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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled ML20098A4861995-09-22022 September 1995 Proposed Tech Specs,Converting Existing VEGP TS Requirements to Format & Content of NUREG-1431 ML20086G5691995-07-0606 July 1995 Proposed Tech Specs Section 3.8.3.1,Page 3/4 8-15 Re Footnote & Bases & Expansion ML20085G7171995-06-14014 June 1995 Proposed Tech Specs,Clarifying in Revised Bases of 3/4 Chapter 8,that Alignment of Standby Auxiliary Transformer Intended to Be Temporary Alignment & Will Be Utilized When Normal Preferred Offsite Power Source,Rat Unavailable ML20083M0731995-05-12012 May 1995 Proposed Tech Specs Revising SR 4.1.6.2 to Support Exemption from 10CFR50,App J Type a Test Schedule ML20083A1391995-05-0202 May 1995 Proposed Tech Specs,Adding Automatic Load Sequencer to Plant TS ML20082D9881995-04-0404 April 1995 Proposed Tech Spec Page 6-7 Reflecting Corrected Terminology Re Composition of Plant Review Board ML20081J5031995-03-17017 March 1995 Proposed TS 3.9.4 Re Containment Airlock Doors to Be Open During Fuel Movement ML20081D1591995-03-17017 March 1995 Proposed TS Table 3.3-8, Accident Monitoring Instrumentation, Deleting Loop Numbers 551,552,553 & 554 ML20082E7731995-03-0404 March 1995 Proposed Tech Specs Re Plant Review Board Composition ML20080N2451995-02-28028 February 1995 Proposed Tech Specs Pages Re Accident Montoring Instrumentation 1999-09-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G6571999-10-13013 October 1999 Proposed Tech Specs Pages,Revising TS to Permit Relaxation of Allowed Bypass Test Times & Completion Times for LCOs 3.3.1 & 3.3.2 ML20217B1221999-10-0404 October 1999 Proposed Tech Specs Pages,Revising TS 5.5.6 Incorporating Exceptions to Reg Guide 1.35,rev 2,as Described in FSAR Section 3.8.1.7.2 Re Prestressed Concrete Containment Tendon Surveillance Program ML20212F4891999-09-22022 September 1999 Proposed Rev to TS SR 3.8.1.13,to Include Upper Limit for DG Loading for 2 H Portion of SR ML20211J5511999-08-30030 August 1999 Proposed Tech Specs,Raising Level of Approval Authority for Deviations from Guidelines Provided to Minimize Unit Staff Overtime Specified in TS 5.2.2 ML20211J7281999-08-26026 August 1999 Proposed Tech Specs Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be in IAW with Versions of LCO 3.0.4 & SR 3.0.4 as Noted in Rev 1 to NUREG-1431 ML20211E9111999-08-24024 August 1999 Proposed Tech Specs,Relaxing Slave Relay Test Frequency from Quarterly to Refueling Frequency ML20196L3181999-05-18018 May 1999 Proposed Tech Specs SRs 3.8.1.3 & 3.8.1.13 Reducing Loading Requirements for DGs ML20205S3791999-04-19019 April 1999 Proposed Tech Specs Revising SR 3.3.5.2 & Associated Bases to Allow Loss of Voltage & Degraded Voltage Trip Setpoints to Be Treated as Nominal Values in Same Manner as Trip Setpoints for RTS & ESFAS Instrumentation ML20205Q7901999-04-13013 April 1999 Proposed Tech Specs,Updating Versions of LCO 3.0.4 & SR 3.0.4 to Be Consistent with Versions of LCO 3.0.4 & SR 3.0.4 as Appear in Rev 1 to NUREG-1431 ML20154M9961998-10-15015 October 1998 Proposed Tech Specs,Deleting & Modifing Conditions Which Were Issued with Licenses That Are Now Obsolete ML20151U2011998-09-0303 September 1998 Proposed Tech Specs Pages for Amends to Licenses NPF-68 & NPF-81,changing TS to Support Replacement of Nuclear Instrumentation Sys Source Range & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236R4661998-07-13013 July 1998 Proposed Tech Specs Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Selected Protected Channels ML20154Q8611998-06-30030 June 1998 Proposed Tech Specs Bases Since Implementation of Improved TS on 970123 Through Aug 1998 ML20206N3131998-06-30030 June 1998 Proposed Tech Specs Re Replacement of Nuclear Instrumentation Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys ML20236F1631998-06-26026 June 1998 Proposed Tech Specs Revising LCO 3.3.6 Re CVI Instrumentation & LCO 3.9.4 Re Containment Penetrations to Facilitate Outage Planning ML20248K5801998-05-25025 May 1998 Rev 1 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20247K5041998-05-15015 May 1998 Proposed Tech Specs Pages Revising New