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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18066A6641999-09-30030 September 1999 Proposed Tech Specs Re Surveillance Implementation ML18066A6501999-09-17017 September 1999 Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8 ML18066A5911999-07-30030 July 1999 Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432 ML18066A5691999-07-19019 July 1999 Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS ML18066A5011999-06-11011 June 1999 Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9 ML18068A5851999-05-0303 May 1999 Proposed Tech Specs Section 3.5,converting to ITS ML18066A4551999-04-0707 April 1999 Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1 ML18066A4431999-03-30030 March 1999 Proposed Tech Specs Section 3.7,converting to ITS ML18066A4251999-03-22022 March 1999 Revised TS Pages for ITS Section 3.4 ML20207B2501999-03-0101 March 1999 Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS ML18066A3281998-11-0909 November 1998 Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17 ML20195E4451998-11-0909 November 1998 Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI ML20154N2901998-10-12012 October 1998 Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs ML20151Z8111998-09-14014 September 1998 Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1 ML18066A3021998-09-14014 September 1998 Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages ML18066A2011998-06-17017 June 1998 Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18065B1801998-03-13013 March 1998 Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown ML18067A8161998-01-26026 January 1998 Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20 ML18066A4901998-01-20020 January 1998 Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment. ML18067A7071997-10-0101 October 1997 Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12 ML18067A6731997-09-0303 September 1997 Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys ML18067A6771997-09-0303 September 1997 Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16 ML18067A6001997-06-27027 June 1997 Proposed Tech Specs Revising Electrical Power Systems ML18067A4701997-03-28028 March 1997 Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174 ML20137H5901997-03-27027 March 1997 Proposed Tech Specs Change Request Re Change in Co Name ML18067A4531997-03-26026 March 1997 Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18065B0331996-10-25025 October 1996 Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS ML18065B0171996-10-18018 October 1996 Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR ML18065A9551996-10-0202 October 1996 Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves ML18065A9111996-09-0404 September 1996 Proposed Tech Specs 3.7, Electrical Power Systems. ML20117K9581996-09-0303 September 1996 Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments ML18065A8631996-08-14014 August 1996 Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items ML18065A5861996-03-29029 March 1996 Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1 ML18065A4911996-02-0606 February 1996 Proposed Tech Specs Re Removal of cross-train Testing Requirements from LCO Action Statements ML18065A4411996-01-18018 January 1996 Proposed Tech Specs Allowing Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas ML18065A4361996-01-18018 January 1996 Proposed Tech Specs Re Primary Coolant Pump Flywheel Insps ML18065A4111996-01-10010 January 1996 Proposed Tech Specs,Requesting Exemption from 10CFR50 App J & TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg ML18065A3841996-01-0505 January 1996 Proposed Tech Specs,Revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage ML18065A3771995-12-27027 December 1995 Proposed Tech Specs,Rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS ML18065A3481995-12-11011 December 1995 Proposed Tech Specs,Revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 of TS Relocating in CPC Quality Program Description ML18065A3341995-12-0606 December 1995 Proposed Tech Specs,Relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage ML18065A1761995-10-17017 October 1995 Proposed Tech Specs,Changing Pressurizer Cooldown Limit from 100 to 200 F/H,Adding Word Shall to TS 3.1.2c,adding Average Hourly to Column Headings in TS 3.1.2c & Removing Action 3.3.3C from Page 3-31 to 3-30 ML18065A1241995-09-21021 September 1995 Proposed Tech Specs Re Diesel Generator Testing