Proposed Change to Tech Spec Tables 3.3-3 Through 3.3-5, Paragraph 4.8.1.1.2 Re Degraded Electrical Power Grid Conditions.Safety Evaluation EnclML19253B588 |
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Site: |
Farley |
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Issue date: |
10/10/1979 |
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From: |
ALABAMA POWER CO. |
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To: |
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Shared Package |
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ML19253B584 |
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References |
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NUDOCS 7910160446 |
Download: ML19253B588 (11) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power ML20134J4051997-02-0606 February 1997 Proposed Tech Specs,Providing Addl Info Re voltage-based Repair Criteria for SG Tubing ML20133G5801997-01-10010 January 1997 Proposed Tech Specs Re Generic Laser Weld Sleeving & Deleting One Cycle Implementation of L* Which Expired at Last Unit 2 Outage ML20138G9581996-12-26026 December 1996 Proposed Tech Specs Reflecting Guidance Contained in GL 95-05, SG Tube Support Plate Voltage-Based Repair Criteria, Using Revised Accident Leakage Limit of 20 Gpm & Using Probability of Detection That Is Voltage Dependent ML20134N9211996-11-18018 November 1996 Proposed Tech Specs Bases B 3/4 2-5 Re RCS Total Flow Rate Surveillance ML20134K5551996-11-15015 November 1996 Proposed Tech Specs 3.6.2.2 Re Spray Additive Sys ML20134G9601996-11-11011 November 1996 Proposed Tech Specs Amending License NPF-8 to Replace Farley Specific Laser Welded Sleeve Requirements Currently in TS W/Generic Laser Welded Sleeve Process ML20149L8991996-11-0606 November 1996 Revised Technical Specification Pages for Plant Units 1 & 2 ML20128M4821996-10-0808 October 1996 Proposed Tech Specs Reflecting Deletion of Cycle Specific L* Repair Criteria Which Expires at Start of Next Unit 2 Refueling Outage ML20128F8821996-09-30030 September 1996 Proposed Tech Specs Change Request Relocating cycle-specific Core Operating Parameter Limits to Colr.Proposed Changes Based on Guidance Found in NRC GL 88-16,WOG-90-016, NUREG-1431 & COLR Approved by NRC 1999-06-30
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217B1791999-10-0404 October 1999 Revised TS Re Control Room,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation, Reflecting Agreements Reached in 990909 & 16 Discussions ML20209B8161999-06-30030 June 1999 Proposed Tech Specs Chapters 3.4,3.5,3.6,3.7,4.0 & 5.0, Converting to ITS ML20196J8731999-06-30030 June 1999 Proposed Tech Specs Correcting Errors,Per 990222 TS Amend Re Control Room,Penetration Room & Containment Purge Filtration Systems & Radiation Monitoring Instrumentation ML20207D6421999-05-31031 May 1999 Proposed Conversion to ITSs for Chapter 3.3 ML20206H0001999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI on Conversion to ITS ML20206F4421999-04-30030 April 1999 Proposed Revs to Previously Submitted Tech Specs with LAR Related to RAI Re Conversion to Its,Chapter 3.8 ML20206B4721999-04-21021 April 1999 Corrected Proposed TS Pages 5.5-6,5.5-7,5.5-8 & 5.5-9, Replacing Current W Model 51 SGs with W Model 54F L-99-170, Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with1999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205S9641999-04-20020 April 1999 Snoc Jfnp Startup Test Rept Unit 1 Cycle 16. with ML20205G8571999-04-0202 April 1999 Proposed Ts,Increasing Dei Limit from 0.15 to Uci/Gram IAW 10CFR50.90 ML20205A2401999-03-19019 March 1999 Proposed Tech Specs Table 3.3-6,re