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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18040B2891999-03-12012 March 1999
Proposed Tech Specs Including Rev 0 to EMF-1997(P)(A) Into TS Section 5.6.5 & Including Revised MCPR Safety Limits in TS Section 2.1.1.2
ML18040B2881999-01-12012 January 1999
Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML17164A6711998-07-0808 July 1998
Proposed Tech Specs,Implementing Improved Tech Specs of NUREG-1433.Page B3.8-1 of Incoming Submittal Not Included
ML17159A3261998-05-12012 May 1998
Proposed Tech Specs Re Removal of Fire Protection Program
ML18026A4711997-02-11011 February 1997
Proposed Tech Specs Requesting Improved TSs LCO 3.10.3 & LCO 3.10.4 Be Approved for Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315
ML20129D7851996-09-23023 September 1996
Proposed Tech Specs Re MSIVs Leakage Testing
ML20116K3491996-08-0909 August 1996
Proposed Tech Specs Re Battery Load Profiles
ML17158B5581996-03-20020 March 1996
Proposed Tech Specs,Changing Open Logic for HPCI Suction Valve HV-155/255-F042 in Order to Eliminate HPCI Pump auto- Transfer on High Suppression Pool Level
ML20115A8171996-02-29029 February 1996
Proposed Tech Specs,Relocating Spec 3/4.9.6, Refueling Platform to Document Which Is Controlled Under Requirements of 10CFR50.59
ML20115A8211996-02-29029 February 1996
Proposed Tech Specs,Removing Rod Block Monitor Requirements from TS by Reducing Number of Rod Movements During Power Maneuvers
ML17158B1071996-02-12012 February 1996
Proposed Tech Specs to Implement 10CFR50,App J,Option B & Establish New Spec 6.8.5, Primary Containment Leakage Rate Testing Program.
ML17164A5801995-02-10010 February 1995
Proposed Tech Specs for Aot/Sti Extensions
ML17164A4351994-11-21021 November 1994
Proposed Tech Specs Increasing MSIV Leakage Rate & Deleting MSIV-LCS
ML17158A5441994-10-28028 October 1994
Proposed Tech Specs,Incorporating Administrative Changes
ML20058F8281993-11-24024 November 1993
Proposed Tech Specs Re Power Uprate W/Increased Flow
ML17157C2741993-04-0202 April 1993
Proposed TS 3.4.1.1.2 Re LCO for Recirculation Loops,Single Loop Operation
ML20082P1871991-09-0404 September 1991
Proposed Tech Specs for HPCI Sys Low Pressure Surveillance Test Acceptance Criteria
ML17157A3371990-09-24024 September 1990
Proposed Tech Specs in Support of Facility Cycle 5 Reload
ML17157A2441990-07-0202 July 1990
Proposed Tech Specs to Support Cycle 6 Reload
ML19325D7491989-10-19019 October 1989
Proposed Tech Specs 3.2.2 Eliminating Certain Requirements on One Time Basis for 3 Months
ML17156B1101989-04-14014 April 1989
Proposed Tech Specs,Making Changes to Emergency Svc Water Sys,Per 10CFR50,App R
ML17156A7291988-08-10010 August 1988
Proposed Tech Specs,Extending Operation During Cycle 4 W/ One Recirculation Loop Out of Svc
ML18040A8741988-04-0606 April 1988
Proposed Tech Specs Re Radiation Monitoring Instrumentation
ML17146B0891987-12-23023 December 1987
Proposed Tech Specs Index & Sections 3/4.2.1,3/4.2.2, 3/4.2.3,3/4.2.4,3/4.3.6,3/4.4.1,B 2.1,B 3/4.2.1,B 3/4.2.2, B 3/4.2.3 & B 3/4.4.1,to Support Cycle 3 Reload
ML18040A8421987-06-10010 June 1987
Proposed Tech Specs,Increasing Load Profile for Batteries 1D612 & 1D622
ML18040A8341987-04-16016 April 1987
Proposed Tech Spec 4.1.3.1.4(a) Changing Requirements for Surveillance of Scram Discharge Vol Vent & Drain Valves
ML18040A8261987-02-0909 February 1987
Proposed Tech Specs,Allowing Alternate Method of post-accident Drywell Gaseous Sampling & Providing Relief for Unnecessarily Restrictive Action Statement on Drywell Oxygen Analyzer