ML18064A8411995-07-0505 July 1995 Proposed Tech Specs,Deleting Section 6.4, Training, & Revising Sections 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff ML18064A7611995-05-0101 May 1995 Proposed Tech Specs Re Requirements for Periodic DG Peak Load Tests ML18064A7331995-04-27027 April 1995 Revised Proposed Ts,Consisting of Changes to Basis in First Paragraph of Page 3-2 & Rev to List of Approved Methodology Repts ML18064A7361995-04-27027 April 1995 Proposed Tech Specs,Supporting Action Statements for Inoperable Safety Valves in Proposed Specs 3.1.7 of TS Change Request of 950103 ML18064A6631995-03-30030 March 1995 Proposed Tech Specs for One Time Surveillance Deferment ML18064A6691995-03-24024 March 1995 Proposed TS Re pressure-temp Limits ML18064A6221995-02-20020 February 1995 Proposed TS Figure 3-4, LTOP Setpoint Limit. 1999-09-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18066A6641999-09-30030 September 1999 Proposed Tech Specs Re Surveillance Implementation ML18066A6501999-09-17017 September 1999 Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8 ML18066A5911999-07-30030 July 1999 Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432 ML18066A5691999-07-19019 July 1999 Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS ML18066A5011999-06-11011 June 1999 Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9 ML18068A5851999-05-0303 May 1999 Proposed Tech Specs Section 3.5,converting to ITS ML18066A4551999-04-0707 April 1999 Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1 ML18066A4431999-03-30030 March 1999 Proposed Tech Specs Section 3.7,converting to ITS ML18066A4251999-03-22022 March 1999 Revised TS Pages for ITS Section 3.4 ML20207B2501999-03-0101 March 1999 Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS ML18066A3281998-11-0909 November 1998 Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17 ML20195E4451998-11-0909 November 1998 Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI ML20154N2901998-10-12012 October 1998 Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs ML18066A3021998-09-14014 September 1998 Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages ML20151Z8111998-09-14014 September 1998 Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1 ML18066A2011998-06-17017 June 1998 Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses ML18066A1841998-06-10010 June 1998 Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period. ML18068A3451998-04-29029 April 1998 Rev 9 to EI-9, Offsite Radiological Monitoring. ML18068A3441998-04-28028 April 1998 Rev 3 to EI-6.6, Gamma E Determination. ML18065B2271998-04-21021 April 1998 Reactor Vessel Neutron Fluence Methodology. ML20217C3101998-03-24024 March 1998 Palisades,Review of Actual Fluence Determination ML18065B1801998-03-13013 March 1998 Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown ML18065B2021998-03-10010 March 1998 Rev 7 to Relocated TS Per GL 89-09. ML18067A8161998-01-26026 January 1998 Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20 ML18066A4901998-01-20020 January 1998 Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment. ML20197G3851997-12-17017 December 1997 Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan ML18065B2321997-10-24024 October 1997 Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment. ML18067A7071997-10-0101 October 1997 Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12 ML18067A6731997-09-0303 September 1997 Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys ML18067A6771997-09-0303 September 1997 Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16 ML18067A6001997-06-27027 June 1997 Proposed Tech Specs Revising Electrical Power Systems ML18067A4701997-03-28028 March 1997 Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174 ML20137H5901997-03-27027 March 1997 Proposed Tech Specs Change Request Re Change in Co Name ML18067A4531997-03-26026 March 1997 Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown ML18067A5151997-02-11011 February 1997 Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment. ML18065B2011996-12-24024 December 1996 Rev 11 to Offsite Dose Calculation Manual. ML18065B0861996-11-27027 November 1996 Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20. ML20134P4071996-11-19019 November 1996 Suitability,Training & Qualification Plan, Rev 16 ML20137G3871996-10-29029 October 1996 Rev 6 to Relocated TS Per NRC GL 89-09 ML18065B0331996-10-25025 October 1996 Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS