|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A7561995-04-25025 April 1995 Proposed Tech Specs,Adding RWCU Sys High Blowdown Containment Isolation Trip Function & Associated LCO & SRs to Tables 3.3.2-1,3.3.2-2 & 4.3.2.1-1 ML17291A6541995-02-10010 February 1995 Proposed Tech Specs,Modifying Surveillance Acceptance Criteria from 10% to 20% for Individual Jet Pump diffuser- to-lower Plenum Differential Pressure Variations of Individual Jet Pump from Established Patterns ML17291A4811994-10-31031 October 1994 Proposed Tech Spec Relocating Safety/Relief Valve Position Indication Instrumentation Requirements ML17291A4781994-10-31031 October 1994 Proposed Tech Spec 3/4.1.3.1, Reactivity Control Sys. ML17291A4451994-10-12012 October 1994 Corrected Proposed TS Bases 3/4.2.6, Power/Flow Instability. ML17291A4221994-09-26026 September 1994 Proposed Tech Specs,Reflecting Use of Siemens Power Corp Staif Code for Stability Analysis,Per Ieb 88-007,Suppl 1 ML17291A3981994-09-18018 September 1994 Proposed TS Table 3.6.3-1 Re Primary Containment Isolation Valve Requirements ML17291A3191994-08-0808 August 1994 Proposed Tech Specs 4.0.5 Re Guideliness for Inservice Insp & Testing Program ML17291A2171994-07-12012 July 1994 Proposed Tech Specs for Relocation of TS Tables for Instrument Response Time Limits ML17291A2221994-07-0808 July 1994 Proposed TS W/Regard to Control Rod Scram Insertion Testing Under Emergency Circumstances ML17291A1561994-06-23023 June 1994 Proposed Tech Specs Re Supporting Hydrostatic Testing 1999-07-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17284A9121999-10-13013 October 1999 Proposed Tech Specs 3.3.6.1,Table 3.3. 6.1-1, Primary Containment Isolation Instrumentation. ML17284A8761999-08-27027 August 1999 Replacement Page 9 of 9 to Attachment 4 of Procedure 13.10.6 ML17284A8491999-07-29029 July 1999 Proposed Tech Specs,Revising SR 3.5.2.2 Re Condensate Storage Tank Water Level ML17284A8421999-07-29029 July 1999 Proposed Tech Specs Revising SR of TS 3.8.4, DC Sources - Operating & SR 3.8.5.1 of TS 3.8.5, DC Sources - Shutdown. ML17284A8461999-07-29029 July 1999 Proposed Tech Specs,Revising Table 3.3.5.1-1, ECCS Instrumentation Items 1.a,2.a,4.a & E.A. ML17284A8521999-07-29029 July 1999 Proposed Tech Specs 3.4.9, RHR Shutdown Cooling Sys - Hot Shutdown. ML17333A0021999-04-20020 April 1999 Proposed Tech Specs Section 3.4.11,replacing Existing Reactor Pressure Temp Limit Curves by 000630 ML17292B6341999-04-0707 April 1999 Proposed Tech Specs Modifying MCPR Safety Limits to Allow Continued Power Operation at Plant Following Restart from R-14 RFO ML17292B5731999-03-0101 March 1999 ODCM for WNP-2 ML17292B4881998-12-17017 December 1998 Proposed Tech Specs SR 3.8.1.8,allowing Capability to Manually Transfer Between Preferred & Alternate Offsite Power Sources During Modes 1 & 2 by 990125 ML20198A7051998-11-30030 November 1998 Revs 8 Through 13 to TS Bases & Revs 12 Through 15 of Licensee Controlled Specs ML17284A7181998-08-0505 August 1998 Proposed Tech Specs SR 3.8.4.7,allowing Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 