ML20215C1291986-12-0909 December 1986
Proposed Tech Spec Tables 3.6.3-1 & 3.8.4.2-1,supporting Mods to Improve Containment Isolation Function & Testability of Feedwater Sys
ML17146A4811986-08-0505 August 1986
Proposed Administrative Changes to Tech Specs
ML20206J9471986-06-23023 June 1986
Proposed Tech Specs Changing Main Steam Line Radiation High Setpoint from Three Times Background to Seven Times Background
ML17146A4161986-06-19019 June 1986
Proposed Tech Specs Re Cycle 2 Reload.Nshc Encl
ML17146A3111986-03-27027 March 1986
Proposed Tech Spec Changes Providing Editorial Correction to Previously Approved Change for Unit 1 & Supporting Mods Which Enhance Capability of Drywell Cooling Sys for Unit 2
ML20141C9281986-03-27027 March 1986
Proposed Tech Specs Re Recirculation Sys W/One & Two Loop Operation,Supporting Operation W/One Recirculation Loop Out of Svc
ML17146A2681986-02-10010 February 1986
Proposed Tech Specs,Reflecting Incorporation of Fifth Diesel Generator Into Plant Design
ML20137G5781985-11-26026 November 1985
Proposed Tech Specs,Deleting Requirement for Operability of Refueling Floor Wall & High Exhaust Ducts & Railroad Access Exhaust Duct Radiation Monitoring Sys for Conditions 1,2 & 3
ML17156A1261985-04-11011 April 1985
Proposed Tech Spec Changes Re Single Loop Operation Requirement
ML18040A7701985-02-11011 February 1985
Proposed Tech Specs Re Util Review Committee Membership
ML17139C7431984-12-0606 December 1984
Proposed Tech Specs Separating Unit 1 from Unit 2 Battery Loads to Avoid Forced Shutdown of Unit 2 During Unit 1 Refueling Outage
ML18040A7421984-09-24024 September 1984
Proposed Tech Specs,Revising Table 3.3.7.1-1, Radiation Monitoring Instrumentation.
ML18040A7411984-09-0707 September 1984
Proposed Tech Specs Re Primary Containment Isolation Valves & Containment Sys Limiting Condition for Operation & Bases
ML20078M6531983-10-20020 October 1983
Proposed Changes to Tech Spec Table 4.8.1.1.2-2 Re Settings for Emergency Svc Water Pump Timers
ML17139B3301983-02-0303 February 1983
Proposed Tech Specs 2.2.1.1,3.2.2,4.2.2 & 3.3.6-2 Re Reactor Protection Sys Instrumentation,Average Power Range Monitor & Control Rod Block Instrumentation Setpoints
ML17139B3311983-02-0303 February 1983
Proposed Tech Specs 3.4.3 & 4.4.3 Re RCS Leakage Detection Sys
ML18031A4031982-10-19019 October 1982
Proposed Changes to Tech Spec Table 3.8.4.1-1 to Include More Conservative Type 2 Molded Case Circuit Breakers & to Add Previously Omitted Type 3 Molded Case Circuit Breakers
1999-03-12
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18040B2891999-03-12012 March 1999
Proposed Tech Specs Including Rev 0 to EMF-1997(P)(A) Into TS Section 5.6.5 & Including Revised MCPR Safety Limits in TS Section 2.1.1.2
ML18040B2881999-01-12012 January 1999
Proposed Tech Specs Re ANFB-10 Critical Power Correlation & MCPR Safety Limits
ML17164A6711998-07-0808 July 1998
Proposed Tech Specs,Implementing Improved Tech Specs of NUREG-1433.Page B3.8-1 of Incoming Submittal Not Included
ML17159A3261998-05-12012 May 1998
Proposed Tech Specs Re Removal of Fire Protection Program
ML20199C8741997-10-22022 October 1997
Rev 0 to NASI-00-507, Corrective Action Process Effectiveness Assessment
ML18026A4711997-02-11011 February 1997
Proposed Tech Specs Requesting Improved TSs LCO 3.10.3 & LCO 3.10.4 Be Approved for Use During Susquehanna Ses Unit 2 Eighth Refueling & Insp Outage Scheduled for 970315
ML17158C0321997-01-0808 January 1997
Rev 4, Solid Radwaste Pcp.
