|
|
Line 54: |
Line 54: |
| 'cfm outside air intake. | | 'cfm outside air intake. |
| f."" After each complete or partial replacement of.a HEPA filter bank by verifying that the HEPA filter banks remove > 99il of the DQP when they are tested in-p'lace in accordance with ANSI | | f."" After each complete or partial replacement of.a HEPA filter bank by verifying that the HEPA filter banks remove > 99il of the DQP when they are tested in-p'lace in accordance with ANSI |
| . N510-1975 rate of 2000 cfm + 10!.., A | | . N510-1975 rate of 2000 cfm + 10!.., A while operating the ventilation system at a flow f |
| -
| |
| . '...
| |
| while operating the ventilation system at a flow f | |
| ~ | | ~ |
| : g. After each complete or partial replacement of a charcoa1 adsorber bank by verifying that th charcoal adsorbers remove | | : g. After each complete or partial replacement of a charcoa1 adsorber bank by verifying that th charcoal adsorbers remove |
|
---|
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
CONTAINMENT SYSTEHS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
- a. An overall integrated leakage rate of:=
- l. < La, 0.50 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P, (39.6 psig), or
- 2. < Lt, 0.32 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a reduced pressure of Pt, (19.8 psig).
- b. A combined leakage rate of < 0.60 La for all penetrations and valves subject to Type B and C tests as identified in Table 3.6-1 when pressurized to Pa.
- c. A combined leakage rate of < 0. 27 La for all penetrations identified in Table 3.6-1 as secondary containment bypass leakage paths when pressurized to Pa.
APPLICABILITY: NODES 1, 2, 3 and 4.
ACTION:
With either (a) the measured overall integrated containment leakage rate exceeding 0.75 La or 0.75 Lt, as applicable, or (b) with the measured combined leakage rate for aTl penetrations and valves subject to Types B and C tests exceeding 0.60 La or (c) with the combined bypass leakage rate
~
exceeding 0. 27 La, restore the leakage rate(s) to within the limit(s) prior to increasi ng the Reactor Coolant System temperature above 200'F.
SURVEILLANCE RE UIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972:
- a. Three Type A tests (Overall integrated Containment Leakage Rate) shall be conducted at 40 + 10 month intervals during shutdown at either Pa ( 39.6 psig) or at Pt ( 19.8 psig) during each 10-year ST. LUCIE - UNIT 1 3/4 6-2 4/18/80
CONTAINMENT SYSTBiS SUR'lEILLANCE REQU IRB1ENTS Continued) service period. The third test of each set shall be conducted during the shutdown for the 10-year plant.inservice inspection..
- b. If any periodic Type A test fails to meet either .75 L or .75 L, the test schedule for subsequent Type A tests shall b reviewed and approved by the Commission. If two consecutive Type A tests fail to meet either .75 L or .75 L , a=-Type A test shall be perform d at least every 18 mont~is until two con-secutive Type A tests me t either .75 L or .75 L at which time the above test schedule may be resumed.
- c. The accuracy of each Type A test shall be verified by a supplemental test which:
- l. Confirms the accuracy of the Type A test by verifying that the difference between supplemental and Type A test data is within 0.25 L or 0.25 Lt, a
2.. Has a duration sufficient to establish accurately the change in leakage between the Type A test and the supplemental test
- 3. Requires the quantity of gas injected into th containment or bled from the containment during the supplementa'1 test to be equivalent to at least 25 percent, of the total measured leakage rate at P- (39.6 psig) or Pt (19.8 psig).
a
- d. Type B and 'C tests shall be conducted with gas at P '39;6 psig) at intervals no greater than 24 months except for tests in-volving air locks..
- e. The combined bypass leakage rate shall be determined to be
< 0.27 L by applicable Type B and C tests at least once per 24 months except for penetrations which are .not individually testable; penetrations not individually testable shall be determined to have no detectable leakage when tested with soap bubbles while the containment is pressurized to P (39.6 psig) during each Type A test.
Air locks shall be tested and demonstrated OPERABLE per Surveillance Requirement 4.6.1.3.
ST. LUCIE - UNIT 1 3/46-3 4/18/80
0 V
PLANT SYSTEHS SURVEILLANCE RE UIREHENTS Continued)
- e. At. least once per 18 months by:
l.'erifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is < 4.15 inches Hater Gauge while operating the ventilation system a.t a flow rate. of 2000 cfm + 10/..
2.'erifying A
that on a containment i'solation signal or chlorine accident detection signal, the system automatically isolates the control room within 35 seconds and swi"tches into a recirculation mode. of operation with flow through the HEPA filters and charcoal adsorber banks.
- 3. 'eri,ying that the system maintains the control room at a positive pressure of > 1/8 inch H.G. relative to the outside atmosphere during system operation with <450
'cfm outside air intake.
f."" After each complete or partial replacement of.a HEPA filter bank by verifying that the HEPA filter banks remove > 99il of the DQP when they are tested in-p'lace in accordance with ANSI
. N510-1975 rate of 2000 cfm + 10!.., A while operating the ventilation system at a flow f
~
- g. After each complete or partial replacement of a charcoa1 adsorber bank by verifying that th charcoal adsorbers remove
> 99; of a halogenated hydrocarbon refrig rant test gas when they are tested in-place in accordance with ANSI N510-1975 while operating the ventilation system at a flow rate of 2000
+ 10/. 'fm ST. LUCIE - UNIT 1 3/4 7-23 4/1 8/80
SAFETY EVALUATIOH 0
Re." St. Lucie Unit.l;,'ocket No 50-335 Proposed Amendment Containment & Control Room Leakage I. Introduction This evaluation supports a proposal to (1) increase the combined leakage rate allowed for all penetrations identified as secondary containment by-pass leakaqe paths, and (2) increase the limit on outside air intake into the control room during the recirculation mode of operation. The sought after bypass leakage rate of 27'A was previously evaluated in Appendix 6B of the FSAR. The reevaluation discussed herein is based on a more conser-vative containment modeling technique. The current limit on control room outside air intake is based on the original control room post-LOCA habit-ability evaluation that is presented in FSAR section 15.4.1.2.5(d). The evaluation did not take credit for the operation of the "backfitted" Iodine Removal System (IRS) and Shield Building Ventilation System (SBVS) heaters. The reevaluation discussed below uses the same control room models and assumptions presented in the FSAR in addition to the operation of the "backfitted" systems.