ML18065B0171996-10-18018 October 1996 Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR ML18065A9551996-10-0202 October 1996 Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves ML18065A9111996-09-0404 September 1996 Proposed Tech Specs 3.7, Electrical Power Systems. ML20117K9581996-09-0303 September 1996 Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments ML18065A8631996-08-14014 August 1996 Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items ML18065A7661996-06-10010 June 1996 Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys. ML18065A7651996-06-10010 June 1996 Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys. ML18065A5861996-03-29029 March 1996 Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1 ML18065A8021996-02-21021 February 1996 Rev 2 to EM-09-13, ISI Pressure Testing Program. ML20137G3631996-02-16016 February 1996 Rev 10 to Offsite Dose Calculation Manual 1999-09-30
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* ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST VARIABLE HIGH POWER TRIP SETPOINT CHANGE PROPOSED CHANGED PAGES May 30, 1991 3 Pages
- TABLE 2.3.1 Reactor Protective Svstem Trip Setting Limits 1. Variable High Power<1> 2. Primary Cool ant Fl ow<2> 3. High Pressure Pressurizer
- 4. Thermal Low Pressure'2* > 5. Steam Generator Low Water Level 6. Steam Generator Low Pressure<2> 7. Containment High Pressure Four Primary Coolant Pumps Operating above core power, with a minimum setpoint of of rated power and a maximum of of rated power of Primary Coolant Flow With Four Pumps Operating Psia P1;ri1? Applicable L1m1ts Not Lower Than the Center Line of Feed-Water Ring Psia Psig Three Primary Coolant Pumps Op er at i ng<4>
above core power with a minimum setpoint of rated power and a maximum of of rated power of Primary ant Flow With Four Pumps Operating Psia Replaced by Variable High Power Trip and 1750 Psia Minimum Pressure Setting Not Lower Than the Center Line of Feed-Water Ring Psia Psig (1) The VHPT can be 30% of rated power for power levels 20% of rated power. (2) May be bypassed below 10-4% of rated power provided auto bypass removal circuitry is operable.
For low power physics tests, thermal margin/low pressure, primary coolant flow and low steam generator pressure trips may be bypassed until their react points are reached (approximately 1750 psia and 500 psia, respectively), provided automatic bypass removal circuitry at 10-1% rated power is operable.
(3) Minimum trip setting shall be 1750 psia. (4) Operation with three pumps for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is permitted to provide a limited time for repair/pump restart, to provide for an orderly shutdown or to provide for the conduct of reactor internals noise monitoring test measurements.
2-5 Amendment No. $J, TSCR9104.CTH
- * . 2.3 LIMITING SAFETY SYSTEM SETTINGS -REACTOR PROTECTIVE SYSTEM (Contd) The reactor protective system consists of four instrument channels to monitor selected plant conditions which will cause a reactor trip if any of these conditions deviate from a preselected operating range to the degree that a safety limit may be reached. 1. Variable High Power -The variable high power trip (VHPT} is incorporated in the reactor protection system to provide a reactor trip for transients exhibiting a core power increase starting from any initial power level (such as the boron dilution transient).
The VHPT system provides a trip setpoint no more than a Rredetermined amount above the indicated core power
> and also sets a maximum value. Operator action is required to increase the setpoint as core power is increased; the setpoint is automatically decreased as core power decreases.
Provisions have been made to select different set points for three pump and four pump operations.
- 2. TSCR9104.CTH During normal plant operation with all primary coolant pumps operating, reactor trip is initiated when the reactor power level reaches 106.5% of indicated rated power. Adding to this the possible variation in trip point due to calibration and instrument errors, the maximum actual steady state power at which a trip would be actuated is 115%, which was used for the purpose of safety analysis.
<4> Primary Coolant System Low Flow -A reactor trip is provided to protect the core against DNB should the coolant flow suddenly decrease significantly.<
3> Flow in each of the four coolant loops is determined from a measurement of pressure drop from inlet to outlet of the steam generators.
