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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20138M5091997-02-13013 February 1997 Proposed Tech Specs Section 15.3.3. Re Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray ML20134L9791997-02-12012 February 1997 Proposed Tech Specs Re Relocation of Turbine Overspeed Protection ML20134A3661997-01-24024 January 1997 Proposed Tech Specs 15.5.4 Re Fuel Storage ML20134A3121997-01-21021 January 1997 Proposed Tech Specs 15.6.11, Radiation Protection Program ML20133N4021997-01-16016 January 1997 Proposed Tech Specs 15.3.2 Re Chemical & Volume Control Sys, 15.3.3 Re Emergency Core Cooling Sys,Auxiliary Cooling Systems,Air Recirculation Fan Coolers & Containment Spray & 15.3.8 Re Refueling ML20133N6321997-01-16016 January 1997 Proposed Tech Specs 15.1-6,15.2.2 Re Safety Limit,Reactor Coolant Sys Pressure,Ts 15.3.1-9,TS 15.3-10,TS 15.3.4-2 & TS 15.3.4-3 ML20133L1071997-01-13013 January 1997 Proposed Tech Specs 15.3.15 Re Overpressure Mitigating Sys & 15.3.1 Re Reactor Coolant Sys ML20133E5531997-01-0606 January 1997 Proposed Tech Specs 15.4.1, Operational Safety Review, Changing Ref Note 20 from TS 15.3.10.B to TS 15.3.10.E to Match TS Section Previously Containing Hot Channel Factor Limit ML20132F3471996-12-19019 December 1996 Proposed Tech Specs Improving Sections TS 15.3.10, Control Rod & Power Distribution Limits & TS 15.4.1, Operational Safety Review ML20132C3741996-12-12012 December 1996 Proposed Tech Specs Section 15.3.3 Re Eccs,Auxiliary Cooling Sys,Air Recirculation Fan Coolers & Containment Spray ML20135A8921996-12-0202 December 1996 Proposed Tech Specs 15.3.14 & 15.4.15 Re Fire Protection Sys ML20135A8431996-12-0202 December 1996 Proposed Tech Specs 15.3.10 Re Control Rod & Power Distribution Limits & 15.4.1 ML20129F2101996-09-30030 September 1996 Proposed Tech Specs Modify TS Section 15.3.3, Eccs,Auxiliary Cooling Sys,Air Recirculation Fan Coolers, & Containment Spray,To Incorporate Allowed Outage Times ML20129C0771996-09-19019 September 1996 Proposed Tech Specs Revising Section 15.3.15, Overpressure Mitigating Sys & Section 15.3.1, Rcs ML20117D2651996-08-22022 August 1996 Proposed Tech Specs Re Licensed Power Level for Plant ML20116N1341996-08-15015 August 1996 Proposed Tech Specs,Consisting of Suppl to Change Request 170,modifying TS 15.3.10, Control Rod & Power Distribution Limits & TS 15.4.1, Operational Safety Review ML20116G4891996-08-0505 August 1996 Proposed Tech Specs Modifying 15.2.3 & 15.5.3 of Change Request 188 & 15.2.1,15.2.3 & 15.3.1.G of Change Request 189 Supporting SEs ML20116D7471996-07-29029 July 1996 Proposed Tech Specs Re Health Physics Manager Qualifications for Plant ML20112F7341996-06-0404 June 1996 Proposed Tech Specs 15.2.3, Limiting Safety Sys Settings & Protective Instrumentation & 15.5.3, Design Features - Reactor ML20117K1991996-06-0404 June 1996 Proposed Tech Specs 15.2.1, Safety Limit,Reactor Core, 15.2.3, Limiting Safety Sys Settings,Protective Instrumentation & 15.3.1.G, Operational Limitations to Maintain Safety Margin for Unit 2 W/Replacement SGs ML20112E2441996-05-29029 May 1996 Proposed Tech Specs 15.1 Re definitions,15.3.6 Re Containment sys,15.4.4 Re Containment Tests & 15.6 Re Administrative Controls ML20108D1531996-04-29029 April 1996 Proposed Tech Specs Re Removal of Fire Protection Requirements ML20108A0011996-04-24024 April 1996 