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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] |
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EEMERGENCY COOLING
- . .7
- 1. 2c 3 4~ 'S OPERATOR ACT10 0
' NO. 0F; MIN.- .
MINIMUM PERMISSABLE IFECONDITIONS OF
- COLUMN 3 OR 4
$$. NO. OF
- CHANNELS CHANNELS OPERABLE.- DEGREE OF-
- TO-TRIP ~ CHANNELS- . REDUNDANCY" CONDITIONS
' BYPASS CANNOT BE MET:
i NO. FUNCTIONAL'bMIT 3G 1. SAFETY INJECTION Hot- Shutdown ***
o- ' l1. 1 1 Manual. 2 ,
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2 2 1-Hot Shutdown ***
$$ b. High Containment Pressure :3 ~
oo Hot Shutdown ***'
2 2 -1 Primary Pressure is im8Ec. Steam Generator low Steam J3 Less Than 1800 psig
~
8,y0 Pressure / Loop- '
o-Primary Pressure'is Hot Shutdown ***-I ;
- d. Pressurizer low Pressure 3 '2 2 'l
.Less Than 1800 psig j
- 2. CONTAINMENT SPRAY 2 2
- ** Hot Shutdown ***-
M 1 2
.-2 of:3 2 per -1/ set Hot Shutdown ***
- b. Hi-Hi Containment Pressure 2-sets (Containment Spray) of 3' 'inLeach- set .
' set.
- 3. AUXILIARY FEEDWATER
- a. Low-Low Steam Generator Water Hot Shutdown ***~
- i. Start Motor Driven Pump 3/ steam 2/either 2/ steam 1 gen. : gen. gen.
1 Not Shutdown ***
2/both ii. Start Turbine Driven 3/ steam 2/ steam Pump gen. .; gens. gen.
1/ Main- 1/ Main- 1- Turbine Power
- b. Trip of Both Main Feedpumps 2/ Main-' : channel to operable.
feed feed feed Less Than 40%'
Starts Both' Motor Driven
~
pump pump -pump status in.48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or*
Pumps and Turbine Driven- . reduce power to less-
~
Pump than 40% within~6 hours.
a-Unit 1 - Amendment No.
Unit 2 Amendment'No. Page 1 of 2:
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1 TABLE 15.3.5-3
- . ~
. EMERGENCY COOLING 1
2 '3 4 5 OPERATOR ACTION 4
. ~ NO. 0Fi MIN. - MINIMUM PERMISSABLE IF CONDITIONS OF-NO. OF ~ CHANNELS OPERABLE DEGREE OF BYPASS COLUNN.3 OR 4:
1NO. FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS -REDUNDANCY CONDITIONS CANNOT BE MET
- 3. AUXILIARY FEEDWATER (Continued) 4
- c. Undervoltage on 4KV: Buses 2/ bus 1/ bus- 1/ bus --' -
Hot' Shutdown ***
- i. Starts Turbine Driven-Pump
- d. Safety Injection; Signal S.I. INITIATING FUNCTIONS AND REQUIREMENT'AS IN 1 ABOVE Starts Motor Driven Pumps
- =
I 4. SAFETY-RELATED ELECTRICAL BUSES
- a. Degraded Voltage (4.16KV) 3/ bus 2/ bus 2/ bus 1/ bus ****
- b. Loss of Voltage (4.16KV) 2/ bus 1/ bus 1/ bus 1 ****
- c. Loss of Voltage (480V) 3/ bus .2/ bus- 2/ bus 1 Hot Shutdown ***
- - Turbine power as derived from the turbine first.st' age impulse pressure. I
- - Must activate 2 switches simultaneously.
C** -
If minimum conditions are not met within 24-hours-after reaching hot' shutdown, the unit shall be.in cold shutdown within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of the event causing the unit shutdown.
- * - Normal operation provided both diesel generators are available and the associated diesel generator is operating and providing power to the affected safeguards bus. If minimum conditions are not met within 7 days,-the' affected unit shall be placed in hot shutdown.
Unit 1 Amendment No.
Unit 2 Amendment No. Page 2 of 2
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ETABLE 15.3.5-51 3~ A
[ INSTRUMENT OPERATING CONDITIONS FOR INDICATIONS. -.
i 1- 2 3 MINIMUM ~
' NO. OF- . OPERABLE OPERATOR ACTION IF CONDITIONS.