Cr,Penetration Room & Containment Purge Filtration Sys & Radiation Monitoring Instrumentation ML20205A3101999-02-28028 February 1999 Analysis of Capsule Z from Alabama Power Co Jm Farley Unit 2 Reactor Vessel Radiation Surveillance Program ML20207C2451999-02-22022 February 1999 Proposed TS Amends to Clarify SR Refs to ANSI N510 Sections 10,12 & 13 to ASME N510-1989,with Errata Dtd Jan 1991 & to Add Footnote Which Refs FNP FSAR for Relevant Testing of Details ML20203A7711999-02-0303 February 1999 Proposed Tech Specs Pages Re Conversion to Its,Chapter 3.4 ML20205T0011998-12-23023 December 1998 Rev 17 to FNP-0-M-011, Odcm ML20205T0081998-12-23023 December 1998 Rev 18 to FNP-0-M-011, Odcm ML20196B6241998-11-20020 November 1998 Proposed Tech Specs Pages Re Conversion to Improved TS, Chapters 3.6.& 5.0 ML20155J4561998-11-0606 November 1998 Proposed Tech Specs Re Nuclear Instrumentation Sys Power Range Daily Surveillance Requirement ML20154K2521998-10-12012 October 1998 Proposed Tech Specs Section 6,providing Recognition of Addl Mgt Positions Associated with SG Replacement Project & Providing Ability to Approve Procedures Re Project Which May Affect Nuclear Safety ML20151V6991998-09-11011 September 1998 Snoc Jm Farley Nuclear Plant Startup Test Rept Unit 2 Cycle 13. with ML20237D4111998-08-20020 August 1998 Proposed Tech Specs Reflecting Conversion to Improved TS Re Discussion of Changes & Significant Hazards Evaluations ML20217N4801998-05-0101 May 1998 Proposed Tech Specs Bases Pages Re Safety Limits,Reactivity Control Systems & Afs ML20205S9971998-04-19019 April 1998 Rev 16 to FNP-0-M-011, Odcm ML20217Q7261998-03-20020 March 1998 Proposed Tech Specs Re Power Update Implementation,Replacing Page 6-19a ML20202G1311998-02-12012 February 1998 Proposed Tech Specs Re Pressure Temp Limits Rept ML20202F1121998-02-12012 February 1998 Revised Proposed Changes to TS Page 6-19a for Power Uprate ML20198H3661998-01-0707 January 1998 Proposed Tech Specs Pages,Adding Note to Specifically Indicate Normal or Emergency Power Supply May Be Inoperable in Modes 5 or 6 Provided That Requirements of TS 3.8.1.2 Are Satisfied ML20198E6621997-12-31031 December 1997 Proposed Tech Specs Changing Nis IR Neutron Flux Reactor Trip Setpoint & Allowable Value ML20198E3141997-12-30030 December 1997 Proposed Tech Specs Re Auxiliary Bldg & Svc Water Bldg Battery Surveillances ML20197B6691997-12-18018 December 1997 Proposed Tech Specs Pages Re 970723 TS Amend Request Associated W/Pressure Temperature Limits Rept ML20212B1791997-10-31031 October 1997 1 SG ARC Analyses in Support of Full Cycle Operation ML20211P5861997-10-16016 October 1997 Proposed Tech Specs Pages,Revising Number of Allowable Charging Pumps Capable of Injecting in RCS When Temperature of One or More of RCS Cold Leg Temperatures Is Less than 180 F ML20211J1501997-09-30030 September 1997 Proposed Tech Specs,Correcting Page 20 of 970723 TS Amend Request to Relocate RCS Pressure & Temperature Limits from TS to Pressure & Temperature Limit Rept ML20217C0341997-09-25025 September 1997 Revised Proposed Ts,Providing Addl Info Re 970630 Submittal, Titled, Jfnp TS Change Request - Credit for B for Spent Fuel Storage ML20211A6891997-09-17017 September 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20216D0031997-09-0303 September 1997 Proposed Tech Specs Re Moveable Incore Detector Sys ML20149K1001997-07-23023 July 1997 Proposed Tech Specs,Relocating RCS P/T Limits from TS to Proposed P/T Limits Rept IAW Guidance Provided by GL 96-03, Relocation of P/T Limit Curves & LTOP Sys Limits ML20148Q1041997-06-30030 June 1997 Proposed Tech Specs,Revising & Clarifying Requirements