
Inside. Containment Purge Type C
. Butterfly.~-.FCV'<<:25-2)
Purge; Outs1de Supply Haste ','Globe .{V-6741 j.:, Outside Nitrogen supply to Bypass Management:-- Check .(V'-'6779 j: S?. Tanks Component
'utside'utterfly.{7+GV-14-7}
Outside. RC Pump CM supply .
Bypass.
Cooling Butterfly. (I-BCV-.14-1 } Outside.
Component Butterfly (IQCV-14-6j Outside RC Pump CM Return Bypass Cooling Butterfly (I'4CV-14-2 j Outside Fuel Transfer Double Gasket Flange Inside Fuel Transfer Bypass Tube 26 CVCS GloBe (V 451 5)" Inside Letdown Line Bypass O Globe .(V -2516}: 'ns1de 28 Sampling Globe V -520D} ',- Outside Reactor Coolant Bypass Globe V -.52a3} Outside Sample Globe I-FCV43-1E}. Outside SI Tank Sample Bypass Globe I-FC)43-1F} Outside SI Tank Sample
4 1
'lg
TABLE 3.6-1 Continued Location Test Penetrat1on ~S stem Valve Ta Number to Containment Service ~Te+
29 Sampling Globe (V-5202) Outside Pressurizer Steam Bypass rn Globe (Y-5205) Outside Space Sample I
5 Sampling Globe V-5201) Outside 'ressurizer Surge Bypass
~ ~
Globe V-5204) Outside Line Sample 31 Haste Gate V-6554) Outside Containment Vent Bypass Management Gate V-6555) Outside jieader g- v- 07oo9 Safety Injection Gate (Y-3463) Outside Safety Injection Tank Tank Test Lines ll Outside Fill and Sampling Bypass Ca>
Haste Gate I-LCV-07-11A) Outside Reactor Cavity Sump Bypass We Vl
{management Gate I-LCV-07-11B) Outside Pump Discharge I
Ch 43 Haste Gate (V-6301) Outside Reactor Drain Tank Bypass
{management Gate (V-6302) Outside Pump Suction CVCS Gate (V-2505) Outside RC Pump Controlled Bypass Gate (I-SE-01-1) Inside Bleedoff Fuel Pool Gate (I-V-07-206) Outside Refueling Cavity . Bypass Cleanup Gate (I-V-07-189) Inside Purification Flow Inlet Fuel Pool Gate (I-V-07-170) Outside Refueling Cavity Bypass Cleanup Gate (I-V-07-188) Inside Purification Floe z-Fsb-a7-i,z,> ~
Outlet Sampling Gl l Inside {{2 Sampling Type C
~+)
Globe ( ) Outside 7 -ggf-27-5
II TABLE 3.6-1 Continued Location Test k(~
Penetration ~S stem Valve Ta Number to Containment Service e*
.Samplin Globe (I-FSE-27-1 1 ) Outside H2 Sampling Type C ~
lac 2- v-27(ol kh Inside 51 Sampling Globe (I-FSE-27-5,6,7) Inside H2 Sampling Type C k(~
Sle Globe ( I-FSE-27-9) Outside 51 Samplin Globe (I-FSE-27-10) Outside H2 Sampl ing Type C s.i a. p7/02 kk Inside"
'
52a Sampling Ga te I-FCY-26-1) Inside Radiation Bypass Gate (I-FCV-26-2) Outside Monitoring 52b Sampling Gate (I-FCY-26-3) Inside Radiation Bypass Gate I-FCV-26-4) Outside Monitoring 52c Sampling Gate (I-FCV-26-5) Inside Radiation Bypass Gate I-FCY-26-6) Outside Monitoring Return 52d ILRT -Gate-( I-V00140 Inside ILRT Test Tap Bypass glo (I V00143 Outside
~
C.