Proposed Tech Specs Section 15.7 RETS Re Removing Items Identified in GLs 89-01 & 95-10 as Being Procedural Details & Relocating Items to Appropriate Documents ML20149D9691996-03-20020 March 1996 Proposed Tech Specs,Providing Corrected Page to Bases for TS 15.3.1 ML20100L3891996-02-27027 February 1996 Proposed Tech Specs,Consisting of Change Request 186, Modifying TS Section 15.4.4, Containment Tests, Spec I.C.1 to State That Type a Tests Shall Be Conducted Per 10CFR50, App J Modified by Approved Exemptions 1999-08-04
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C0521999-10-0505 October 1999 Proposed Tech Specs 15.3.1.A,15.3.3.A & 15.3.3.C,eliminating Inconsistencies & Conflict Between TSs ML20210M6171999-08-0404 August 1999 Proposed Tech Specs 15.3.5,removing Word Plasma from Discussion of Type of Display Monitor for sub-cooling Info in CR & TS 15.3.7,removing Discussion That Allowed Delay in Declaring EDG Inoperable Due to OOS Fuel Oil Transfer Sys ML20210B5121999-07-15015 July 1999 Pbnp Simulator Four-Yr Rept ML20209C1831999-07-0101 July 1999 Proposed Tech Specs Page Re Amend to Licenses DPR-24 & DPR-27,removing Ifba Enrichment Curve Methodology from TS ML20205R6741999-04-12012 April 1999 Proposed Tech Specs Updating References to Reflect Relocation of Referenced Info in UFSAR ML20203A2261999-02-0202 February 1999 Proposed Tech Specs Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design ML20202F6521999-01-29029 January 1999 Proposed Tech Specs 15.6 & 15.7,reflecting Administrative Control Changes ML20154G5601998-10-0707 October 1998 Proposed Tech Specs Ensuring That 4 Kv Bus Undervoltage Input to Reactor Trip Is Controlled IAW Design & Licensing Basis for Facility ML20154H4231998-10-0505 October 1998 Proposed Tech Specs Section 15.4.1,removing Requirement to Check Environ Monitors on Monthly Basis ML20154C0561998-09-30030 September 1998 Rev 5 to Pbnp Units 1 & 2 IST Program Third 10-Yr Interval ML20154C1941998-09-28028 September 1998 Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels ML20153G7361998-09-23023 September 1998 Proposed Tech Specs Removing Explicit Testing Requirements of TS Section 15.4.13, Shock Suppressors (Snubbers) ML20206E2731998-08-26026 August 1998 Rev 11 to Pbnps Odcm ML20206E2681998-08-26026 August 1998 Rev 12 to EM Environ Manual for Wepc ML20236W7861998-07-30030 July 1998 Proposed Tech Specs Change 206,revising to Incorporate Changes to TS to More Clearly Define Requirements for Service Water Sys Operability ML20249C3811998-06-22022 June 1998 Proposed Corrected Tech Specs Pages Re Radiological Effluents ML20248C6651998-05-28028 May 1998 Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses ML20248G1671998-05-27027 May 1998 Proposed Edited Tech Specs Pages Adding CR & Condenser Air Ejector Radiation Monitor SR & Correcting Errors in Notes of Table 15.4.1-1 ML20203K9571998-02-26026 February 1998 Proposed Tech Specs,Revising Sections 15.3.6, Containment Sys bases,15.3.12 CREFS Including bases,15.4.4 Containment Tests bases,15.4.11 CREFS Including Bases, 15.6.8 Plant Operating Procedures & 15.6.12 ML20203K2981997-12-15015 December 1997 Proposed Tech Specs Re Administrative Controls ML20203K3081997-12-0808 December 1997 Rev 0 to Draft Radiological Effluent & Matls Control & Accountability Program ML20203K3231997-12-0202 December 1997 Rev 11 to Draft Odcm ML20203K3121997-12-0101 December 1997 Rev 