1 & 3,125 Vdc Batteries E-B1-1 & HPCS-B1-DG3 & Div 1,250 Vdc Battery E-B2-1 ML17284A7071998-07-17017 July 1998 Proposed Tech Specs Modifying SR 3.8.4.7 to Allow Performance Discharge Test to Be Performed in Lieu of Battery Svc Test for Div 2,125 Vdc,Battery E-B1-2 ML17284A6431998-05-29029 May 1998 Revised Plant Procedure Sys for Site Wide Procedures, Replacing Pages Located in Manual W/Pages in Package ML17292B2831998-03-0909 March 1998 Proposed Tech Specs Establishing Interim SLMCPR for Siemens Power Corp ATRIUM-9X Fuel Applicable to Cycle 14 Only ML17292B2591998-01-31031 January 1998 Offsite Dose Calculation Manual. ML17292B1321997-12-0404 December 1997 Proposed Tech Specs Modifying Min Critical Power Ratio Safety Limits ML17292B0281997-08-14014 August 1997 Proposed Tech Specs Revising TS 5.5.6 by Adding Note That Would Extend Interval Requirement to Perform Full Stroke Exercise Testing of TIP-V-6 Until 1998 Refueling Outage ML17292A9691997-08-12012 August 1997 Proposed Tech Specs Supporting Request for Enforcement Discretion for Period of 45 Days from TS Action 3.6.1.3.A Required Actions to Isolate Purge Line & Verify Penetration Flow Path Isolated Every 31 Days ML17292A9421997-07-16016 July 1997 Proposed Tech Specs Adding New Min Reactor Vessel Pressure Versus Reactor Vessel Metal Temp (P/T) Curves,Applicable Up to 12 EFPYs ML17292A8901997-06-0606 June 1997 Revised Tech Spec Page 2.0-1 Modified to Indicate That SLMCPR for ATRIUM-9X Fuel Applies Only to Cycle 13 & Corresponding Bases Pages ML17292A8651997-05-20020 May 1997 Proposed Tech Specs,Requesting Mod of Minimum Critical Power Ratio Safety Limits by 970615 ML17292A8301997-03-31031 March 1997 Wppss WNP-2 RPV Surveillance Matls Testing & Analysis. ML17292A7621997-03-24024 March 1997 Rev 5 to TS Bases. ML17292A7631997-03-24024 March 1997 Rev 7 to Licensee Controlled Specs. ML17292A7581997-03-22022 March 1997 Proposed Tech Specs Modifying Response Time Testing SR for RPS Instrumentation,Primary Containment Isolation Actuation Instrumentation & ECCS Actuation Instrumentation ML17292A7531997-03-20020 March 1997 Proposed Tech Specs Re Response Time Testing Requirements ML17292A6591997-01-14014 January 1997 Proposed Tech Specs Reflecting Compilation of TS Change Requests Submitted to NRC in Ltrs Dtd 951208,960709 & 1212 ML17292A6341996-12-12012 December 1996 Proposed Tech Specs Requesting Conversion Based Upon NUREG-1434,rev 1 ML17292A6161996-11-19019 November 1996 Rev 1 to WNP-2 IST Program Plan (Pumps & Valves) 2nd Interval (941213-041212). ML17292A5511996-10-15015 October 1996 Proposed Tech Specs Re Secondary Containment & SGTS to Reflect Revised Secondary Containment Drawdown & post- Accident Analyses Results ML17292A5411996-10-10010 October 1996 Proposed Tech Specs Requesting Addition of Section 2B(6) Re Storage of Byproduct,Source & Special Nuclear Materials ML17292A4501996-09-0606 September 1996 Proposed Tech Specs,Containing Corrections to Factual Statements & Proposed Info to Clarify Evaluations ML17292A4111996-08-0909 August 1996 Proposed Tech Specs,Revising TS