The total flow through the reactor core is measured by summing the loop pressure drops across the steam generators and correlating this pressure sum with the pump calibration flow curves. The percent of normal core flow is shown in the following table: 4 Pumps 3 Pumps 100.0% 74.7% During four-pump operation, the low-flow trip setting of 95% insures that the reactor cannot operate when the flow rate is Less than 93% of the nominal value considering instrument errors. <4> 2-6 Amendment No. pJ, Jpl
- 2.3 LIMITING SAFETY SYSTEM SETTINGS -REACTOR PROTECTIVE SYSTEM (Contd) Basis (Contd) 6. Low Steam Generator Pressure -A reactor trip on low steam generator secondary pressure is provided to protect against an excessive rate of heat extraction from the steam generators and subsequent cooldown of the primary coolant. The setting of 500 psia is sufficiently below the rated load operating point of 739 psia so as not to interfere with normal operation, but still high enough to provide the required protection in the event of excessively high steam flow. This setting was used in the accident analysis.
7. Containment High Pressure -A reactor trip on containment high pressure is provided to assure that the reactor is shutdown before the initiation of the safety injection system and containment spray. <10> 8. Low Power Phvsics Testing -For low power physics tests, certain tests will require the reactor to be critical at low temperature and low pressure psia). For these certain tests only, the thermal margin/low pressure, primary coolant flow and low steam generator pressure trips may be bypassed in order that reactor power be increased for improved data acquisition.
Special operating precautions will be in effect during these tests in accordance with approved written testing procedures.
At reactor power levels below 10-1% of rated power, the thermal margin/low-pressure trip and low flow trip are not required to prevent fuel rod thermal limits from being exceeded.
The low steam generator pressure trip is not required because the low steam generator pressure will not allow a severe reactor cooldown, should a steam line break occur during these tests. References (1) ANF-91-181, Section 15.0.7 (2) deleted (3) Updated FSAR, Section 7.2.3.3. (4) ANF-90-078, Section 15.0.7 (5) XN-NF-86-9l(P)
(6) deleted (7) deleted (8) ANF-90-078, Section 15.1.5 (9) ANF-87-150(NP), Volume 2, Section 15.2.7 (10) Updated FSAR, Section 7.2.3.9. (11) ANF-90-078, Section 15.2.1 2-9 Amendment No. $1, J$7 TSCR9104.CTH
- ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 TECHNICAL SPECIFICATIONS CHANGE REQUEST VARIABLE HIGH POWER TRIP SETPOINT CHANGE EXISTING PAGES WITH PROPOSED CHANGES MARKED May 30, 1991 3 Pages
- TABLE. 2.3.1 Reactor Protective System Trip Setting Limits Four Primary Coolant Pumps Operating Three Primary Coolant Pumps
- 1. Variable High Power'1> \5%
above core power, with a minimum setpoint of of rated power and a maximum of of rated power core power with a minimum setpoint of rated power and a maximum of of rated power 2. Primary Cool ant Fl ow<2>
of Primary Coolant Flow With Four Pumps Operating of Primary ant Flow With Four Pumps Operating
- 3. High Pressure Pressurizer Psia Psia 4. Thermal Marginf, Low Pressure<2* > Ptrlp Limits Replaced by Variable High Power Trip and 1750 Psia Minimum Pressure Setting 5. Steam Generator Low Water Level Not Lower Than the Center Line of Feed-Water Ring Not Lower Than the Center Ltne of Feed-Water Ring 6. Steam Generator Low Pressure<2>
Psia Psia 7. (1) (2) (3) (4) Containment High Pressure Psig ** . .:*** .. 'l -. ; The VHPT can be 30% of rated for power levels 20% of rated power. . -* * .. * * , ** -May be bypassed below 10-43 of rated power provided auto bypass removal circuitry is operable.
For low power physics tests, thermal margin/low pressure, primary coolant flow and low steam generator pressure trips may be bypassed until their react points: .. reached .. (approx*imately 1750 psi a and 500 psi respectively), provided automatic bypass removal circuitry at 10-1% rated power* is
- Minimum trip setting shall be 1750 psia. Operation with three pumps for a maximum of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is permitted to provide a limited time for repair/pump restart, to provide for an orderly shutdown or to provide for the conduct of reactor internals noise monitoring tesf measurements.
2-5 Amendment No.