12 to Draft Environ Manual Wisconsin Electric ML20203K3201997-11-25025 November 1997 Rev 0 to Draft Radiological Effluent Control Manual Wisconsin Electric ML20247P2681997-09-23023 September 1997 Proposed Tech Specs Implementing Boron Concentration Changes Re Planned Conversion of Unit 2 to 18-month Fuel Cycles ML20210M5151997-08-14014 August 1997 Proposed Tech Specs,Removing Requirement in Plant TS to Perform Pbnp Unit 2 Containment Integrated Leak Rate 60-months from Previous Test ML20210J0331997-08-0707 August 1997 Proposed Tech Specs,Replacing Wording & Double Underlining of Revised Wording ML20140C9111997-06-0303 June 1997 Proposed Tech Specs,Modifying TS Section 15.3.3, Eccs,Acs, Air Recirculation Fan Coolers & Containment Spray, to Incorporate AOT Similar to Ones Contained in NUREG-1431,Rev 1 ML20141C5931997-05-0909 May 1997 Proposed Tech Specs Section 15.3.3, Eccs,Acs,Air Recirculation Fan Coolers & Containment Spray to Incorporate Allowed Outage Times Similar to Those Contained in NUREG-1431,Rev 1 ML20140H0321997-05-0101 May 1997 Rev 5 to Training Programs Trpr 33.0, Licensed Operator Requalification Training Program ML20140H0171997-05-0101 May 1997 Rev 12 to Training Courses Trcr 86.0, Administrative ML20140G9811997-04-29029 April 1997 Assessment of Corrective Action Program Pbnp ML20140D7251997-04-14014 April 1997 Proposed Tech Specs,Changing Title of Corporate Officer Responsible for Nuclear Operations from Vice President- Nuclear Power, to Chief Nuclear Officer Per TS Section 15.6.2.1.c ML20140D7091997-04-14014 April 1997 Proposed Tech Specs,Eliminating Provisions for Operation of Units at Below 3.5% Rated Power W/Only One RCP ML20140G9241997-04-11011 April 1997 Rev 6 to ISTs IT 536, Containment Sump B Suction Line Leak Test (Refueling Shutdown) ML20140G9071997-04-0707 April 1997 Rev 8 to ISTs IT 525B, Leakage Reduction & Preventive Maint Program Test of 2SI-896A&B,SI Pump Suction Valves (Refueling) ML20140G8741997-04-0707 April 1997 Rev 35 to ISTs IT 04, Low Head Safety Injection Pumps & Valves (Quarterly) ML20217P2851997-04-0303 April 1997 Rev 10 to Point Beach Nuclear Plant,Units 1 & 2 Odcm ML20137N6451997-04-0202 April 1997 Proposed Tech Specs 14.2.4, Steam Generator Tube Rupture ML20140G9031997-03-21021 March 1997 Rev 8 to ISTs IT 325, CVCS Valves (Cold Shutdown) ML20140G9741997-03-21021 March 1997 Rev 0 to Operations Refueling Tests Ort 10A, Recovery from Integrated Lrt W/Core Off-Loaded ML20137C8331997-03-20020 March 1997 Proposed Tech Specs 15.2.2, Safety Limit,Reactor Coolant Sys Pressure ML20140G9621997-03-19019 March 1997 Rev 0 to Operations Refueling Tests Ort 9A, Preparation for Integrated Lrt W/Core Off-Loaded ML20140G9131997-03-17017 March 1997 Rev 4 to ISTs IT 535B, Leakage Reduction & Preventive Maint Program Test of Train B HHSI & RHR Sys (Refueling) ML20140G9521997-03-17017 March 1997 Rev 16 to Operations Refueling Tests Ort 6, Containment Spray Sequence Test ML20140G8821997-03-0404 March 1997 Rev 9 to ISTs IT 115, Instrument Air Valves (Quarterly) ML20140H3401997-02-28028 February 1997 WO Work Plan WO 9612073, Removal/Replacement of Breakers 1Y-06-11 ML20140H3011997-02-28028 February 1997 WO Work Plan WO 9612056, Removal/Replacement of Breakers 1Y-06-05 ML20140H3331997-02-28028 February 1997 WO Work Plan WO 9612072, Removal/Replacement of Breakers 1Y-06-01 ML20140H3241997-02-27027 February 1997 WO Work Plan WO 9612057, Removal/Replacement of Breakers 1Y-06-03 1999-08-04