II. Discussion The St. Lucie Unit 1 calculations estimating whole body and thyroid doses from a postulated loss of coolant accident (LOCA) have been revised. The revised analysis uses a more conservative containment release model. The analysis was previously presented in Appendix 6B of the FSAP, and was based on a single volume well-mixed containment activity release model as well as the "backfit", containment bypass fraction of 27K. The difference between the FSAR analysis and the analysis described herein is that a more conser-vative two compartment containment model is used that takes into account the difference in iodine scrubbing effectiveness between the regions of the con-tainment that receive or do not receive spray coverage. The volume of the containment atmosphere that is sprayed is conservatively assumed to be 86/.
i'lixing is assumed to occur between the sprayed and unsprayed regions at a rate of 4 volumes of unsprayed region per hour. The only other change in assumptions from those presented in Appendix 6B of the FSAR is that it takes 44 minutes for the sprays to reduce the elemental iodine concentration in the containment by the allowable factor of 100 rather than the previous period of 28 minutes. The removal of particulate iodine by the sprays is terminated at 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The pH of the sodium hydroxide solution at the spray nozzle will be between 8.5 and ll. The revised offsite LOCA doses are pre-sented in Table l. Although the revised thyroid doses for both the exclu-sion zone boundary and low population zone are somewhat higher because a more conservative model was used, they are still well within the 300 rem limit set by 10 CFR 100 for the reactor siti ng cri teria.
In the process of developing revised offsite LOCA dose calculations, it was determined that Technical Specification leak testing criteria could be made less stringent. The current Specifications set a 12" limit on unfiltered
,0 0 SAFETY EVALUATION (Continued) secondary containment bypass leakage and a 100 CFH limit on Control Room in-leakage. The revised LOCA analysis discussed above justifies a containment bypass leakage of up to 27% and a control room inleakage of up to 450 CFH.
The LOCA doses presented in Table 1 are based on a bypass leakage of 27'A and the more conservative containment model. All other FSAR assumptions have been retained, The revised 30 day post-LOCA control room doses are presented in Table 2 and are compared to those presented in the FSAR. The control room dose model used in the reelevation is identical to the model described in chap-.
ter 15 of the FSAR. The only change in assumptions is that the IRS and SBVS heat "backfits" have been incorporated and the containment bypass leakage in-creased to 27~ value. Control room inleakage is conservatively limited to 450 CFH. This maximum value of inl eakage, plus the Control Room air conditioning System, assures that the relative humidity of the air at the inlet of the con-trol room's charcoal filters is less than 70/, Relative humidity must be main-tained below this value in order that the assumed charcoal efficiencies presen-ted on FSAR page 15.4.1-20d can be obtained.. The effect of a postulated chlo-rine release on the control room habitability was also reevaluated. The chlorine release evaluation illustrated a value for inleakage of 568 CFtl which is above the limitation imposed by the relative humidity requirements.
III. Conclusion Me have concluded, based on the considerations discussed above, that: (1) the amendment does not involve a significant increase in the probability or con-sequences of accidents previously considered and does not involve a significant decrease in a safety margin, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Com-mission's regulations and the issuance of this amendment will not be inimical to the common defense and securi ty or to the health and safety of the public,
TABLE I REEYALUATION OF FSAR OFFSITE LOCA DOSES FOR 27'A SHIELD BUILDING BYPASS LEAKAGE
~FSAR *~ANENDt1ENT 2 Hour Thyroid- Dose at 1555 Meters (EZB) 66 rem 75 rem 2 Hour Mhole Body Dose at 1555 fleters (EZB) 4 rem 4 rem 30 Day Thyroid Dose at 1609 tIeters (LPZ) 150 rem 167 rem 30 Day i<hole Body Dose at 1609 Meters (LPZ) 5.5 rem 6 rem
- Post Iodine removal systems backfit case per FSAR Appendix 6B with addition-al calculational conservatisms as noted in text.
TABLE II REEVALUATION OF FSAR CONTROL ROOM LOCA DOSES FOR THE POST IODINE REMOVAL'YSTEMS BACKFI'T CASE LIITH 450 CFM INLEAKAGE "FSAR'0
- At1EIIDMENT Control Room Thyroid Dose rem 12.5 rem Control Room (!hole Body Dose 1.7 rem 3.0 rem Control Room Skin Dose 17.8 rem 27.0 rem
- FSAR case at page 15.4.1-20d with no credit for iodine removal system backfits and 100 CFM control room inleakage.
~*Post iodine removal systems backfit case with additional calculational conservatisms as noted in text and 450 CFM control room inleakage.
STATE OF FLORIDA )
) ss COUNTY OF DADE )
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florid'a Power 5 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document -on behalf of said Licensee.
Robert E. Uhrig t
Subscribed and sworn to before me this
~SCIBQ Or A i l~
NOTARY PUBLX , in and for the county of Dade, State of Florida Notary Pubgc, State ot Florida at Largo My Commis"'on Expires October 30, >>1983 lory COmmiSSiOn eXpireS: ~ended tbru Maynard Eonding Agency
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