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| {{#Wiki_filter:5.CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable rod positions shall be logged once per shift and after a load change greater than l(5 of rated power.If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 935 of rated power.6.POWER DISTRIBUTION L IHITS a.Hot channel factors: (1)With steam generator tube plugging>225 and<25K, the hot channel factors (defined in the basis)must meet the following limits at all times except during low power physics tests: Fq (Z)<(2e03'/P)x K(Z)>for P>~5 Fq (Z)<(4.06)x K(Z), for P<.5 F H<1.55[l.+0.2 (1-P)j Where P'is the fraction of.rated power at which the core is operating; K(Z)is the function given in Figure 3.2-3b;Z is the core height location of Fq If F , as predicted by approved physics calculations, exceeds 2.03, the power will be limited to the rated power multiplied by the ration of 2.03 divided by the predicted F , or augmented surveil.lance of hot channel factors shall be implemented. | | {{#Wiki_filter:5. CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable rod positions shall be logged once per shift and after a load change greater than l(5 of rated power. If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 935 of rated power. |
| (2)With steam generator tube plugging<22K, the hot channel factors (defined in the basis)must meet the following limits at all times except during low power physics tests: Fq (Z)<'2e 10/P)x K(Z)p for P>e5 F (Z)<(4.20)x K(Z), for P<.5 F H<1.55[1.+0.2 ('1-P)]Where P is the fraction of rated power at which the core is operating; K(Z)is the function given in either Figure 3.2-3 or 3.2-3a;Z is the core height location of Fq.3~2 2-27-80 soosoao+Pg 0 0 l P J~g t TABLE 4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Descri tion 1.Nuclear Power Range (Check, Calibrate and Test only applicable above 10$of rated power.)Check S (1)M*(4)Calibrate Test D (2)M (3)Q*(4)Remarks 1)Load v.s.flux curve 2)Thermal power calculation 3)Signal to T;bistable action (permissive, rod stop;trips)4)Upper 8 lower detectors for symmetric offset (+5 to-5X)'.Nucl ear Intermediate Range S (1)~N.A.P (2)1)Once/shift up to 50K, R.P.2)Log level;bistable action (permissive, rod stop, trip)3.Nuclear Source Range S (1)N.A.P (2)1)Once/shift when in service 2)Bistable action (alarm, trip)4.Reactor Cool ant Temperature S B/W (1)1 (2)~1)Overtemperature-T 2)Overpower-T 5.Reactor Coolant Flow 6.Pressurizer Water Level 7.Pressurizer Pressure 8.4 kv Voltage 8 Frequency 9.Analog Rod Position N.A.R(1)M1 Reactor protection circuits only With step counters 1)Calibrate indicated position to within 12 steps of actual position 2-27-80 0'l r.1I I~<6 (P-4 f C'C I l F l V 1 , t STATE''OF FLORlDA))COUNTY OF DADE)ss Robert E.Uhrig, being first duly sworn, deposes and says: That he is a Vice President of Florida Power 6 Light Company, the Licensee herein;That he has executed the foregoing document;that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.Robert E.Uhrig Subscribed and sworn to before me this~~day of l9 PO 4 r NOTARY PUBL , in and for the county of Dade, State of Florida b!0i~PQbtic, Sh".~Q cf PiQ'i~t~ct Lozg0 My Coo.rr'"~ha Expires Ocia&r 30,'IS33 f$y commission exp3.res Bordcxl t!>re ll}} | | : 6. POWER DISTRIBUTION L IHITS |
| | : a. Hot channel factors: |
| | (1) With steam generator tube plugging >225 and <25K, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests: |
| | Fq (Z) < (2e03'/P)x K(Z) > for P > ~ 5 Fq (Z) < (4.06) x K(Z), for P < .5 F |
| | H |
| | < 1.55 [l.+0.2 (1-P) j Where P 'is the fraction of. rated power at which the core is operating; K(Z) is the function given in Figure 3.2-3b; Z is the core height location of Fq If F , as predicted by approved physics calculations, exceeds 2.03, the power will be limited to the rated power multiplied by the ration of 2.03 divided by the predicted F , or augmented surveil.lance of hot channel factors shall be implemented. |