52e ILRT Qlo~ (I-V0013g Inside ILRT Test Tap Bypass (I-V00144 Outside ILRT glo Blind Flange
~( ~ gable Inside ILRT Pressure ~
Bypass Gate (I-V00101 Outside Connection (I~-1-'H - g-2$-Il 56 - Containment Gate . Outside Hydrogen Purge Outside Bypass H2 Purge Gate (~i-R) >-" ~
Outside Air Makeup 57 Containment Gate (A%33) X-~->< 13 Outside Hydrogen Purge Exhaust Bypass H2'Purge Gate 4-RS-14 7= v m-iy Outside
~ . ~ .sC TABLE 3.6-1 Continued Location Test Penetration ~S stem Valve Ta Number to Containment Service ~Te*
58 Containment Purge Gate Gate
(~~)
(4-t!~)
+
- ~-~~
~ Outside
'utside Hydrogen Purge Exhaust Bypass H2 67 Vacuum Check (I-V-25-20) Inside Containment Type C Relief Butterfly (I-FCV-25-7) Outside Vacuum Relief 68 Vacuum Check (I-V-25-21) Inside Containment Type C Relief Butterfly (I-FCV-25-8) Outside Vacuum Relief Personnel W.A. None N.A. Ingress E Egress Type'**
Lock to Containment Escape N.A. None N.A. Emergency Ingress 5 Type 8*~
Lock Egress to Containment Maintenance N.A. None N.A. Vessel Maintenance Type B
)latch 4r]A>)
cd (Gasket Or 8 peM p~~geaa5
~
Interspace)
Electrical 'N.A. All primary canisters N.A. Electrical Type 8 Penetrations except welded spares connections in PCY 1 Hain Steam Steel Tap 1 Outside Expansion Bellows Type 8 Containment Tap 2 Outside
. Nozzles Main Steam Steel Tap 1 Outside Expansion Bellows Type 8 Containment -Tap 2 Outside Nozzles Feedwater Steel Containment Nozzles 'ap Tap 1 2
Outside Outside Expansion Bellows Type 8
TABLE 3.6-2 Continued Penetration Valve Ta Number Number Function ~tl tt Testable During tt Isolation tt t B. HANUAL OR REHOTE HANUAL
- l. I-V-18-947 Station air supply, Hanual Yes
- 2. I-V-25-11,12 56 Hydrogen purge outside air make- Yes up, Hanual (NC)
- 3. I-V-25-13,14, 57 8 58 Hydrogen purge exhaust, Manual Yes NA 15,16 (NC)
- 4. V-3463 4.1 Safety injection tank test line, Yes Hanual (NC)
+- I-g 70 0 9
- 5. MM 41 Safety injection tank test line, Yes NA" Hanual (NC)
- 6. V-07206, V-07189 46 Refueling cavity purification flow Yes inlet, Ha>>ual (NC)
- 7. V-07170, V-07188 Refueling cavity purification flow g80. outlet, Hanual (NC) 8.
9.
I-FSE-27-1,2,3, 4,8, 9
(0 lf .
I-FS 5,6,7; a la
- ]Sin'es VS~ Hydrogen sampling Hydrogen sampling manual line, line, Remote Remote
'anual Yes Yes
'j)~" ~'vp} ~
,s '<+a'
~
TABLE 3.6-2 Continued Penetration Testable Ouring Is6lation Valve Ta Number Number Function Plant 0 eration ~Time Sec
- 10. I-FCV-26-1 81'2 52a Radiation monitoring Yes NA ll. I-FCV-26-3 8 4 52b Radiation monitoring Yes NA
- 12. I-FCV-26-5 8 6 52c Radiation monitoring, return Yes
- 13. I-V00140(%8@- 52d ILRT test tap Yes I-V00143
- 14. I-Y00139~~ ~ 52e ILRT test tap Yes I-V00144~~~
- 15. I-V00101~+ 54 ILRT pressure connection Yes NA
- 16. I-FCV-03-1E 8[ 1F 28 SI Tank Sample Yes NA%*
NA - Manual Valve-Isolation time not applicable.
- May be opened on an intermittent basis under administrative control.
** Normally closed valves - Isolation time not applicable.
a
ATTACHMENT2 SAFETY EVALUATION Introduction As a result of continuing review of the St. Lucie Unit I Technical Specifications by Florida Power 6 Light Company (FPL), incorrect and incomplete valve and penetration numbers were found to be listed in Table 3.6-l, "Containment Leakage Paths" and Table 3.6-2, "Containment Isolation Valves" of the St. Lucie Unit I Technical Specifications.
Discussion Review of the St. Lucie Unit I Technical Specifications by FPL found several incorrect valve numbers, valve types and penetration numbers listed in Table 3.6-I, "Containment Leakage Paths" and Table 3.6-2 "Containment Isolation Valves" of the St. Lucie Unit I Technical Specifications. The proposed valve number and type and penetration number changes are administrative/editorial in nature. This proposed change is intended to ensure that the Technical Specifications reflect actual valve number, proper valve type and penetration numbers and as-built configurations for electrical penetrations installed in St.
Lucie Unit I. Some valve numbers currently listed in the Technical Specifications reflect generic valve numbers and not the specific valve tag numbers.
Additionally, several valve tag numbers do not include the seismic qualification identifier or are shown as incorrect valve types. Certain penetrations lack the alphabetical identification that should be listed in addition to the numerical identification. Also, a change to the electrical penetrations valve tag number descriptions is proposed to clearly specify electrical penetrations which require periodic leak testing.