NO.: FUNCTIONAL UNIT CHANNELS CHANNELS OF COLUNN 2 CANNOT BE MET
-1. PORV Position' Indicator 1/ Valve- 1/ Valve If the operability of the PORY position-indicator cannot be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, shut the 3 associated PORV Block Valve.
- 2. PORV Block Valve Position 1/ Valve. 1/ Valve If the operability of the'PORY Block Valve Position Indicator Indicator cannot be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, shut'-
and verify the Block-Valve shut by direct obser-vation or declare the Block Valve inoperable.
- 3. Safety Valve Position Indicator 2/ Valve' 1/ Valve if the operability of a Safety Valve Position 1 l:
Indicator cannot be restored within seven days, be i'. at least Hot Shutdown within-the next l 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. ,
- 1.
l
- 4. Reactor Coolant System Subcooling 2 1 If the operability of a subcooling monitor cannot be restored or a backup monitor made lI i l functional within'48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, be in at least l Hot. Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 5. Auxiliary Feedwater Flow Rate
- 1 ~1 If the operability of the auxiliary feedwater flow rate indicator car.not be restored within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, be in hot' shutdown within 12.. hours.
- 6. Control Rod Misalignment as 1 1 Log individual rod positions once/hr., after a Monitored by On-Line load change >10% or after >30 inches of control Computer rod motion.
0 Applies to presently-installed combination of auxiliary feedwater pump discharge flow indicators and auxiliary feedwater :
flow to steam generator indicators. ~
Unit 1 Amendment No.
i Unit 2 Amendment No.
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- Specification.15.3.0.C delineates additional conditions which must be satisfied to permit operation to continue, consistent with the Limiting l Cchcitit.rJ for Operatier stitsunts for power sources, when a nontal or emerger.cy power source is not operable, it specifically prohibits operation when one system, subsystem, train, component or device is inopersle because its nonnal or emergency power source .is inoperable and a redundant system,' subsystem, train, component or device is inoperable for another reason.
The provisions of this specification permit the action statements associated with individual systems, subsystems, trains, components, or devices to be consistent:
with the action statements of the associated electrical power source. It allows operatior te be governed by the time limits of the action statement associated
~with the Limiting Condition for Operation-for the normal or emergency power source, not the individual action statements for each system, subsystem, train, component or device determined to.be inoperable solely because of the inoper-ability of its normal or emergency power source.
For examp.le, Specification 15.3.7.B.1.e allows a 7 day out-of-service time .l for one: emergency diesel generator. If the definition of operable were applied
' without consideration of Specification 15.3.0.C., all systems, subsystems,
. trains ' components or devices supplied by the inoperable emergency power source wo'uld'also be inoperable. This would invoke the applicable action statements for
.each of the applicable LCO. .However, the provisions of Specification 15.3.0.C permit the. time limits for continued operation to be consistent with the state-unt for the inoperable emergency diesel generator instead, provided the other specifie{conditior.s are satisfied. In this case, the corresponding normal' power source.must be operable, anc all redundant systems.: subsystems, trains. -components,
,' and devices 'must be operable. or otherwise satisfy Specification 15.3.0.C (i.e.,
be' capable of performing their design function and have:at 1 east one normal or one emergency power source operable). If these conditions are not satisfied.
shutdown is required in accordance with Specification 15.3.0.A.
1
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t i Unit 1 Amendment No. 15.3.0-3 1 Unit 2 Amendment No, a w I
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,).- dates l accommodate the weld data-needs;of_all the participants in the Babcock and
+' - Wilcox Master Integrated Reactor' Vessel Surveillance. Program. Additionally, the1 schedule:will- provide plate / forging material data as well' as fluence data: isj
. corresponding to:the expiration of the current licenses'and of.any future 11icense extensions.-
.1 Re'ferences=
-(1) FSAR,'Section 4.1.5
'(2) Westinghouse Electric Corporation, WCAP-10638 '!
-(3) Westinghouse Electric' Corporation, WCAP-8743 (4) Westinghouse Electric Corporation,'WCAP-8738 4
.(5) Babcock & Wi1cox, BAW 1803L (6);RegulatoryGuidel.99, Revision 2 .,
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-Unit 1 Amendment No.
Unit-2 Amendment No. 15.3.1-8a 1 4
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