ML20129D7851996-09-23023 September 1996
Proposed Tech Specs Re MSIVs Leakage Testing
ML20116K3491996-08-0909 August 1996
Proposed Tech Specs Re Battery Load Profiles
ML17158B5581996-03-20020 March 1996
Proposed Tech Specs,Changing Open Logic for HPCI Suction Valve HV-155/255-F042 in Order to Eliminate HPCI Pump auto- Transfer on High Suppression Pool Level
ML20115A8211996-02-29029 February 1996
Proposed Tech Specs,Removing Rod Block Monitor Requirements from TS by Reducing Number of Rod Movements During Power Maneuvers
ML20115A8171996-02-29029 February 1996
Proposed Tech Specs,Relocating Spec 3/4.9.6, Refueling Platform to Document Which Is Controlled Under Requirements of 10CFR50.59
ML17158B1071996-02-12012 February 1996
Proposed Tech Specs to Implement 10CFR50,App J,Option B & Establish New Spec 6.8.5, Primary Containment Leakage Rate Testing Program.
ML17158A6821995-04-26026 April 1995
Rev 3 to Nuclear Dept Procedure ON-100-009, Control Room Evacuation.
ML17158A6841995-04-13013 April 1995
Rev 3 to Nuclear Dept Procedure ON-200-009, Control Room Evacuation.
ML20081L9151995-03-14014 March 1995
Rev 1 to NS-ST-002, Security Training & Crucial Security Task Certification
ML17164A5801995-02-10010 February 1995
Proposed Tech Specs for Aot/Sti Extensions
ML17164A5891995-01-20020 January 1995
Rev 2 to PP&L SSES Odcm.
ML17164A4351994-11-21021 November 1994
Proposed Tech Specs Increasing MSIV Leakage Rate & Deleting MSIV-LCS
ML17158A5441994-10-28028 October 1994
Proposed Tech Specs,Incorporating Administrative Changes
ML20058F8281993-11-24024 November 1993
Proposed Tech Specs Re Power Uprate W/Increased Flow
ML17157C3881993-05-31031 May 1993
Rev 8 to ISI-T-100.0, ISI Program Plan for Pump & Valve Operational Testing.
ML17157C3901993-05-31031 May 1993
Rev 5 to ISI-T-200.0, ISI Program Plan for Pump & Valve Operational Testing.
ML18017A2671993-04-20020 April 1993
Exercise Manual.
ML17157C2741993-04-0202 April 1993
Proposed TS 3.4.1.1.2 Re LCO for Recirculation Loops,Single Loop Operation
ML18017A2631992-05-0606 May 1992
Emergency Exercise Std for Conduct in Performance of 920219 NRC Graded Exercise
ML20113G9881992-02-19019 February 1992
Package Providing Basis for Conduct of Simulated Radiological Accident at Plant
ML17157B0081991-12-31031 December 1991
Rev 7 to ISI-T-100.0, Sses,Unit 1,ISI Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04
ML17157B0101991-12-31031 December 1991
Rev 4 to ISI-T-200.0, Sses,Unit 2,ISI Program Plan for Pump & Valve Operational Testing, Per Generic Ltr 89-04
ML18017A2591991-10-16016 October 1991
Exercise Manual, Approved by Util as Std for Conduct in Performance of 911016 NRC Graded Exercise
ML20082P1871991-09-0404 September 1991
Proposed Tech Specs for HPCI Sys Low Pressure Surveillance Test Acceptance Criteria
ML17157A3381990-09-30030 September 1990
Cycle 5 Reload Summary Rept.
ML17157A3371990-09-24024 September 1990
Proposed Tech Specs in Support of Facility Cycle 5 Reload
ML17157A2441990-07-0202 July 1990
Proposed Tech Specs to Support Cycle 6 Reload
ML17157A0891990-03-19019 March 1990
Rev 0 to Procedure MT-024-024, Diesel Engine Analysis & Load Balancing.
ML17157A0871990-03-19019 March 1990
Rev 0 to Procedure TP-024-087, Data Collection for E Diesel Generator Combustion Intake Air Temp Test.