The proposed changes are listed below:
~3/4 6-5 Penetration 7, Valve Ta Number Check (I-V-l5-I347) should read Check (I-V-l5328)
Penetration 9, Valve Ta Number Check (I-V-I8-957) should read Check (I-V-I8 I 95)
- 3. ~3*3/4 6-Penetration 4I, Valve Ta Number Gate (I-V-03-I307) should read Gate (I-V-07009)
Penetration 48 should read 48a, Valve Ta Number Globe (I-FSE-27-0I,02,03,04) should read Globe (I-FSE-I,2,3,4)
Globe (I-FSE-27-08) should read Globe (I-FSE-27-8)
- 3. ~PP/4 6.7 Penetration 48 should read 48c, Valve Ta Number E JW2/0 I 3/3
V 4
4 ll 4 I
I fl I. ~ '
4
~ ~
I'I
~ 4 If ~
4
~ VI It 4 II 4% ~
4 I ~ 4 I
4 ~ 4 I 4 I lll,
'4 4 4
If 44 4 I ~
~ ~ I" O' II I ~ f V
4 "4
Check (lE-27-1341)
(
s 1/
P
/
should read Check (I-V+
01)
First Penetration 51 should read 5lc Second Penetration 51 should read 5la, Valve Ta Number Check (I-FES-27-1342) should read Check (I-V-27102)
Pent ration 52d, Valve Ta Number Gate (I-V00140(1325)) should read Globe (I-V00140)
Gate (I-V00143(1325)) should read Globe (I-V00143)
Penetration 52e, Valve Ta Number Gate (I-V00139(1322)) should read Globe (I-V00139)
Gate (I-V00144(1322)) should read Globe (I-V00144)
Penetration 54, Valve Ta Number Gate (I-VOOI 0 I (612)) should read Gate (I-VOOI 0 I')
Penetration 56, Valve Ta Number Gate (V-25-11) should read Gate (I-V-25-11)
Gate (V-25-12) should read Gate (I-V-25-12)
Penetration 57, Valve Ta Number Gate (V-25-13) should read Gate (I-V-25-13)
Gate (V-25-14) should read Gate (I-V-25-14)
- 4. ~P3/4 -3 Penetration 58, Valve Ta Number Gate (V-25-15) should read Gate (I-V-25-15)
Gate (V-25-16) should read Gate (I-V-25-16)
Penetration Electrical Penetration, Valve Ta Number "All primary canisters except welded spares" should read "All primary canisters and flanged electrical penetrations except welded spares."
- 3. ~P*3/4 3-21 Valve Ta Number B.5.
I-V-03-1307 should read I-V-07009 Valve Ta Number B.8.
I-FSE-27-1,2,3,4,8,10 should read I-FSE-27-1,2,3,4,8,11 Penetration 48 should read 48a & 48c Valve Ta Number B.9.
E JW2/013/4
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I-FSE-27>>7,9,11 should read I-FSE-27-5,6,7>> 0 Penetration 51 should read 51a 8 51c
- 6. ~P3/4 6-2 Valve Ta Number 13.
I-V00140 (1325) should read I-V00140 I-V00143 (1325) should read I-V00143 Valve Ta Number 14.
I-V00139 (1322) should read I-V00139 I-V00144 (1322) should read I-V00144 Valve Ta Number 15.
I-VOOI 0 I (612) should read I-VOOI 0 I E JW2/013/5
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ATTACHMENT3 DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The standards used to arrive at a determination that a request for amendment involves no significant hazards consideration are included in the Commission's regulations, IO CFR 50.92, which states that no significant hazards considerations are involved if the operation of the facility in accordance with the proposed amendment would not (I) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated or (3) involve a significant reduction in a margin of safety. Each standard is discussed as follows:
(I) Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change corrects valve tag and penetration numbers found to be incorrectly or incompletely listed in the St. Lucie Unit I Technical Specifications Table 3.6-I "Containment Leakage Paths" and Table 3.6-2 "Containment Isolation Valves". Since no change to the facility is proposed, the probability or consequences of an accident previously evaluated would not increase.
(2) Use of the modified specification would not create the possiblity of a new or different kind of accident from any accident previously evaluated.
The proposed change corrects incorrectly or incompletely listed valve and penetration numbers in Table 3.6-I "Containment Leakage Paths" and Table 3.6-2 "Containment Isolation Valves". This administrative/editorial change will not create the possibility of a new or different kind of accident from any accident previously evaluated.
(3) Use of the modified specification would not involve a significant reduction in a margin of safety.
The proposed change involves correcting valve tag and penetration numbers which are currently incorrectly or incompletely listed in Table 3.6- I "Containment Leakage Paths" and Table 3.6-2 "Containment Isolation Valves" of the St. Lucie Unit I Technical Specifications and will not reduce the margin of safety.
Based on the above, we have determined that the amendment request does not (I) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the probability of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in a margin of safety; and therefore does not involve a significant hazards consideration.
E J W3/013a/3
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