Section 6.3 Re Unit Staff Qualifications,By Changing Operations Manager Qualification Requirements Associated W/Operations Knowledge from Meeting Ansi/Ans N18.1-1971 ML17292A3561996-07-0909 July 1996 Proposed Tech Specs,Revising Rev a, Including Changes in Vol 7.Proposed Rev Does Not Change Conclusion of NSHC or Environ Assessment Provided Rev a ML17292A7241996-05-31031 May 1996 Offsite Dose Calculation Manual. ML17292A2741996-04-25025 April 1996 Rev 0 to UT-WNP2-208V0, Exam Summary Sheet. ML20107M3391996-04-24024 April 1996 Proposed Tech Specs,Modifying TS to Support Cycle 12, Scheduled to Begin Subsequent to Spring 1996 Outage ML17292A1511996-04-22022 April 1996 Proposed Tech Specs,Supplementing TS That Describes Administrative & Editorial Changes to Section 6.0, Administrative Controls. ML17291B2801996-03-19019 March 1996 Proposed Tech Specs Re Containment Leakage Testing ML17291B2491996-02-26026 February 1996 Proposed Tech Specs,Submitting Revised Copy of TS Bases Which Include Minor Changes & Clarifications Made Per Requirements of 10CFR50.59 ML17333A0201996-01-19019 January 1996 Proposed Tech Specs Re Primary Containment Leakage Testing ML17291B1751995-12-31031 December 1995 Reactor Power Uprate Startup Test Rept, for WNP-2. W/951215 Ltr ML17291B0941995-10-26026 October 1995 Proposed Tech Specs,Replacing Existing Reactor Recirculation Flow Control Sys W/Adjustable Speed Drive Sys ML17291A9911995-08-16016 August 1995 Proposed Tech Specs Page 3/4 4-4,incorporating Surveillance Notes in Front of Surveillances 4.4.1.2.1 & 4.4.1.2.2 for Jet Pump Operability to Clarify That Notes Apply to Each Surveillance ML17291A9591995-07-28028 July 1995 Operations Instructions OI-23,Rev a to, Human Performance Improvement Program. ML20087E2831995-07-26026 July 1995 Performance Enhancement Strategy 1995 ML17291A8401995-06-0606 June 1995 Proposed Tech Specs Index,Deleting Ref to Bases Pages ML17291A8371995-06-0606 June 1995 Proposed Tech Specs Section 6.9.3.2,adding Ref to Three TRs Describing Analytical Methods That May Be Used in Determining Reactor Core Operating Limits for Reload Licensing Applications ML17291A8441995-06-0606 June 1995 Proposed Tech Specs Section 6.0, Administrative Controls. 1999-08-27
[Table view] |
Text
~
REQUEST I<'OR AMENDME<NT TECHNICALSPECIFICATION 3.3.5.1 EMERGENCY CORE COOLING SYSTEM (ECCS)
INSTRUMENTATION Attachment 3 Marked-Uy Version of Technical SpeciTication 3.3.5.1 9908060092 990729 PDR ADQCK 05000397 P PDR
fCCS Instrumentation 3.3.5.1 Table 3.3.5.1.1 (page 1 of 4)
Emergency Core Cooling System Instrunentation APPLICABLE COND IT IONS NODES OR REFEREHCED OTHER REQUIRED FROM SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOMABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREHEHTS VALUE
- 1. Lou Pressure Coolant injection.A (LPCI) and Lou I'Yd. 3 Pressure Core Spray (LPCS)
Subsystems
- a. Reactor Vessel llater 1,2,3, 2(b) SR 3.3.5.1.1 a-1 i es Level Lou Lou Low, 4(a) 5(a)
SR 3.3.5.1.2 Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6 b; Oryuel l Pressure - High. 1,2,3 2(b) SR 3.3.5.1.2 < 1.88 ps i g.