ML20127B4271990-01-19019 January 1990
Rev 8 to Procedure MT-GE-008, 480 Volt & Under Circuit Breaker High Current Testing
ML19325D7491989-10-19019 October 1989
Proposed Tech Specs 3.2.2 Eliminating Certain Requirements on One Time Basis for 3 Months
ML20082C4101989-08-16016 August 1989
Spec Change Notice 7 to Rev 4 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML17156B1101989-04-14014 April 1989
Proposed Tech Specs,Making Changes to Emergency Svc Water Sys,Per 10CFR50,App R
ML17156B0671989-03-31031 March 1989
Rev 3 to ISI-T-200.0, Pump & Valve Inservice Insp Testing Program.
ML17156B0651989-03-31031 March 1989
Rev 6 to ISI-T-100.0, Pump & Valve Inservice Insp Testing Program.
ML20082C4071989-03-23023 March 1989
Spec Change Notice 6 to Rev 4 to F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML17156B1391989-02-22022 February 1989
Rev 12 to EO-100-009, Plant Shutdown from Outside Control Room.
ML20082B2771989-01-0404 January 1989
Rev 4 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML20082C3731988-11-0707 November 1988
Spec Change Notice 5 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML20082C3711988-11-0101 November 1988
Spec Change Notice 4 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML20082C3641988-10-14014 October 1988
Spec Change Notice 3 to Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
ML17156A7291988-08-10010 August 1988
Proposed Tech Specs,Extending Operation During Cycle 4 W/ One Recirculation Loop Out of Svc
ML20082B2911988-07-11011 July 1988
Rev 3 to TS F1000, TS for Design & Installation of Electrical Raceway Fire Barriers
1999-03-12
[Table view] |
Text
<'rr Oar r TABLE 2.2.1-1
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REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS lQ C5% TT;.
, DOc.. ALLOWABLE OQ p?'M FUNCTIONAL UNIT TRIP SETPOINT VALUES 2-'-
Op...
O VIII 2
- l. Intermediate Range Monitor, Neutron Flux-High < 120/125 divisions < 122/125 divisions OQ
'OO~.
<-"-'=
?
of full scale of full scale
- OlQ
'UMO~'~f 2. Average Power Range Monitor:
(
. arne a. Neutron Flux-Upscale, Setdown < 15K of RATED THERMAL POWER < 20K of RATED THERMAL POWER
- b. Flow Biased Simulated Thermal Power-Upscale O. 58 W+5V% 5.s8 W+(2.%
- 1) Flow Biased t?l?t???t, t tt a maximum of a maximum of
- 2) High Flow Clamped < 113.5X of RATED < 115.5X of RATED THERMAL POWER THERMAL POWER
- c. Neutron Flux-Upscale < 118'f RATED THERMAL POWER < 120X of RATED THERMAL POWER P d.. Inoperative MA
.-3. Reactor Vessel Steam Dome Pressure - High < 1037 psig < 1057 psig
- 4. Reactor Vessel Water Level - Low, Level 3 13.0 inches above Tnstr ument zero*
> 11.5 inches above Tnstrument zero .
~
- 5. Main Steam Line Isolation Valve - Closure
< 10X closed < ill closed 0
- 6. Main Steam Line Radiation High . < 3.0 x full power < 3.6 x full power background . Sackground 0
- 7. Drywell Pressure - High < 1 72 psig < 1.88 psig
- 8. Scram Discharge Volume Water Level - High < 88 gallons < 88 gallons
- 9. Turbine Stop Valve - Closure < 5.5X closed < 7X closed
-10. Turbine Control Valve Fast Closure, Trip Oil Pressure - Low > 500 psig > 460 psig Reactor Mode Switch Shutdown Positiotr NA NA I
- 12. Manual Scram NA NA See Bases Figure 3/4 3-1.
6
~ V 4 II r
t I PtU tlPlhBEABVjf~~
A'4,'j'$>> j] q ~ 'VsyA'gj g"",.':, + +, ~ ." '~Z .", 'g,"
0'OWER
~2%3 DISTRIBUTION LIMITS 3/4.2.