[Table view] |
Text
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i Rov. 2 i PBNP DIESEL PROJECT DESIGN SUBMITTAL 1
7.2.3 Site Accentance Testiner Site Acceptance testing will be completed per ANSI /IEEE Std 387-1984 section 6.3
[
i and Reg. Guide 1.9 Rev. 3^ as follows:
- 1. Start Test
- 2. Load-Run Test
- 3. Fast-Ste.rt Tant ,
{
i
- 4. Loss-of-Offsite-Power (LOOP) Test
- 5. Safety-Injection-Actuation-Signal (SIAS) Test
- 6. Combined SIAS and LOOP Test ;
- 7. Single Load Rejection Test'
- 8. Full Lead Rejection Test s i
- 9. Endurance and Margin Test" ,
- 10. Hot Restart Test
- 11. Synchonizing Test
- 12. Protective Trb. <$ ass Test
- 13. Test Mode' Change ~0verfTestC l
- 14. Redundant Unit Test i
NOTES:
Compliance to Reg. Guide '.9 Fev. 3 is for the factory and site I A.
acceptance testing section only. Reg. Guide 1.9 Rev. 2 is used for l other portions of this work as outlined in Appendix D of this Design Summary.
B. These tests were successfully accomplished at the factory as indicated earlier. However, Wisconsin Electric will also perform l these tests during the site acceptance testing.
C. _ This ' test cannot ibe "accomplishedEas~ outlinedfin'. Reg Guide'X9 R0v 3 because of ; the design !cf . the control _ ' scheme. This.r test F will~ : be performed to. test the funetion'of the.controlfscheme aa designed.
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9407180171 94C711 PDR ADOCK 05000266 P POR 109 June 22, 1994 PBNP.WPF
Th e" bu s [t i e-bre ake fs'pec i fi c a t i on s' h a've"p ro vi s i on sith a t' t he; req u i red " red U nd sn t' decay heat remov61}:for. the shutdown unit:and the required; redundant. shared ,
engineered safeth feat'ures fore th'e?other unit"are . operable. Thef specification
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that'appliesonlyito:thedefueledcondition'does~'not.have:thelprovisionifor?the l requiredcredundant0d.ecay heat removalcforLthe? shutdown unit, citi has?provisi.oni foe verifying lthena'dequafytof-a ' single train of. spentyfuel pool coolingsindleu{off the consideration. of decay; heat removal, for_a reactor;inicold l shutdown #
The Point Beach DC electrical system has been modified so that each of the four main DC distribution buses, which are shared between the two units, has its own power supplies consisting of a safety-related station battery (DOS, D06, D105, D106) and a battery charger. In addition to these bus-specific power supplies, a swing safety-related battery (D305) is inetsited which is capable of being conr.ected to any one of the four main C4 distribution buses. Swing battery t chargers are also provided. Under cormal circumstances, one battery and one battery charger are connected in each main DC distribution bus. The battery charger normally shall be in service on each battery so that the batteries will always be at full charge in anticipation of a loss-of-AC power incident. Under unusual circumstances, two of the five safety-related batteries may be out of service for a limited period of time provided one of the two out-of-service batteries is returned to service within the time periods specified in ,
Specification 15.3.7.B.I.hi.. These limiting conditions for operation ensure that adequate DC power will always be available for starting the emergency generators and other emergency uses. !
