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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits ML17310A5211993-08-0505 August 1993 Proposed Tech Specs Requesting to Change Word Pressurizer to RCS for Item #4 in Both Tables 3.3-10 & 4.3-7 ML17310A5151993-08-0505 August 1993 Proposed Tech Specs Changing Surveillance Frequency from Monthly to Quarterly for Channel Functional Tests for RPS & ESFAS Instrumentation ML17310A4211993-06-30030 June 1993 Proposed Tech Specs Requesting Addl Operating Margin in Time Response of Turbine Driven AF Pump to SG Low Level Signal ML17310A2981993-05-20020 May 1993 Proposed TS 4.7.9 Re SR to Ensure Operability of Snubbers ML17306B2671993-01-25025 January 1993 Proposed Tech Specs,Reflecting Revised Train a Kw Value to Be Rejected & Load Designation & Incorporation of Provisions Discussed in 920508 Ltr Re DG Full Load Rejection Testing ML17306B1451992-11-20020 November 1992 Proposed Tech Specs Revising TS 3.2.1 Lhr, & TS 3.2.4, DNBR Margin, Increasing Action from 1 H to 4 H for COLSS Allowed Out of Svc Time Before Requirements Based on More Restrictive Core Protection Calculator Limits Apply ML17306A6491992-04-13013 April 1992 Proposed TS 3.4.8.3 Re RCS - Overpressure Protection Sys ML17306A4731992-02-14014 February 1992 Proposed Tech Specs Re Implementation of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent TS in Administrative Controls Section of TS & Relocation of Procedural Details of RETS to Odcm.... ML17306A4031992-01-16016 January 1992 Proposed Tech Specs Amend to TS Section 3.6.3,table 3.6-1 Deleting Type C Testing Requirements for Eight Valves ML17306A3701991-12-30030 December 1991 Proposed Tech Spec Table 6.2-1 Re Min Shift Crew Composition ML17306A3781991-12-30030 December 1991 Proposed Tech Spec Section 3.6.1.7 Re Containment Purge Supply & Exhaust Valves 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
[Table view] |
Text
TABLE 2.2-1 REACTOR PROTECTIVE INSTRUHEHTAT ION TRIP SETPOINT L IHITS
(
foal Wl FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- 1. TRIP GENERATION A. Process
- 1. Pressurizer Pressure - Iligh 2383 psia 2388 psia
- 2. Pressurizer Pressure Low 1837 psia (2) ~ 1821 psia (2)
- 3. Steam Generator Level Low 44.2~ (4) 43.7-. (4) 91.0'-. (9) << 91.5%
- 4. Steam Generator Level Nigh (9)
- 5. Steam Generator Pressure Low ~
See
+& psia (3) ~
SRO psia (3)
Containment Pressure Iligh 3.0 psig << 3.2 psig 6.
- 7. Reactor Coolant Flow Low a ~ Rate 0.115 psi/sec (6) (7) 0.118 psi/sec (6) (7)
~ 11.9 psid (6)(7) 11.7 psid(6)(7)
- b. Floor
% UN aot c. Band - 10.0 psid (6)(7) 10.2 psid (6)(7)
Ã~
M M 8. Local Power Densi ty Iligh 21.0 kW/ft (5) 21.0 kW/ft (5) ao
- 9. DHBR Low 1.30 (5) 1.30 (5) nw I
r% ..-
oe Util:
B. Excore Neutron Flux Q~ Vari abl e Overpower Tri p oM 1.
~ II aQQ.