SR 3.3.5.1.4 SR 3.3.5.1.6
- c. LPCS Pump Start LOCA'ime 1,2,3, SR 3.3.5.1.5 3.3.5.1.6 iseconds 8.53 and I
Delay Relay SR 4(a) 5(a) < 10.64 seconds
- d. LPCI Pump A 1,2,3, SR 3.3.5.1.5 > 17.24 Start LOCA Time Delay SR 3.3.5.1.6 seconds and Relay 4(a) 5(a) < 21.53 seconds
- e. LPCI Ptas A 1,2,3, SR 3.3.5.1.2 i 3.04 Start LOCA/LOOP Time SR 3.3.5.1.3 seconds and Delay Relay 4(a) 5(a) SR 3.3.5.1.6 < 6.00 seconds
- f. Reactor Vessel 1,2,3 1 per valve C SR 3.3.5.1.2 2 448 psig Pressure - Lou SR 3.3.5.1.4 3.3.5.1.6 and
< 492 (Injection Permissive) SR psig 4( ,5 1 per valve 8 SR 3.3.5.1.2 2 448 psig SR 3 '.5.1.4 and SR 3.3.5.1.6 S 492 psig
- g. LPCS Punp Discharge 1,2,3, SR 3.3.5.1.2 i 668 gpm and Floe LoM (Hininxm (a) 5(a)
SR 3.3.5.1.4
'.6
< 1067 gpn Flou) SR 3.3.5
- h. LPCI Pump A Discharge 1,2,3, SR 3.3.5.1.2 > 605 gpm and F lou - LoM (Hiniaun 4(a) 5(a)
SR 3.3.5.1.4 < 984 gpm Floe) SR 3.3.5.1.6
- i. Manual Initiation 1,2,3, SR 3.3.5.1.6 NA 4(a) 5(a)
(continued)
(a) Mhen associated subsystem(s) are required to be OPERABLE.
(b) Also required to initiate the associated diesel generator (OG).
WNP-2 3.3-43 Amendment No. 449 150
0 "l
I jl j
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 4)
Emergency Core Cooling System Instrunentation APPLICABLE CONDITIONS NODES OR REFERENCED OTHER REOUIRED FRQI SPECI F IED CHANNELS PER REOUIRED SURVEILLANCE ALLOMABLE FUNCTION COND I T I OHS FUNCTION ACTION A.1 REOUIREHENTS VALUE
- 2. LPCI B and LPCI C
- /')/g. 3 Subsystems
- a. Reactor Vessel Mater 1,2,3, 2(b) SR '3.3.5.1.1 ,. > -148 inches
~ Level ~ Low Low Lowi SR 3.3.5.1.2 Level 1 4(a) 5<a) SR 3.3.5.1.4 SR 3.3.5.1.6
- b. Drywel l Pressure - High 1,2,3 2(b) SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6
- c. LPCI Pump B Start-LOCA 1,2,3, 1 C SR 3.3.5.1.5 > 17.24 Time Delay Relay SR 3.3.5.1.6 seconds and 4(a) 5(a) <<21.53 seconds
- d. LPCI Plop C Start - LOCA 1,2,3, SR 3.3.5.1.5 > 8.53 Time Delay Relay SR 3.3.5.1.6 seconds and 4(a) 5(a) << 10.64 seconds
- e. LPCI Pm@ B 1.2.3. SR 3.3.5.1.2 > 3.04 Start -'OCA/LOOP Time SR 3.3.5.1.3 seconds and Delay Relay 4(a) 5(a) SR 3.3.5.1.6 S 6.00 seconds
- f. Reactor Vessel 1,2,3 per valve . C SR 3.3.5.1.2 '48 psig Pressure - Low 1
SR 3.3.5.1.4 and (Injection Permissive) SR 3.3.5.1.6 << 492 psig 4<a),5<a) 1 per valve SR 3.3.5.1.2 R 448 Pslg SR 3.3.5.1.4 and SR 3.3.5.1.6 << 492 PSlg
- g. LPCI Punps 8 8 1,2,3, per pal SR 3.3.5.1.2 2 605 Discharge Flow - Low C
4(a) 5<a) 1 SR 3.3.5.1.4 and (Hininxml Flow) SR 3.3.5.1.6 << 984
- h. Hanual Initiation 1,2,3, SR .3.3.5.1.6 NA 4(a) 5(a)
- 3. High Pressure Core Spray (HPCS) System
- a. Reactor Vessel Mater 1,2,3, b SR 3.3.5.1. I '58 inches Level Low Low, Level 2 SR 3.3.5.1.2 4(a) 5(a) SR 3.3.5.1.4 SR 3.3.5.1.6
<continued)
(a) Mhen associated subsystem<s) are required to be OPERABLE.