for CR Emergency & Penetration Room Filtration Sys,Required Number of Radiation Monitoring Instrumentation Channels & Deleting Containment Purge Exhaust Filter Spec ML20148R7521997-06-30030 June 1997 Proposed Tech Specs,Incorporating Requirements Necessary to Change Basis for Prevention of Criticality in Fuel Storage Pool.Change Eliminates Credit for Boraflex as Neutron Absorbing Matl in Fuel Storage Pool Criticality Analysis ML20148K7501997-06-13013 June 1997 Proposed Tech Specs Changing TS 3/4.9.13, Storage Pool Ventilation (Fuel Movement) ML20140A3931997-05-28028 May 1997 Proposed Tech Specs,Clarifying That Testing of Each Shared EDG to Comply W/Sr 4.8.1.1.2.e Is Only Required Once Per Five Years on a Per EDG Basis,Not on Per Unit Basis ML20148F2381997-05-27027 May 1997 Corrected TS Bases Page B 3/4 1-3 That Incorporates Changes from COLR & Elimination of Containment Spary Additive Sys TS Amends ML20148E5921997-05-27027 May 1997 Proposed Tech Specs Pages Revising Applicable Modes for Source Range Nuclear Instrumentation & Providing Allowances for an Exception to Requirements for State of Power Supplies for RHR Discharge to Charging Pump Suction Valves ML20138B9251997-04-23023 April 1997 Proposed Tech Specs,Revising TS Pages to Include Footnote Concerning Filter Pressure Drop Testing & Mechanical Heater Testing ML20198T4921997-03-31031 March 1997 Small Bobbin Probe (0.640) Qualification Test Rept ML20137H6091997-03-25025 March 1997 Proposed Tech Specs Re Primary Coolant Specific Activity ML20136F8231997-03-0707 March 1997 Proposed Tech Specs 3/4.6.3 Re Containment Isolation Valves Surveillance Requirements ML20135C4941997-02-24024 February 1997 Proposed Tech Specs Re SG Tube Laser Welded Sleeves.Voltage Based Alternate Repair Criteria Is Approved Prior to Laser Welded Sleeve Amend ML20135C6731997-02-24024 February 1997 Proposed Tech Specs Re Surveillance Requirements of Control Room,Penetration Room & Containment Purge Filtration Systems ML20135C8641997-02-14014 February 1997 Proposed Tech Specs Revising Specified Max Power Level & Definition of Rated Thermal Power 1999-06-30
[Table view] |
Text
.
6 E TABLE 3.J-3 (Continued)
(j [HG!re:CRED SAFETY FEATilRE ACTUATION SYSTEH INSTRUHENTATION 5 HINIHUN El TOTAL NO. CllANNELS CilANNELS APPLICABLE '
FUNCTIONAL UNIT _ 0F CilANNEl.S TO TRIP OPERADLE H0 DES ACTION
- b. Undervoltage-RCP Start Turbine-Driven Pump 3-2/ bus 2 2 1 14
- c. S.I. '
Start Motor Driven Pumps
~
See 1 above (all S.,I. initiating functions and requirements)
M u
e, 7. LOSS OF POWER n2 '
')
- a. 4.16 KV Emergency Dus 3/ bus 2/ bus 2/ bus 1, ?, 3 19*,7###
Undervoltage(Loss of Voltage)
- b. 4.16 KV Ener0ency Bus 3/ bus 2/ bus 2/ bus 1. 2, 3 19*,illi Undervoltage (De-graded Voltage)
~1 CD w
O
-a __.
C2 kJ' t
- -) JRs
~b rs; p esa N
T b g
TABLE 3.3-3 (Continued) g TABLE NOTATION D i
Trip function may be bypassed in this MODE below P-11. .
El Trip function may be bypassed in this MODE below P-12.
The channel (s) associated with the protective functions derived frcm the out of service Reactor Coolant. Loop shall be placed in the tripped mode. -
- Trip function may be bypassed for up to two hours for surveillance testing.
s s -
The provisions of Specification 3.0.4 are not applicable.
ACTION STATEMENTS _
ACTION 13 - With the number of OPERABLE Channels one less than the Total Numbarr of Channels, be in HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ACTION 14 - With the number of OPERABLE Channels one less than the Total Numbetr of Channels, operation may prcceed until perfor :ance of the next required CHANNEL i"Ut!CTIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hoisr.