QQM
<<10.6~/min of <<11.0'/min of
-l >%M c) j I a. Rate THERMAL POWER RATED (8) THERHAL POWER RATED (8)
~ 'I II b. Cei I ing <<110.0>> of RATED <<111.0>> of RATED Wl'I THERMAL POWER (8)
TNERHAL POWER (8)
- c. Band <<9.7-'; of RATED -9.9'f RATED THERMAL POWER (8) THERMAL POWER (8)
TABLE 3.3-4 ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES I
C) ESFA SYSTEM FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES m I. SAFETY INJECTION (SIAS)
R7 C7 m A. Sensor/Trip Units
- 1. Containment Pressure - High < 3.0 psig 5 3.2 psig
- 2. Pressurizer Pressure - Low > 1837 psia"'ot
> 1821 psia B. ESFA System Logic Applicable Not Applicable C. Actuation Systems Not Applicable Not Applicable II. CONTAINMENT ISOLATION (CIAS)
A. Sensor/Trip Units
- 1. Containment Pressure - High < 3.0 psig < 3.2 ps>g
- 2. Pressurizer Pressure - Low > 1837 psia' > 1821 psia' B. ESFA System Logic Not Applicable Not Applicable C. Actuation Systems Not Applicable Not Applicable III. CONTAINMENT SPRAY (CSAS)
A. Sensor/Trip Units Containment Pressure High - High < 8.5 psig < 8.9 psig B. ESFA System Logic Not Applicable Not Applicable C. Actuation Systems Not Applicable Not Applicable IV. MAIN STEAM LINE ISOLATION (MSIS)
Sensor/Trip Units m
A.
1.
2.
Steam Generator Steam Generator Pressure Level -
High Low > ~895 psia"'
91.0X NR~ '
QQO
- m. psia"'
91.5X NR( )
C7
- 3. Containment Pressure High 3.0 psig < 3.2 psig
- 0. ESFA System Logic Not Applicable Not Applicable C) C. Actuation Systems Not Applicable Not Applicable CQ
TABLE 3. 3-4 (Continued)
TABLE NOTATIONS (1) In MODES 3-6, value may be decreased manually, to a minimum of 100 psia, as pressurizer pressure is reduced, provided the margin between the pres-surizer pressure and this value is maintained at less than or equal to 400 psi; the setpoint shall be increased automatically as pressurizer pressure is increased until the trip setpoint is reached. Trip may be manually bypassed below 400 psia; bypass shall be automa.ically removed whenever pressurizer pressure is greater than or equal to 500 psia.
(2) Irange of the distance between instrument nozzles.
steam generator upper and lower level narrow (3) In MOOES 3-P, value may be decreased manually as steam generator pressure is reduced, provided the margin between the steam generator pressure and this value is maintained ~t less than or equal to 200 psi; the'setpoint shall be increased automatically as steam generator pressure is increased until the trip setpoint is reached.
(4) %%u'f the distance between steam generator upper and lower level wide range instrument nozzles.
PALO VERDE - UNIT l 3/4 3-27
TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- 1. TRIP GENERATION A. Process Pressurizer Pressure High
- 1. 2383 psia 2388 psia
- 2. Pressurizer Pressure Low 1837 psia (2) 1821 psia (2)
- 3. Steam Generator Level - Low = 44.2-; (4) ~ 43.7% (4)
- 4. Steam Generator Level High 91.0'-. (9) ~ 91.5%
(9)
- 5. Steam Generator Pressure Low 8SS
~opsia (3) ~
8RO psia (3)
- 6. Containment Pressure High 3.0 psig ~
3.2 psig
- 7. Reactor Coolant Flow Low
- a. Rate 0.115 psi /sec (6)(7) ~ 0.118 psi/sec (6) (7)
- b. Floor ~ 11.9 psid (6)(7) ~ 11.7 psid(6)(7)
- c. Band 10.0 psid (6)(7) 10.2 psid (6)(7)
- 8. Local Power Density High 21.0 kW/ft (5) 21.0 kW/ft (5)
- 9. DNBR Low 1.30 (5) 1.30 (5)
B. Excore Neutron Flux
- 1. Vari abl e Overpower Tri p
- a. Rate ~10.6'./min of RATED -11.0'/min of RATED THERMAL POWER (8) THERMAL POWER (8)
- b. Ceil ing -I IO.O~ of RATED <111.0'. of RATED THERMAL POWER (8) THERMAL POWER (8)