(b) Also required to initiate the associated DG.
MNP-2 3.3-44 Amendment No. 449 150
I
~ i H
,,", l
ECCS Instrumentation'.3.5.1 Table 3.3.5.1-1 (page 3 of 4)
Emergency Core Cooling System Instrunentation APPLICABLE CORDI TIOHS MMES OR REFERENCED OTHER REQUIRED FRO}i SPEC IF IED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUHCTIOH ACTIOH A.1 'EQUIREHENTS VALUE
- 3. HPCS Systein (continued)
- b. 0rywel l 1,2,3 4(b) SR 3.3.5.1.2 8 1.88 psig Pressure - High SR 3.3.5.1.4 SR 3.3.5. 1.6
- c. Reactor Vessel 1,2,3, SR 3.3.5.1.1 Mater, Level High, 4(a) 5(a)
SR 3.3.5.1.2 3.3.5. 1.4 Level 8 SR SR 3.3.5.1.6
- d. Condensate Storage 1,2,3, SR 3.3.5.1.2 2 448 ft l,inch Tank Level Low- 4(c) 5(c)
SR 3.3.5.1.4 elevation SR 3.3.5.1.6
- e. Suppression Pool 1,2,3 SR 3.3.5.1.2 + 466 f~
Mater Level High SR 3.3.5.1.4 11 incnes SR 3.3.5.1.6 elevation
- f. Flow 1,2,3, SR 3.3.5.1.2 k 1200 gpn and HPCS Rate -System Low (Hfniaasa SR 3.3.5.1.4 S 1512 gpm I'low) 4(a) 5(a) SR 3.3.5.1.6
- g. Hanual Initiation 1,2,3, SR 3.3'5.1.6 NA 4(a) 5(a)
- 4. Automatic Depressurization System (ADS) Trip System A
- a. Reactor Vessel 2(d) 3(d) SR 3.3.5.1.1 + .148 inches
'Water Level - Low 1
SR 3.3.5.1.2 Low Low, Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6
- b. ADS Initiation 1 2(d) 3(d) SR 3.3.5.1.2 S 115.0 seconds Timer SR 3.3.5.1.3 SR 3.3.5.1.6
- c. Reactor Vessel 2(d) 3(d) SR 3.3.5.1.1 > 9.5 inches Mater Level Low,- 1 SR 3.3.5. 1.2 Level 3 SR 3.3.5.1.4 (Permissive) SR 3.3.5.1.6
- d. LPCS Punp 1 2(d) 3(d) SR 3.3 '.1.2 k 119 psig and Discharge SR 3.3.5.1.4 s 171 psig Pressure - High SR 3.3.5.1.6 (continued)
(a) 'When associated subsystem(s) are required to be OPERABLE.
(b) Also required to initiate the associated DG.
(c) When HPCS -
is OPERABLE for coepliance with LCO 3.5.2, ~~ECCS Shutdown," and aligned to the condensate storage tank while tank ~ster level is not within the limit of SR 3.5.2.2.
(d) Mith reactor steam dome pressure > 150 psig.
WNP-2 3.3-45 Amendment No. 449 150
0 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 4)
Emergency Core Coolfng System Instrunentation APPLICABLE CONDITIONS NODES OR REFERENCED OTHER REQUIRED FROH SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOllABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREHENTS VALUE
- 4. ADS Trip System A (continued)
- e. LPCI Pump A Discharge 2(d) 3(d) '.3.5.1.2 > 116 psig Pressure - High 1 SR SR 3.3.5.1.4 and SR 3.3.5.1.6 s 134 psig
- f. Accuaulator Backup 1 2(d) 3(d) SR 3.3.5.1.2 R 151.4 psig Compressed Gas System 3.3.5.1.4 Pressure - Low SR SR 3.3.5.1.6
- g. Hanual Initiation 1 2(d) 3(d) SR 3.3.5.1.6 IV+.3
- 5. ADS Trip System B
- a. Reactor- Vessel Uater 1 2(d) 3(d) F SR 3.3.5.1.1 > -14B inches Level Low Low Loll~ SR 3.3.5.1.2 Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6
- b. ADS Initiation Tfmer 1,2 ,3 SR 3.3.5.1.2 s 115.0 SR 3.3.5.1.3 seconds SR 3.3.5.1.6
- c. Reactor Vessel Mater 2(d) 3(d) 3.3.5.1.1 9.5 inches Level Low, Level 3 1 SR SR 3.3.5 1.2
~
2 (Permissive) SR 3.3.5.1.4 SR 3.3.5.1.6
- d. LPCI Pumps 8 S C 1 2(d) 3(d) 2 per pulp SR 3.3.5.1.2 ? 116 psig .
