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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
REACTOR COOLANT SYSTEH RECIRCULATION LOOPS - SINGLE LOOP OPERATION'-
LINITIHG COHOITIOH FOR OPERATION 3.4.1.1,2 One reactor. coolant recirculation loop shall be in operation with the pump speed < 80% of the rated puep speed, and
'a. the following revised specification lioits shall be followed:
- l. Specification 2. 1.2: the HCPR Safety Liait shall be increased to 1. 07.
- 2. Table 2. 2.1-1: the APRH Flow. Biased Scraa Trip Setpoints shall be as follows:
Tri Se oint Al 1owabl e Value
- 3. Specification 3.2. I: The HAPLHGR lisits shall be by 0.8+~
~ ultiplied by 4-.9. ), g
- 4. Specification 3.2.2: the AplN Setpoints shall be as follows:
Tri Set oint Al 1owabl e Value 1 + 55K)T l us,eRT SRB
< (0.58W + 46X)T S~ < (O.SSI + 4%)T Table 3. 3. 6-2: the RBM/APN Control Rod Block Setpoints shall be as fo1 1 ows:
- a. RBN - Upscale Tri Set oint Allowable Value
~ +
b, APRH-Flow Biased Tri Se oint Al 1 owabl e Value
~ +
- b. APRN and LPGA%'">> neutron flux noise levels'hall be less than three tiaes their established baseline levels when THElNAL PtNER is greater than the liait specified in Figure 3/4.1.1.1-1.
- c. Total core flow shall be greater than or equal to 42 aillion lbs/hr when THERNL REER is greater than the li it
~ specified in Figure 3.4.1.1.1-1.
'APPLICABILITY: OPERATIONAL CONOITIONS 1>> and 2>>, except during two loop operation. f SUSQUEHANNA
- UHIT 1 3/4 4 1c Ayendment Ho 72 IS%
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7'he AlbJlPiuW C,RITic.RL 70~ 6,R. RAT to (AC.PQQ Sbo.ll .be.. qve~+e+ 44am 0+ Cg0,O( +o 't++. (a+gCS+ O& '640 S~llotuv~g UMIAK,CS
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3/4. 4 REACTOR COOLAHT SYSTEH BaSES 3/4.4. 1 RECIRCULATIOH 'SYSTEH Operation with one reactor recirculation loop inoperable has been evaluated and found acceptable, provided that the unit is operated in accordance with Specification 3.4.1.1.2.
For .single loop operation, the RBM and APRM setpoints are adjusted by a 7X decrease in recirculation drive flow to account for the active loop drive flow that bypasses the core and goes up through the inactive loop jet pumps.
Surveillance on the pump speed of the operating recirculation loop is imposed to exclude the possibility of excessive reactor vessel internals vibr a-tion. Surveillance on differential temperatures below the threshold limits on THERHAL POWER or recirculation loop flow mitigates undue thermal stress on vessel nozzles, recirculation pumps and the vessel bottom head during extended operation in the single loop mode. The threshold limits are those values which wi ll sweep up the cold ~ater from the vessel bottom head.
THERHAL POWER, core flow, and neutron flux noise level limitations are pre-scribed in accordance with the recoenendations of General Electric Service Information Letter Ho. 380, Revision 1, "BWR Core Thermal Hydraulic Stability,"
dated February 10, 1984.
An inoperable jet poop is not, in itself, a sufficient reason to declare a recirculation loop inoperable, but it does, in case of a design-basis-accident, increase the blowdown area and reduce the capability of reflooding the core; thus, the requirement for shutdown of the facility with a jet pump inoperable.
Jet pump failure can be detected by monitoring jet pump performance on a prescribed schedule for significant degradation, Recirculation pump speed mismatch limits are in compliance with the ECCS LOCA analysis design criteria for two loop operation. The limits will ensu~e an adequate core flow coastdown from either recirculation loop following a LOCA.
In the case where the mismatch limits cannot be maintained during the loop operation, continued operation is permitted in the single loop code.
In order to prevent undue stress on the vessel nozzles and bottom head region, the recirculation loop temperatures shall be within 50 F of each other rior to star tup of an idle loop. The loop temperature must also be within 0 F of the reactor pressure vessel coolant temperature to prevent thermal shock to the recirculation p~ and recirculation nozzles. Since the coolant in the bottom of the vessel is at a lower temperature than the coolant in the upper regions of the core, undue stress on the vessel would result if the tem-perature difference was greater than 145'F.
SUSQUEHANHA - UHIT 1 B 3/4 4-1 Amendment Ho. 72
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