| | (2) With steam generator tube plugging < 22K, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests: |
| | Fq (Z) <'2e 10/P )x K(Z) p for P > e5 F (Z) < (4.20)x K(Z), for P < .5 F |
| | H |
| | < 1.55 [1.+0.2 ('1-P)] |
| | Where P is the fraction of rated power at which the core is operating; K(Z) is the function given in either Figure 3.2-3 or 3.2-3a; Z is the core height location of Fq. |
| | 3 ~ 2 2-27-80 soosoao +Pg |
| | |
| | 0 0 l P |
| | J |
| | ~ g t |
| | |
| | TABLE 4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Descri tion Check Calibrate Test Remarks |
| | : 1. Nuclear Power Range S (1) D (2) M (3) 1) Load v.s. flux curve (Check, Calibrate and Test M*(4) Q*(4) 2) Thermal power calculation only applicable above 3) Signal to T; bistable 10$ of rated power.) action (permissive, rod stop; trips) |
| | : 4) Upper 8 lower detectors for symmetric offset (+5 to -5X) |
| | '. |
| | Nucl ear Intermediate Range S (1) ~ N.A. P (2) 1) Once/shift up to 50K, R.P. |
| | : 2) Log level; bistable action (permissive, rod stop, trip) |
| | : 3. Nuclear Source Range S (1) N.A. P (2) 1) Once/shift when in service |
| | : 2) Bistable action (alarm, trip) |
| | : 4. Reactor Cool ant Temperature S B/W (1) 1 1) Overtemperature- T (2) ~ 2) Overpower- T |
| | : 5. Reactor Coolant Flow |
| | : 6. Pressurizer Water Level |
| | : 7. Pressurizer Pressure M1 |
| | : 8. 4 kv Voltage 8 Frequency N.A. Reactor protection circuits only |
| | : 9. Analog Rod Position R(1) With step counters |
| | : 1) Calibrate indicated position to within 12 steps of actual position 2-27-80 |
| | |
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| | t |
| | |
| | STATE''OF FLORlDA ) |
| | ) ss COUNTY OF DADE ) |
| | Robert E. Uhrig, being first duly sworn, deposes and says: |
| | That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee. |
| | Robert E. Uhrig Subscribed and sworn to before me this |
| | ~~day of l9 PO 4 |
| | r NOTARY PUBL , in and for the county of Dade, State of Florida b!0i~ PQbtic, Sh".~Q cf PiQ'i~t~ ct Lozg0 My Coo.rr'"~ha Expires Ocia&r 30, 'IS33 f $y commission exp3.res Bordcxl t!>re |
| | |
| | ll}} |
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test ML17352B0041995-01-17017 January 1995 Proposed Tech Specs 6.9.1.7, COLR, Including Ref to Topical Rept NF-TR-95-01 Re Implementation of FPL Nuclear Physics Methodology for Calculations of COLR Parameters ML17352A8341994-10-20020 October 1994 Proposed TS 3/4.7.1.1 & Associated Bases,Addressing Max Allowable Reactor Thermal Power Operation W/Inoperable MSSVs ML17352A8281994-10-20020 October 1994 Proposed Tech Specs 4.8.1.1.2e & 4.8.1.1.2f,addressing EDG Fuel Oil Testing & TS 3.8.1.1,addressing Required Action in Event Diesel Fuel Oil Does Not Meet Diesel Fuel Oil Testing Program Limits ML17352A8311994-10-20020 October 1994 Proposed Tech Specs 3/4.4.9.1,reflecting Removal of Schedule for Withdrawal of Rv Matl Specimens ML17352A8381994-10-20020 October 1994 Proposed Tech Specs,Allowing Containment Personnel Airlock Doors to Be Opened During Core Alterations & Movement of Irradiated Fuel in Containment,Provided Certain Conditions Met ML17352A7321994-07-19019 July 1994 Proposed TS 3/4.7.1 & Associated Bases Addressing Operation at Reduced Power Levels W/Inoperable Main Steam Safety Valves ML17352A7291994-07-19019 July 1994 Proposed Tech Specs 4.8.1.1.2e & 4.8.2.2.2f Re EDG Fuel Oil Testing Program ML17352A7241994-07-19019 July 1994 Proposed Tech Specs Adding Rod Bank Insertion Limits & K(Z) Curves to COLR ML17352A5471994-04-19019 April 1994 Proposed TS 4.0.5a Re ISI & Testing Programs ML17352A5441994-04-19019 April 1994 Proposed Tech Specs Changing Containment Spray Sys Surveillance Requirements 1999-07-27