Discharge 3.3.5.1.4 Pressure - High SR SR 3.3.5.1.6 and 5 134 psig
- e. Accuwlator Backup 1 2(d) 3(d) SR 3.3.5.1.2 2 151.4 psig Compressed Gas System 3.3.5.1.4 Pressure - Low SR SR 3.3.5.1.6
- f. Hanual Initiation 1 2(d) 3(d) SR 3.3.5.1.6 NA (d) Wfth reactor steam dome pressure > 150 psig.
WNP-2 3.3-46 Amendment No. 149
~ ~
S O
REQUEST FOR AMENDMENT TECHNICALSPECIFICATION 3.5.2.2 EMERGENCY COIN COOLING SYSTEM (ECCS) ~
INSTRUMENTATION Attachment 4 Replacement Pages for Technical Specification 3.3.5.1
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-. 1 (page 1 of 4)
Emergency Core Cooling System Instrunentation APPLICABLE CONDITIONS HODES OR REFERENCED OTHER -REQUIRED FROH SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 1. Low Pressure Coolant Injection-A (LPCI) and Low Pressure Core Spray (LPCS)
Subsystems
- a. Reactor Vessel Water 1,2,3, 2(b) 3.3.5.1.1 > -142.3 Level Low Low Low, 4(a) 5(a)
SR SR 3.3.5 ' ' inches Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6 ~
- b. Drywell Pressure High 1.2.3 2(b) SR 3.3.5.1.2 < 1.88 psig.
SR 3.3.5.1.4 SR 3.3.F 1.6
- c. LPCS Pwp Start.LOCA.. 1.2.3. SR 3.3 '.1 '. > 8.53 Time Delay Relay SR 3.3.5.1.6 seconds slid 4(a) 5(a) S 10.64 seconds
- d. LPCI Pump A
- 1I2I3I SR 3.3 '.1 ' > 17.24 Start LOCA Time Delay SR 3.3.5.1.6 seconds and Relay 4(a) 5(a) < 21.53 seconds
- e. LPCI Pump A 1,2,3, SR 3.3.5.1.2 h 3.04 Start LOCA/LOOP Time SR 3.3.5.1.3 seconds and Delay Relay 4(a) 5(a) SR 3.3 '.1.6 < 6.00 seconds
- f. Reactor Vessel 1,2,3 1 per valve C SR 3.3.F 1.2 ?: 448 psig Pressure Low SR 3.3.5.1 ' and (Injection Permissive) SR 3.3.5.1.6 < 492 psig 4 5 1 per valve B SR 3.3.5.1.2 > 448 psig SR 3.3 '.1.4 and SR 3.3.5.1.6 < 492 psig g.
LPCS Pump Discharge 1,2,3, SR 3.3 ' '.2 > 668 gpm and Flow Low (Hinimml SR 3.3.5.1.4 < 1067 gpm Flow) 4(a) 5(a) SR 3.3.5.1.6
- h. LPCI Pump A Discharge SR 3.3.5.1.2 2 605 gpm and Flow Low (Ninilmml SR 3.3.5 '.4 < 984 gpm F low) 4(a) 5(a) SR 3.3.5.1.6 i'anual Initiation 1I2I3I SR 3.3.5 1.6
~ HA 4(a) 5(a)
(continued)
(a) When associated subsystem(s) are required to be OPERABLE.