ACTION 15 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in HOT SHUTDOWN within the following 12 h.;'rs; however, one channel associated with an operating loco may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ACTION 16 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provideo the .
inoperable channel is placed in the bypassed condition and the minimum Channels OPERABLE requirements is demonstrated within I hour; one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.2.1.1.
ARLEY - UNIT l 3/4 3-21 lI54 238
h 9 &
TABLE 3.3-3 (Continued} {0)b ACTION 17 - With less than the Minimum Channels OPE:.ABLE, coeration may continue provided the containment purge and exhaust valves are maintained closed.
ACTION 18 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least HOT STAMOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. _
ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the tripped condition within one hour. j ENGINEERED SAFETY FEATURES INTERLOCKS DESIGNATICN CON'ITION AND SETPOINT FUNCTION P-11 With 2 of 3 pressurizer P-ll pre. vents anual block pressure channels > 2010 of safety injection actuation ps19 on low pressuri:er pressure coincident with low pressurizer water level P-12 With 2 of 3 Tavg channels Permits manual block of S.I;
< 541*F. Causes steam line isolation on high steam flow; Affects steam dLeo blocks.
Prevents manual block of With 2 of 3 T"V9 channels
> 545'F safety injection actuation on low steam line cressure.
Il54 239 FARLEY - UNIT 1 3/4 3-22
TABLE 3.3-4 (Continued)
"1 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS a
FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE VALUES h 6. Auxiliary Feedwater H
H a. Steam Generator 2 15% of narrow range h 14% of narrow range instru-Water Level-Low-Low instrument span-each steam ment span-each steam ge.nerator generator
- b. Undervoltage - RCP h 2680 RCP bus voltage 2:2640 RCP bus voltage
- c. S.I. see 1 above (all SI Setpoints)
R 7. Loss of Power s~
y a. 4.16 KV Emergency Bus Under- h3255 volts bus voltage
- g voltage (Loss of Voltage)
- b. 4.16 KV Emergency Bus Under- 33675 volts bus voltagt
- voltage (Degraded Voltage)
- The time delay shall be within 5% of that specified in the manufacturer's published undervoltage relay time curves.
w P
-.=.
N h
CD
D}{D QD f TABLE 3.3-5 (Centinued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES _
INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECON05 '
- 7. Containment Pressure--Hich-Hich __ _
- a. Steam Line Isolation 1 7.0
~ '
- 8. Containment Pressure--Hich-Hich'-Hich , ,
- a. Containment Spray 1 45.0
- b. Containment Isolation-Phase "B" Not Applicable
- 9. Steam Generator Water Level--Hich-Hich Turbine Trip-Reactor Trip
- a. 152 ###
. b. Feedwater Isolation 1 32.0
- 10. Steam Generator Water Level--Low-Lew
- a. Motor-driven Auxiliary Fee 6<ater Pumps ** 60.0
- b. Turbine-driven Auxiliary Feedwater Pumps *** 60.0
- 11. Undervoltace RCP
- a. Turbine-driven Auxiliary 50.0
- 12. S.I. Sicnal __
- a. Motor-driven Auxiliary Feedwater Pump 50.0 Insert 1................. .
D -
INSERT 1
- 13. Loss of Power
- a. 4.16 KV Emergency Bus 1.2 ****
Undervoltage (Loss of Voltage)
- o. 4.16 KV Emergency Bus *****
Undervoltage (Degraded Voltage)
- The response time limit from voltage decreasing below 68% of nominal voltage to generation of the Diesel start signal.
- The response time shall include the time delay associated with the undervoltage relays as determined in Table 3.3-4 plus an additional second associated with interposing relay and circuit breaker operation.