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17355A3921999-07-27027 July 1999 Proposed Tech Specs 3.8.1.1,3.4.3 & 3.5.2,extending AOT for Inoperable EDG from 72 Hours to 7 Days on one-time Basis ML17355A3581999-06-28028 June 1999 Cycle 18 Startup Rept. with 990628 Ltr ML17355A3041999-04-26026 April 1999 Proposed Tech Specs Deleting Obsolete Part of License Condition 3.L & Incorporating Administrative Changes to TS Index,Ts 3/4.1.2.5 & TS 3/4.7.6 ML17355A2491999-03-0808 March 1999 Proposed Tech Specs Section 6.0,deleting Certain Requirements That Are Adequately Controlled by Existing Regulations,Other than 10CFR50.36 & TS ML17355A2411999-02-24024 February 1999 Proposed Tech Specs Page 3/4 7-15,removing Restrictions on Location at Which Temp of UHS May Be Monitored ML17355A2011999-01-25025 January 1999 Cycle 17 Startup Rept. with 990125 Ltr ML17354B1641998-10-27027 October 1998 Proposed Tech Specs Pages Re Amends to Licenses DPR-31 & DPR-41,to Incorporate Specific Staff Qualifications for Multi-Discipline Supervisor Position Into TS ML20197C9661998-08-27027 August 1998 Rev 15 to Security Training & Qualification Plan ML17354A9471998-04-27027 April 1998 Rev 2 to Turkey Point Nuclear Plant Recovery Plan. ML17354A8381998-03-12012 March 1998 Proposed Tech Specs Deleting License Conditions 3.I,3.K,3.H & 4 & Incorporating Recent Organization Change in TS 6.5.1.2 & 6.5.3.1.a ML17354A7801998-02-0202 February 1998 Proposed Tech Specs Re Diesel Fuel Storage Sys ML17355A2711998-01-30030 January 1998 Rev 7 to ODCM for Gaseous & Liquid Effluents from Turkey Point Plant,Units 3 & 4. ML17354A7621998-01-0909 January 1998 Proposed Tech Specs Sections 5.3.1 & 6.9.1.7,,allowing Implementation of Zirlo Fuel Rod Cladding ML17354A7321997-12-0404 December 1997 Proposed Tech Specs Section 6.9.1.7, COLR, Clarifying References 4 & 6 by Adding Best Estimate LOCA to COLR & Documenting re-analysis Performed as Result of Revs to Large Break LOCA Methodology ML17354A6161997-08-27027 August 1997 Proposed Tech Specs Page 6.2,allowing Use of 12 Hour Shifts for Nominal 40 (36 to 48) Hour Week ML17354A4971997-05-0101 May 1997 Rev 1 to Turkey Point Nuclear Plant Recovery Plan. ML17354A4771997-04-24024 April 1997 Proposed Tech Specs Page 6-22 Re Large Break Loss of Coolant re-analysis ML17354A4221997-02-24024 February 1997 Proposed Tech Specs 6.9.1.7 Re COLR & Large Break Loss of Coolant Accident re-analysis ML17354A3741996-12-17017 December 1996 Proposed Tech Specs,Modifying TSs to Change SR for TS 4.4.10 Re Reactor Coolant Pump Flywheel Insp ML17354A3521996-11-22022 November 1996 Proposed Tech Specs 3/4.8 Re Electrical Power Sources & 3/4.8.1 Re AC Sources Operating Limiting Condition for Operation ML17354A2871996-10-0303 October 1996 Proposed Tech Specs Revising TS to Allow Deferral for One Cycle of Reactor Coolant Pump Flywheel Ultrasonic Exams Required by Reg Guide 1.14 ML17353A7991996-07-17017 July 1996 Proposed Tech Specs,Revising TSs to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Intervals Determined by performance-based Criteria ML17353A7111996-05-28028 May 1996 Proposed Tech Specs Section 6.0, Administrative Controls. ML18008A0451996-05-10010 May 1996 Proposed Tech Specs Re Various Administrative Improvements ML17353A6781996-05-0909 May 1996 Proposed Tech Specs Re SBLOCA re-analysis ML17353A6521996-04-23023 April 1996 Proposed Tech Specs Re Accumulator Water Level & Pressure Channnel,Per NRC GL 93-05 ML17353A6581996-04-19019 April 1996 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl & Incorporating Administrative Clarifications & Corrections ML17353A6171996-03-21021 March 1996 Proposed Tech Specs,Revising TS Such That Requirements for Radiological