~ ~ 2 APRM SETPOINTS LIMITING CONDITION FOR OPERATION 3.2.2 The APRM flow biased simulated thermal power-upscale scram trip setpoint (S) and flow biased neutron flux-upscale control rod block trip setpoint (SRB) shall be established according to the following relationships:
~6'if~~
Tri Set oint Allowable Value S < 6 (aesW~Sg/)W S < i'o.58'wes27.)T'&E SRB
< h%T (0.58W+Q7)~ S ERT.'PT where: S and S B
are in percent of RATED THERMAL POWER, M = too/recirculation flow as a percentage of the ioop recirculation flow which produces a rated core flow of 100 million lbs/hr, T = Lowest value of the ratio of FRACTION OF RATED THERMAL POWER divided by the MAXIMUM FRACTION OF LIMITING POWER DENSITY. T is always less than or equal to 1.0.
APPLICABILITY: OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or
~q R TEO THEREAT PO EE.
ACTION:
With the APRM flow biased simulated thermal power-upscale scram trip setpoint and/or the flow biased neutron flux-upscale control rod block trip setpoint less conservative than the value shown in the Allowable Value column for S or S B, as above determined, initiate corrective action within 15 minutes and adjust 3 and/or S to be consistent with the Trip Setpoint value" within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or reduce. THERMAL PIER to less than 25K of RATED THERMAL POWER within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
SURVEILLANCE RE UIREMENTS 4.2.2 The FRTP and the MFLPD shall be determined, the value of T calculated, and the most recent actual APRM flow biased simulated thermal power-upscale scram and flow biased neutron flux-upscale control rod block trip setpoints verified to be within the above limits or adjusted, as required: e
- a. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s, ~ cs
- b. Within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after completion of a THERMAL POWER increase of at least 15K of RATED THERMAL POWER, and
- c. Initially and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the reactor is operating with MFLPD greater than or equal to FRTP.
With MFLPD greater than the FRTP during power ascension up to 90K of RATED THERMAL POWER, rather than adjusting the APRM setpoints, the APRM gain may be adjusted such that APRM readings are greater than or equal to 100X times MFLPD, provided that the adjusted APRM reading does not exceed lOOX of RATED THERMAL POWER, the req'uired gain adjustment increment does not exceed 10K of RATED THERMAL POWER, and a notice of the adjustment is posted on the reactor control panel.
SUSQUEHANNA - UNIT 1 3/4 2-5
'0 I
l ~
3 v
e s TABLE 3.3.6-2 CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS TRIP. FUNCTION TRIP SETPOINT ALLOWABLE VALUE
- 1. 'ROD BLOCK MONITOR
- a. Upscal e < 0.66 W + 40X < 0.66 W+ 43X
- b. Inoperative NA NA
- c. Downscale > 5/125 divisions of full scale > 3/125 of divisions full scale
- 2. APRM
- a. Flow Biased Neutron o.5& w + jo7." o. 58 W + 5>7.
Flux - Upscale
- b. Inoperative NA NA
- c. Downscale > 5X of RATED THERMAL POWER > 3X of RATED THERMAL POWER
- d. Neutron Flux - Upscale Startup < 12X of RATED THERMAL POWER < 14X of RATED THERMAL POWER
- 3. SOURCE RANGE MONITORS as Detector not full in NA NA
- b. Upscale < 2x 10 cps < 4 x 10 cps C. Inoperative NA ~ NA
- d. Downscale ) 3 cp s*'A > 2 cps*"
4.,INTERMEDIATE RANGE MONITORS
- a. .Detector not full in NA NA
- b. Upscale < 108/125 divisions of full scale < 1-10/125.divisions of full scale
- c. Inoperative HA NA
- d. Downscale > 5/125 divisions of full scale > 3/125 divisions of full scale
- 5. SCRAM DISCHARGE VOLUME
- a. Water Level - High < 44 gallons < 44 gallons
- 6. REACTOR COOLANT SYSTEM RECIRCULATION FLOW
- a. Upscal e < 108/125 divisions of full scale 111/125 divisions of full scale
- b. Inoperative NA NA
- c. Comparator < 10X flow deviation 11X flow deviation The Average Power Range Monitor rod block function is varied as a function of recirculation loop flow
). The trip setting of this function must be m ., oined in accordance with Specification 3.2.2.
initial loading and startup the count rate ma, ".-.: > 0. 5 cps.
'0 ~'
I I Fg