- c. Band ~9.7~ of RATED ~9.3'f RATED'HERMAL THERMAL POWER (8) POWER (8)
TABLE 3.3-4 ENGINEEREO SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES ESFA SYSTEM FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES I. SAFETY INJECTION (SIAS)
A. Sensor/Trip Uni ts
- 1. Containment Pressure High 3~0 psig 3' psig
- 2. Pressurizer Pressure Low ~ 1837 ~ 1821 psia"'ot psia"'ot B. ESFA System Logic Applicable Applicable C. Actuation Systems Not Applicable Not Applicable I I. CONTAINMENT ISOLATION (CIAS)
A. Sensor/Trip Units
- 1. Containment Pressure High 3.0 ~ 3+2 psig psig
- 2. Pressurizer Pressure Low ~ 1837 1821 psia"'ot psia"'ot B. ESFA System Logic Applicable Applicable C. Actuation Systems Not Applicable Not Applicable III. CONTAINMENT SPRAY (CSAS)
A. Sensor/Trip Units Containment Pressure High High 8.5 psig ~ 8.9 psig B. ESFA System Logic Not Applicable Not Applicable C. Actuation Systems Not Applicable Not Applicable IV. HAIN STEAM LINE ISOLATION (HSIS)
A. Sensor/Trip Units
- 1. Steam Generator Pressure Low Steam Generator Level High
~ ~91.0'R'"
O'I5 psia@
89o
%k psia@
- 2. 4 91.5'RR
- 3. Containment Pressure Hi gh 3.0 ~
psig 3.2 pslg B. ESFA System Logic Not Applicable Not Applicable C. Actuation Systems Not Applicable Not Applicable
TABLE 2.2-1 REACTOR PROTECTIVE INSTRUMENTATION TRIP SETPOINT LIMITS FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES
- 1. TRIP GENERATION A. Process Pressurizer Pressure High 2383 psia
- 1. 2388 psia Pressurizer Pressure Low 1837 psia (2) ~ 1821
- 2. psia (2)
- 3. Steam Generator Level Low ~ 44.2~ = 43.7-. (4)
(4)
- 4. Steam Generator Level High 91.0~ (9) = 91.5-. (9)
- 5. Steam Generator Pressure Low 8'ld 9R psia (3) ~ ~SRO psia (3)
- 6. Containment Pressure High 3.0 psig 3.2 pslg
- 7. Reactor Coolant Flow Low
- a. Rate 0.115 psi/sec (6)(7) <<0.118 psi/sec (6)(7)
- b. Floor ~ 11.9 psid (6)(7) 11.7 psid(6)(7)
- c. Band << 10.0 psid (6} (7} - 10.2 psid (6)(7)
- 8. Local Power Density High 21.0 kW/ft (5) 21.0 kW/ft (5)
- 9. DNBR Low 1.30 (5) 1.30 (5)
B. Excore Neutron. Flux
- 1. Variable Overpower Trip
- a. Rate <<10.6~/min of RATED ~11.0~/min of RATED THERMAL POWER (8) THERHAL POWER (8)
- b. Cei 1 ing -110 0'. of RATED <<111.0> of RATED THERMAL POWER (8) THERHAL POWER (8)
- c. Band -.9.7'-. of RATED -9.9~a of RATED THERMAL POWER (8) THERHAL POWER (8)
'k TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUMENTATION TRIP VALUES ESFA SYSTEM FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLr VALUES I.
( SAFETY INJECTION A.
(SIAS)
Sensor/Trip Units C7 m - High
- 1. Containment Pressure < 3.0 psig ~ 3.2 psig
- 2. Pressurizer Pressure Low > 1837 psia"'ot
> 1821 psia"'ot B. ESFA System Logic Applicable Applicable C. Actuation Systems Not Applicable Not Applicable I I. CONTAINMENT ISOLATION (CIAS)
A. Sensor/Trip Units
- 1. Containment Pressure - High s 3.0 psig ~ 3.2 psig
- 2. Pressurizer Pressure - Low ~ 1837 psia"'ot
?: 1821 psia"'ot 4J
~
~ B. ESFA System Logic Applicable Applicable CrJ I C. Actuation Systems Not Applicable Not Applicable Vl III. CONTAINMENT SPRAY (CSAS)
A. Sensor/Trip Units Containment Pressure High - High s 8.5 psig s 8.9 psig B. ESFA System Logic Not Applicable Not Applicable C. Actuation Systems Not Applicable Not Applicable I V. HAIN STEAN LINE ISOLATION (HS IS) m A. Sensor/Trip Units C7
- 1. Steam Generator Pressure - Low > ~ psia"'
8 lS
~ au psia"'1,5%
t3)
C) 2. Steam Generator Level High 91.O% NR'" NR
- 3. Containment Pressure High s 3:0 psig >. 3.2 psig B. ESFA System Logic Not Applicable Not Applicable C. Actuation Systems Not Applicable Not Applicable
0 ~ P I
(~