Effluent Controls Relocated to Offsite Dose Calculation Manual or Process Control Program ML17353A6091996-03-20020 March 1996 Proposed TS 3/4.5.1,reflecting Removal of SRs & Operability Requirements for ECCS SI Accumulators That Concern Water Level & Pressure Channels ML17353A6001996-03-0505 March 1996 Proposed TS Sections 4.4.3.3 & 4.5.2,reducing Frequency of Surveillances & Insps in Accordance W/Gl 93-05,Items 6.6 & 7.5 ML17353A5801996-02-29029 February 1996 Plant Procedures & Training Matl Provided for Preparation of Licensing Exams for Reactor Operator Group Xvi & Senior Reactor Operator Upgrade. ML17353A6191996-02-15015 February 1996 Offsite Dose Calculation Manual for Gaseous & Liquid Effluents from Turkey Point Plant Units 3 & 4. ML17353A7631996-02-0808 February 1996 Conduct of Operations. ML17353A5031995-12-18018 December 1995 Proposed Tech Specs,Increasing Allowed Rated Thermal Power from 2,200 Mwt to 2,300 Mwt ML17353A4541995-11-22022 November 1995 Proposed Tech Specs Re Administrative Controls & Reviews ML17353A4511995-11-22022 November 1995 Proposed Tech Specs Pages 3/4 8-2 & 3/4 8-3 Re Edgs,Per GLs 93-05 & 94-01 ML17353A3971995-10-0404 October 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas,Tables 4.3-1 & 4.3-2 SR for Rps/Nis/Esfas & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentations ML17353A3831995-09-28028 September 1995 Proposed Tech Specs,Implementing Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17353A3531995-09-11011 September 1995 Proposed Tech Specs Re Edgs,Change to Testing Requirements, Per GLs 93-05 & 94-01 ML17353A7641995-08-23023 August 1995 Emergency & Off-normal Operating Procedure Usage. ML17353A2831995-07-26026 July 1995 Proposed Tech Specs 4.1.3.1.2,4.6.5.1,4.4.6.2.2,4.10.1.2 & Table 4.3-3 to Reduce Frequency of Testing,Per GL 93-05 ML17353A2801995-07-26026 July 1995 Proposed Tech Specs,Modifying TS Tables 3.3-1 & 3.3-2 Action Statements for Rps/Nis/Esfas Instrumentation,Tables 4.3-1 & 4.3-2 SRs for Rps/Nis/Esfas Instrumentation & Bases 3/4.3.1 & 3/4.3.2 for Rps/Nis/Esfas Instrumentation ML17353A2761995-07-26026 July 1995 Proposed Tech Specs,Adding to Approved COLR Analysis Methodology Used for SBLOCA Analysis in Anticipation of Thermal Uprate to 2,300 Mwt for Both Units & Increasing Current Margin to Calculated PCT ML17353A2731995-07-26026 July 1995 Proposed Tech Specs,Revising TS to Achieve Consistency Throughout Document by Removing Outdated Matl,Incorporating Administrative Clarifications & Corrections & Correcting Typos ML17353A2701995-07-26026 July 1995 Proposed Tech Specs Re Rod Misalignment Requirement for Movable Control Assemblies ML17353A2671995-07-26026 July 1995 Proposed Tech Specs for Nuclear Instrumentation Sys Adjustments Based on Calorimetric Measurements at Reduced Power Levels ML17353A2401995-06-19019 June 1995 Proposed Tech Specs Re TS SR 4.8.1.1.2.g.7 ML17352B1841995-05-23023 May 1995 Proposed Tech Specs Re Use of Changed Setpoint Presentation Format for RPS & ESFAS Instrumentation ML20083R1291995-05-0505 May 1995 Proposed Tech Specs Re Implementation of Revised Thermal Design Procedure & SG Water Level low-low Setpoint ML17352B0881995-03-30030 March 1995 Proposed Tech Specs SR 4.8.1.1.2.g.7,allowing Separation of 5-minute hot-start Test from 24-h EDG Test Run,Deleting Associated Footnote & Adding New TS SR 4.8.1.1.2.g.14 & Associated Footnote for Performance of Subj 5-minute Test 1999-07-27
[Table view] |
Text
5. CONTROL ROD POSITION INDICATION If either the power range channel deviation alarm or the rod deviation monitor alarm are not operable rod positions shall be logged once per shift and after a load change greater than l(5 of rated power. If both alarms are inoperable for two hours or more, the nuclear overpower trip shall be reset to 935 of rated power.