1154 242
TABLE 4.3-2(Continued [
5 f.! ENGINEERED SAFETY FEATURE ACTUATI0ll SYSTEH INSTRUMENTATION Q SUIEVTitTAhCE RET)UIREHENTS i
c- CilANNEL H0 DES IN WillCll 5 CilAHilEL CilANNEL FUNCTIONAL SURVEILLANCE FUNCT10tlAL UNIT CilECK CAllBRATION , TEST
] REQUIRED
- 4. STEAM LillE ISOLATION
- a. Hanual N.A. H.A. 11 ( 1 ) 1, 2, 3, 4
- b. Automatic Actuation Logic H.A. , H.A. H(2) 1, 2, 3, 4
- c. Containment Pressure-- S R H 1, 2, 3 liigh-liigh u d. Steam Flow in Two Steam S R H 1, 2, 3 h Lines--liigh Coincident with T,yg-- Low-Low c@
- e. Steam Line Pressure-Low S R H 1, 2, 3
- 5. TURBillE TRIP All0 FEEDWATER ISOLATI0li
- a. Steam Generator llater S R H 1, 2, 3 Level--liigh-lii0h
- 6. Auxiliary feedwater Ln
- a. Steam Generator Water S R H ,
1, 2, 3 g
g n
Level-Low-Low f u b. Undervoltage - RCP S R H 1
- c. S . I .' See 1 above (all SI surveillance requirements)
Insert 2...........
INSERT 2
- 7. Loss of Power
- a. 4.16 KV Energency Bus N/A R (3) H (4) 1, 2, 3 Undervoltage (Toss of Voltage)
- b. 4.16 KV Emergency Bus N/A R (3) H (4) 1, 2, 3 Undervoltage (Degraded Voltage) m h
{%'
b A
T_ABLE 4.3-2 (Continued)
TABLE NOTATION (1) Manual actuation switches shall be tested at least once per 18 months during shutdown. Each train or logic channel at all other circuitry associated with manual safeguards actuation shall receive a CHANNEL FUNCTIONAL TEST at least once every other 31 days.
(2) Each train or logic channel shall be tested at least every other 31 days.
(3) Channel calibration shall exclude actuation of the final trip actuation relay.
(4) Functional testing shall consist of verification of relay operation upon removal of input voltage and operation of 2-out-of-3 logic excluding the final trip actuation relay.
FARLEY - UNIT 1 3/4 3-34 1154 245
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
- 3. Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank,
- 4. Verifying the diesel starts from ambient condition, and accelerates to at least 900 rpm for the 2850 Kw generator and 514 rpm for the 4075 Kw generator < in 10 seconds,
- 5. Verifying the generator is synchronized, loaded to > 2050 kw for the 4075 kw generator and > 1475 kw for the 2850
'kw generator and operates for > 60 minutes, and
- 6. Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.
. 7. Verifying that the automatic load sequence timer is -
OPERABLE with each load sequence time within + 10", of its re' quired value or 0.5 seconds which ever is gr_ eater.
. b. At least once per 92 days by verifying that a sample of diesel
\. fuel from the fuel storage tank obtained in accordance with ASTM-D270-65 is within the acceptable limits specified in Table 1 of ASTM D975-74 when checked for viscosity, water and sedimen.t, E c. At least once per 18 months dur;ng shutdown by:
f 1.
~
Subjecting the diesel to an inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of stardby service,
- 2. Verifying the generator capability to reject, without tripping, a load of > 672 kw for the 4075 kw generator and 448 kw for the 2E50 kw generator.
- 3. Simulating a loss of offsite power in conjunction.with a
, safety injection test signal, and:
f (8) Verifying the di_sel starts from ambient condition
. - on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto-connected emergency loads through the load sequencer and operates for > 5 minutes while its generator is loaded with the eme,rgency loads.
FARLEY-UNIT 1 3/4 8-3 1154 246
~.
ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)
(b) Verifying that all diesel generator trips, except engine overspeed, lubrication oil pressure low and generator differential, are automatically bypasscd upon loss of voltage on the emergency bus and/or safety injection test signal.
- 4. Verifying the diesel generator operates for 2: 60 minutes while loaded to2:4075 kw for the 4075 kw diesel generator andt 2850 for the 2850 kw diesel generator.
- 5. Verifying that the auto-connected loads to each diesel generator do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 4353 kw and 3100 kw for the 4075 generator and the 2850 generator, respectively.
- 6. Siaulating a loss of offsite power by itself, and:
(a) Verifying de-energization of the emergency buses and load shedding from the emergency buses.
(b) Verifying the diesel starts from ambient condition on the autostart signal, energizes the emergency buses with permanently connected loads, and the sequencer closes the supply breakers for the auto-connected emergency loads.
- 7. Verifying that on a safety injection test signal (with-out loss of offsite power) the diesel generator starts on the auto-start signal and operates on standby for as 5 minutes.
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