(b) Also required to initiate the associated diesel generator (DG) ~
WNP-2 3.3-43 Amendment No. 449 480
s~
f
.C I
4 i w
k(
il
O ECCS Instrumentation 3.3.5,1 Table 3.3.5.1-1 (page 2 of 4)
Emergency Core Cooling System tnstrunentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECIFIED CHAHHELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUHCTION ACTION A.1 REQUIREMEHTS VALUE
- 2. LPCI 8 and LPCI C Subsystems
- a. Reactor Vessel Water 1,2,3, 2(b) SR 3.3.5.1.1 > -142.3 Level Low Low Low, SR 3.3.5 '.2 inches Level 1 4(a) 5(a) SR 3.3.5 '.4 SR 3.3.5 '.6
- b. Drywell Pressure High 1,2,3 2(b) SR 3.3.5.1.2 < 1.88 psig SR'.3 ~ 5.1.4'R 3.3.5.1.6
- c. LPCI Pump B Start LOCA 1I2I3I SR 3.3.5.1.5 > 17.24 Time Delay Relay SR 3.3 5.1.6 " seconds and
~
4(a) 5(a) < 21.53 seconds
- d. LPCI Pump C Start LOCA 1,2,3, SR 3.3.F 1.5 > 8.53 Time Delay Relay 4(a) 5(a)
SR 3.3.5 '.6 seconds and
< 10.64 seconds
- e. LPCI Pump 8 1I2I3I SR 3.3 '.1.2 a 3.04 Start LOCA/LOOP Time SR 3.3.5.1.3 seconds and Delay Relay 4(a) 5(a) SR 3.3.5 '.6 < 6.00 seconds
- f. Reactor Vessel 1,2,3 1 per valve SR 3.3.5.1.2 ?, 448 psig Pressure Low SR 3.3.F 1.4 and (Injection Permissive) SR 3.3.5.1.6 < 492 psig 4( ) 5( ) 1 per valve SR 3.3.5.1.2 > 448 psig SR 3.3.5.1.4 and SR 3.3.5.1.6 < 492 psig
- g. LPCI Pumps B 8 C 1,2,3, 1 per putnp SR 3.3.5.1.2 ? 605 gpm Discharge Flow Low SR 3.3.F 1.4 and (Mininun Flow) 4(a) 5(a) SR 3.3.5.1.6 S 984 gpm
- h. Manual Initiation 1 ~ 2I3I SR 3.3.5 '.6 HA 4(a) 5(a)
- 3. High Pressure Core Spray (HPCS) System
- a. Reactor Vessel Water 1I2I3I 4(b) SR 3.3.5 '.1 > -58 inches Level Low Low, Level 2 SR 3.3.5.1.2 4(a) 5(a) SR 3.3 '.1.4 SR 3.3.5.1.6 (continued)
(a) When associated subsystem(s) are required to be OPERABLE.
(b) Also required to initiate the associated DG.