- 6. POWER DISTRIBUTION L IHITS
- a. Hot channel factors:
(1) With steam generator tube plugging >225 and <25K, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests:
Fq (Z) < (2e03'/P)x K(Z) > for P > ~ 5 Fq (Z) < (4.06) x K(Z), for P < .5 F
H
< 1.55 [l.+0.2 (1-P) j Where P 'is the fraction of. rated power at which the core is operating; K(Z) is the function given in Figure 3.2-3b; Z is the core height location of Fq If F , as predicted by approved physics calculations, exceeds 2.03, the power will be limited to the rated power multiplied by the ration of 2.03 divided by the predicted F , or augmented surveil.lance of hot channel factors shall be implemented.
(2) With steam generator tube plugging < 22K, the hot channel factors (defined in the basis) must meet the following limits at all times except during low power physics tests:
Fq (Z) <'2e 10/P )x K(Z) p for P > e5 F (Z) < (4.20)x K(Z), for P < .5 F
H
< 1.55 [1.+0.2 ('1-P)]
Where P is the fraction of rated power at which the core is operating; K(Z) is the function given in either Figure 3.2-3 or 3.2-3a; Z is the core height location of Fq.
3 ~ 2 2-27-80 soosoao +Pg
0 0 l P
J
~ g t
TABLE 4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS Channel Descri tion Check Calibrate Test Remarks
- 1. Nuclear Power Range S (1) D (2) M (3) 1) Load v.s. flux curve (Check, Calibrate and Test M*(4) Q*(4) 2) Thermal power calculation only applicable above 3) Signal to T; bistable 10$ of rated power.) action (permissive, rod stop; trips)
- 4) Upper 8 lower detectors for symmetric offset (+5 to -5X)
'.
Nucl ear Intermediate Range S (1) ~ N.A. P (2) 1) Once/shift up to 50K, R.P.
- 2) Log level; bistable action (permissive, rod stop, trip)
- 3. Nuclear Source Range S (1) N.A. P (2) 1) Once/shift when in service
- 2) Bistable action (alarm, trip)
- 4. Reactor Cool ant Temperature S B/W (1) 1 1) Overtemperature- T (2) ~ 2) Overpower- T
- 5. Reactor Coolant Flow
- 6. Pressurizer Water Level
- 7. Pressurizer Pressure M1
- 8. 4 kv Voltage 8 Frequency N.A. Reactor protection circuits only
- 9. Analog Rod Position R(1) With step counters
- 1) Calibrate indicated position to within 12 steps of actual position 2-27-80
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STATEOF FLORlDA )
) ss COUNTY OF DADE )
Robert E. Uhrig, being first duly sworn, deposes and says:
That he is a Vice President of Florida Power 6 Light Company, the Licensee herein; That he has executed the foregoing document; that the state-ments made in this said document are true and correct to the best of his knowledge, information, and belief, and that he is authorized to execute the document on behalf of said Licensee.
Robert E. Uhrig Subscribed and sworn to before me this
~~day of l9 PO 4
r NOTARY PUBL , in and for the county of Dade, State of Florida b!0i~ PQbtic, Sh".~Q cf PiQ'i~t~ ct Lozg0 My Coo.rr'"~ha Expires Ocia&r 30, 'IS33 f $y commission exp3.res Bordcxl t!>re
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