Program 5.5.18 to Extent That Items B,C & D. Refer to LCO Action Statement & Bases Insert for New Required Actions B.5.1 & B.5.2 ML20247G9471998-05-0808 May 1998 Proposed Tech Specs Section 5.5.7, RCP Flywheel Insp Program, Specifying Alternate Flywheel Insp Once Every Ten Years ML20216J4971998-04-16016 April 1998 Proposed Tech Specs 3.3.1 & 3.3.2 Re Reactor Trip Sys & ESFAS Instrumentation ML20199E5351998-01-27027 January 1998 Complete Replacement of All Typed Pages of TS Changes Submitted in Ltr LCV-0849-E ML20199A4131998-01-22022 January 1998 Proposed Tech Specs Adding Conditions for DG for Extended DG Completion Time of Fourteen Days ML20198P6961998-01-16016 January 1998 Revised Spent Fuel Pool Boron Dilution Analysis ML20216B2621997-12-11011 December 1997 Rev 14 to ODCM, for Vogtle Electric Generating Plant ML20199G3901997-11-20020 November 1997 Proposed Tech Specs Facilitating Treatment of Trip Setpoints as Nominal Values & Correct Certain Typos ML20199J6651997-11-20020 November 1997 Proposed Tech Specs Pages Changing Capacity of Unit 1 Spent Fuel Storage Pool from 288 to 1476 Assemblies & Revising Design Features Description to Reflect Criticality Analyses & Storage Cell Spacing ML20211N2451997-10-10010 October 1997 Proposed Typed Tech Specs Pages,Revising Credit for Boron & Enrichment Increase for Fuel Storage ML20217H9051997-08-0808 August 1997 Proposed Tech Specs Pages Re Credit for Boron & Enrichment Increase for Fuel storage.W/marked-up Pages ML20141A8541997-06-13013 June 1997 Proposed Tech Specs Revising LCO 3.4.10 to Reduce Nominal Set Pressure by 1% to 2460 & Increase Tolerance to +2% ML20148E6481997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Pump IST Program ML20148E6611997-05-15015 May 1997 Rev 0 to VEGP Units 1 & 2 Second 10-Yr Interval Valve IST Program ML20133L3081997-01-10010 January 1997 Proposed Tech Specs Table 3.3.1-1 Re Amends 96 & 74 ML20140J4591996-12-13013 December 1996 Rev 11 to ODCM for Vogtle Electric Generating Plant, ML20138F1001996-12-13013 December 1996 Revs 10 & 11 to ODCM, Part 2 ML20132C4711996-12-12012 December 1996 Proposed Tech Specs Re Physical Security & Contingency Plan ML20134J9841996-10-0808 October 1996 /Unit 2 Fuel Assembly Insp Program ML20117N5851996-09-13013 September 1996 Proposed Tech Specs 3.8.1 Re AC Electrical Sources ML20129A6461996-09-11011 September 1996 Proposed Tech Specs,Providing Updated Documentation for License Amends Application for Southern Nuclear to Become Licensed Operator ML20117C4151996-08-23023 August 1996 Proposed Tech Specs to Convert Units 1 & 2 Based on NUREG 1431 ML20117N6361996-06-17017 June 1996 Proposed Tech Specs,Clarifying Requirements of TS SR 4.8.1.1.2.j (2) That Prescribes Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code ML20117N6471996-06-17017 June 1996 Proposed Tech Specs Section 5.3.1,allowing Use of Fuel Assemblies Containing Fuel Rods Clad W/Zirlo ML20111A5501996-05-0606 May 1996 Proposed Tech Specs,Incorporating Extended DG AOT to 14 Days from Discovery of Failure to Meet Lco,Provided Standby Auxiliary Transformer Available ML20106H2391996-03-31031 March 1996 Rev 10 to Gap Security Dept Vogtle Electric Generating Plant Nuclear Security Training & Qualification Plan ML20101D4151996-03-0505 March 1996 Proposed Tech Specs Re Conversion Based on NUREG-1431 ML20100G0371996-02-19019 February 1996 Proposed Tech Specs Based on NUREG-1431 ML20097A3171996-01-30030 January 1996 Proposed Improved TS Based on NUREG-1431 ML20096G8241996-01-22022 January 1996 Inservice Insp Program, for VEGP-2 ML20095J2501995-12-22022 December 1995 Proposed Tech Specs,Allowing Use of Option B of 10CFR50,App J for Type B & C Testing ML20094N4071995-11-20020 November 1995 Proposed Tech Specs,Converting Existing TS to Format & Content of NUREG-1431 ML20093K2281995-10-16016 October 1995 Proposed Tech Specs,Adding Footnote to Spec 4.6.1.2.d Stating That Type B & C Tests Scheduled for Refueling Outage 1R6 Will Be Conducted Per Option B of 10CFR50 App J & Using Guidance of RG 1.163,Rev 0 ML20098C1471995-10-0202 October 1995 Proposed Tech Specs,Allowing Next Type a Test to Be Rescheduled 1999-09-22
[Table view] |
Text
_ _ , , - - . , . . - - . . . .