WNP-2 3.3-44 Amendment No. 449 ASS
1
~
a "I
}
ECCS Instrumentation 3.3.5.1 Table 3.3.5 ~ 1-1 (page 3 of 4)
Emergency Core Cooling System Instrunentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER REQUIRED FROM SPECI F IED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE
- 3. HPCS System (continued)
- b. Drywall 1I2I3 4(b) SR 3.3.5.1.2 S 1.88 psig Pressure High SR 3.3.5.1.4 SR 3.3.F 1.6 c.. Reactor. Vessel,
- 1 'I3I SR, 3.3 5 1.1
~ ~ S 56.0,inches i Water Level High, SR 3.3 '.1.2 Level 8 . 4(a) 5(a) SR 3.3.5.1.4 SR 3.3 '.1.6
- d. Condensate Storage Tank Level Low 1 'I3I SR 3.3.5 '.2 > 448 ft 1 inch SR'.3.5.1.4 elevation 4(c) 5(c) SR '.3.5.1.6
- e. Suppression Pool 1,2,3 D SR 3.3.5.1.2 < 466 ft Water Level High
'R 3.3.5.1.4 11 inches SR 3.3.F 1.6 elevation
- f. HPCS System Flow 1,2,3, SR 3.3.5.1.2 > 1200 gpm and Rate Low (Mininun SR 3.3.5. 1.4 < 1512 gpm Flow) 4(a) 5(a) SR 3.3.5.1.6
- g. Manual Initiation 1I2I3I SR 3.3.5.1.6 NA 4(a) 5(a) 4~ Automatic Depressurization System (ADS) Trip System A
- a. Reactor Vessel 1 2(d) 3(d) SR 3.3.5.1 1~ > -142.3 inches Water Level Low SR 3.3.5.1.2 Low Low, Level 1 SR 3.3 '.1.4 SR 3.3 '.1.6
- b. ADS Initiation 1 2(d) 3(d) SR 3.3 '.1.2 < 115.0 seconds Timer SR 3.3.5.1.3 SR 3.3.5.1.6
- c. Reactor Vessel 1 2(d) 3(d) SR 3.3.5.1 1~ > 9.5 inches Water Level Low, SR 3.3 '.1.2 Level 3 SR 3.3.5 '.4 (Permissive) SR 3.3 '.1.6
- d. LPCS Pump 1 2(d) 3(d) SR 3.3.5.1.2 > 119 psig and Discharge SR 3.3 '.1.4 < 171 pslg Pressure High SR 3.3 '.1.6 (continued)
(a) When associated subsystem(s) arc required to be OPERABLE.
(b) Also required to initiate the associated DG.
(c) When HPCS is OPERABLE for compliance with LCO 3.5.2, "ECCS Shutdown," and aligned to the condensate storage tank while tank water level is not within the limit of SR 3.5.2.2.
(d) With reactor stcam dome pressure > 150 psig.
WNP-2 3.3-45 Amendment No. 449 488
~
'L C
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 4)
Emergency Core Cooling. System Instrunentation APPLICABLE CONDITIONS HOOES OR REFERENCED OTHER REQUIRED FROH SPECIFIED CHANNELS PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREHENTS VALUE
- 4. ADS Trip System A (cont Inued)
- e. LPCI Pump A Discharge Ii2(d) 3(d) SR 3.3.5.1.2 2 116 psig Pressure High SR 3.3 '.1.4 and SR 3.3 5.1.6
~ 5 134 psig
- f. Accunulator Backup 1 2(d) 3(d) SR 3.3.5-1.2 2 151.4 psig Compressed Gas System SR"'.3.5.1.4 Pressure Low SR 3.3.5.1.6
- g. Hanual Initiation 1 2(d) 3(d) SR 3.3.5 1.6,
~ NA
- 5. ADS Trip System B
- a. Reactor Vessel Water ii2(d) 3(d) SR 3.3 5.1.1
~ ? -142.3 Level'- Low Low Low, SR 3".3.'5'.1'.2'nches .
Level 1 SR 3.3.5.1.4 SR 3.3.5.1.6
- b. ADS Initiation Timer 1 2(d) 3(d) SR 3.3 '.1.2 < 115.0 SR 3.3.5.1.3 seconds SR 3.3.F 1.6
- c. Reactor Vessel Water 2(d) 3(d) SR 3.3.5.1.1 2 9.5 inches Level Low, Level 3 1
SR 3.3.5.1.2 (Permissive) SR 3.3 '.1.4 SR 3.3 '.1.6
- d. LPCI Pumps 8 II C 1 2(d) 3(d) 2 per pump SR 3.3 5.1.2
~
> 116 psig Discharge SR 3.3.5.1.4 and Pressure High SR 3.3 5.1-6
~ S 134 psig
- e. Accunulator Backup 1 2(d) 3(d) F. SR 3.3.5.1.2 2 151.4 psig Compressed Gas System SR 3.3.5.1.4 Pressure Low SR 3.3.5.1.6
- f. Hanual Initiation 1 2(d) 3(d) SR 3.3.5.1.6 NA (d) With reactor steam dome pressure > 150 psig.
WNP-2 3.3-46 Amendment No. 449
V 4
I~