The einergsncyidiesel;generatofsjaFe thef souFcesTofistandbylemergshcyfpowed The _
support systems necessary to be operable to ensure the operability of the emergency diesel generators (EDGs) are the EDG starting air system, EDG fuel oil system, EDG ventilat'on system, and EDG DC control power. Thelstind6f[~emefgency
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powe"r supply [ fort 4160 Volt and? associated"480TVolt1 safeguards bus consistsfor;is operable l EDG,lincluding all reqJired support systems;'and anloperable! output
~
brea.kerjtoithatL4160. Volt Lsafeguards bus. '
The LCOs' for theEstandby:smsrsency power supplies require the? redun' dint?stindby emergency; power supplies to beistarted within'24. hours:of: entry intoithese LCOs'.1
~
If the.' standby emergency power supply LC0~ is exited within:24t h'ours,Dthen starting of the redundant standby. emergency powerisupplies is not.~ required k:)lf.thelLCOLwas entered due to La standby,' emergency power supplylfailure'and..the:LC0fwaslexited within 24. hours, then an evaluation iaust bejompleted within 24~ hours of:entri into the LCO.to:-show that the)redundantTstandby poser; supplies areinotfsusceptib1d to1a common- cause failure or" the tredundant: standby emergency l power supplies must be started tolproveLthat'acommoncauselfailuredoes;not.existLwithinf24l hours.of entry into;thejlCO.
i The EDG starting air system is considered operable when 1) all three starting air bottles in each bank are operable, 2) the starting air banks can be maintained at a minimum pressure of 165 psig, 3) the air bank crossconnect valve is shut unless ,
i i
Unit 1 - Amendment No. 15.3.7-7 Unit 2 - Amendment No. I J
hank pressures are being equalized and an operator is statt . .i at the valve
.aring pressure equalization, and 4) all four starting air motors and their associated valves and relays are operable.
The EDG fuel oil system is considered operable when 1) 11,000 gal. of fuel oil is initially available in the emergency fuel oil.fstorage tank Mich[supplie.s to the diesel generators [Because the EDGs consume approximately 205 gallons of fuel per hour when fully loaded, the 11,000 gallon fuel supply in the emergency fuel tank provides sufficient fuel to operate one EDG at design load for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.], 2) the EDG day tank for;ithat}EDGI ;is;operabis and f6KG;0f[isd[G20 2[thj associated motor-operated fill valve are is operable, 3) for G-Ol[and;Gs02r at least one of the two base-mounted sump tank fuel oil transfer pumps is operable, and 4) the fuel oil transfer pump ' y;s stem associated with the EDG is operable.
However, both the fuel oil transfer pump: and- the4r :::cciatc 3 are system is allowed to be out of service for four hours for.p pipi 9.and G01 and;GIO2 due valve:
to a combined four-hour supply of fuel oil in the diesel base and day tanks which do not require a fuel oil transfer pump for flow to the associated EDG. Thelf651;:@l tFansfEFsystem1 s #al l ossd Vbs"66 tiolf[s;e FVi c eJfoF%o]Qu Fs[fo r[ G!0F an'd : G-04 due;to aitwo-hourj supplylof,fuello.il.! inf thej day.jtank. The pumps tran{ferbystem may be out of service for longer than four heues peri 6ds if an appropriate alternate source of fuel is made available to the diesel generators.
The EDG ventilation system is considered operable when diesel room temperature can be maintained $120'F with the diesel engine operating at full load. Temperature will be maintained $120 'F if 1) all gravity-operated louvers are operable, and
- 2) both diesel room exhaust fans are operable M forlG-Ollihd]GE02i one diesel room exhaust fan is operable and outside air temperature is 580'F.
Normal DC control power must energize all DC circuits for the associated EDG to be operable. -The following DC cireu-it cre requvred to be powered for the ::cciated ECC te be cencidered operable +
0 01 Circuit 0._02 918 20 Start 2 015 20 914-01 Centrcl 014-M D-12 11 St+et 1 01' 11 O!2 13 a.nnunc-4+ter Dl' 14 D11 28 Field Flash D13 28 Thel 6rigina[AEC Safei)TEValuationTfoFPBNPlstitesOO6s'itsif0b1}sf6ragi@apaQly islsufficient- forfajminimum :of seven . days
- operation'of{the requiped safety feature l loads which)isj accep. table."j - Therefors,ito satisfilthisire'quirementEst least:34,500 gallons ofj fuelfoil will be maintained availableTforf thelemergenci di.eseli generatorsfat PointiBeach at;all; times .when:EDG;operabilitylisirequiredj Unit 1 - Amendment No. 15.3.7-8 Unit 2 - Amendment No.
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