138 February 22, 1991
- 2.3 LIMITING SAFETY SYSTEM SETTINGS -REACTOR PROTECTIVE SYSTEM (Contd) The reactor protective system consists of four instrument channels to monitor selected plant conditions which will cause a reactor trip if any of these conditions deviate from a preselected operating range to the degree that a safety limit may be reached. 1. Variable High Power -The variable high power trip (VHPT) incorporated in the reactor protection system to provide a reactor trip for transients exhibiting a core power increase starting from any initial power level (such as the boron dilution transient).
The VHPT system provides a trip setpoint no more (I) than a predetermined amount above the indicated core Ai-lC AL?o I Operator action is required to increase the setpoint as core A power is increased; the setpoint is automatically decreased as core power decreases.
Provisions have been made to select different set points for three pump and four pump operations.
During normal plant operation with all primary coolant pumps ope rat i n*g, reactor trip is initiated when the reactor power level reaches 106.5% of indicated rated power. Adding to this the possible variation in trip point due to calibration and instrument errors, the maximum actual steady state power at which a trip would be actuated is 115%, which was used for the purpose l of safety analysis.-<-1+-
Cq) 2. Primary Coolant System Low Flow -A reactor trip is provided to protect the core against DNB should the coolant flow suddenly decrease significantly.<
3> Flow in each of the four coolant loops is determined from a measurement of pressure drop from inlet to outlet of the steam generators.
The total flow through the reactor core is measured by summing the loop pressure drops across the steam generators and correlating this pressure sum with the pump calibration flow curves. The percent of normal core flow is shown in the following table: 4 Pumps 3 Pumps 100.0% 74.7% During four-pump operation, the low-flow trip setting of 95% insures that the reactor cannot operate when the flow rate is Less than 93% of the nominal value considering instrument errors. <4> 2-6 Amendment No. $J, 137 February 20, 1991
2.3 LIMITING
SAFETY SYSTEM SETTINGS -REACTOR PROTECTIVE SYSTEM (Contd) Basis (Contd) 6. Low Steam Generator Pressure -A reactor trip on low steam generator secondary pressure is provided to protect against an excessive rate of heat extraction from the steam generators and subsequent cooldown of the primary coolant. The setting of 500 psia is sufficiently below the rated load operating point of 739 psia so as not to interfere with normal operation, but still high enough to provide the required protection in the event of excessively high steam flow. This setting was used in the accident analysis.
ca> 7. Containment High Pressure -A reactor trip on containment high pressure is provided to assure that the reactor is shutdown before the initiation of the safety injection system and containment spray. <10> . 8. Low Power Physics Testing -For low power physics tests, certain tests will require the reactor to be critical at low temperature and*low pressure psia). For these certain tests only, the thermal margin/low pressure, primary coolant flow and low steam generator pressure trips may be bypassed in order that reactor power can be increased for improved data acquisition.
Special operating precautions will be in effect during these tests in accordance with approved written testing procedures.
At reactor power levels below 10-1% of rated power, the thermal margin/low-pressure trip and low flow trip are not required to prevent fuel rod thermal limits from being exceeded.
The low steam generator pressure trip is not required because the low steam generator pressure will not allow a severe reactor cooldown, should a steam line break occur during these tests. References ANF-C\t-1e1>
5ec.T1oto1 1c;.o.1 (1) ANF 98 878, Tahle 16.8.7 1 (2) deleted (3) Updated FSAR, Section 7.2.3.3. (4) AHF 98 878, Sectiou 15.8.1 1 i\NF-90:--016i SEc..'T10H.
\S.0 .. 1 (5) XN-NF-86-9l(P)
(6) deleted (7) deleted (8) ANF-90-078, Section 15.1.5 (9) ANF-87-150(NP), Volume 2, Section 15.2.7 {10) Updated FSAR, Section 7.2.3.9. {11) ANF-90-078, Section 15.2.1 2-9 Amendment No.
137 February 20, 1991