k*
,3. .. g ENCLOSURE 3 V0GTLE ELECTRIC GENERATING PLANT TECHNICAL-SPECIFICATION CHANGE STEAM GENERATOR LEVEL INSTRUMENTATION INSTRUCTIONS FOR INCORPORATION
, The proposed amendment to the Technical Specifications would be incorporated as follows:
Remove Paae Insert Paae 2-5 and 2-6* 2-5 and 2-6 3/4 3-31 and 3/4 3-32* 3/4 3-31 and 3/4 3-23 E3-1
- Overleaf page containing no change 9006040184 DR 900529 ADOCK 05000424 PDC
.- o ,
.x V
TABLE 2.2-1 (Continued) ..s g REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS y
m SENSOR TOTAL g ALLOWANCE ERROR ALLOWABLE VALUE 3 Z (5) TRIP SETPOINT FUNCTIONAL UNIT (TA) 1.67 >1960 psig** >1950 psig 3.1 0.71
- 9. Pressurizer Pressure-low -
e (PI-0455A,B&C, PI-0456 &
ro PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-0458A) <2395 psig 3.1 0.71 1.67 <2385 psig
- 10. Pressurizer Pressure-High (PI-0455A,B&C, PI-0456 &
PI-0456A, PI-0457 & PI-0457A,~
PI-0458 & PI-0458A) <93.9% of instrument 8.0 2.18 1.67 <92% of instrument
- 11. Pressurizer Water Level-High span span (LI-0459A, LI-0460A, LI-0461) >89.4% of loop 1.87 0.60 >90% of loop Reactor Coolant Flow-Low 2.5 design flow
- LOOP 2 LOOP 3 LOOP 4 m (LOOP 1 FI-0414 FI-0424 FI-0434 FI-0444 FI-0415 FI-0425 FI-0435 FI-0445 (.77,6),,, (JL 7) a,#
FI-0416 FI-0426 FI-0436 FI-0446) ~
>17.8% of narrow 18.5 17.18 "1.67 >18.5%$fnarrow
- 13. Steam Generator Water Level range instrument range instrument Low-Low (21.8) (16.p/) span span
$ LOOP 3 LOOP 4 (LOOP 1 LOOP 2 J LI-0517 LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549 LI-0551 LI-0552 LI-0553 LI-0554) >9481 volts 6.0 0.58 0 >9600 volts
- 14. Undervoltage - Reactor {70% bus voltage) T69% bus voltage)
Coolant Pumps 0 >57.3 Hz >57.1 Hz Underfrequency - Reactor 3.3 0.50 15.
Coolant Pumps
- Loop Timedesign flow = 95,700_gpm constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 10 seconds for lead and 1 second for lag.
CHANNEL CALIBRATION shall ensure that these time constants are adjusted to these values.
si
- w *TAe vala r enled insi/e the parea/An,s is for l,s/maed do*n 1/af Jag: fle lower fay aaff,,,f,,, af, ,f;,,4,gf',
,33 ,
n e vals r stated outs,le d e ,,,,,ge,,, ,, ;;,, ,,,taa,,,,at,&,, thf 4,y de kwer. .fg .c I
1
! +- p y. .~ * ; o . -- .. _
m
, y iJ TA8LE 3.3-3 (Continued) --
o ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS h SENSOR TOTAL
[ ALLOWANCE ERROR z, TRIP SETPOINT ALLOWABLE VALUE-(TA) Z (S) g FUNCTIONAL UNIT
- 5. Turbine Trip and Feedwater Isolation (4 C)4 (ry, y)"
~
(Continued) #
5.1 .. 2.18 1.67 <78.0% of <79.9%^of narrow
[ c. Steam Generator Water Instrument range instrument Level--High-High (P-14) 04.07 (y,gfy* span. span.
LOOP 2 LOOP 3 LOOP 4 (LOOP 1 LI-0517 LI-0527- LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549 LI-0551 LI-0552 LI-0553 LI-0554)
Safety Injection See Functional Unit 1. above for all Safety Injection Trip d.
y Setpoints and Allowable Values.
2 y 6. Auxiliary Feedwater N.A. N.A. N.A. N.A.
- a. Automatic Actuation Logic N.A.
.and Actuation Relays
- b. Steam Generator Water Level--
Low-Low LOOP 2 LOOP 3 -LOOP 4 (LOOP 1 LI-0517 LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 .-
LI-0519 LI-0529 LI-0539 LI-0549 (JF, 9,) p' LI-0551 LI-0552 LI-0553 LI-0554) (yy,rj f 4
18.5 17.18 1.67 >18.5%'of- .>17.8% of
- 1. Start Motor-Driven Pumps Harrow range Warrow range (z t. 8)* (f y,1fy' instrument instrument span.
span.(JTft)Y (351)"
1 18.5 17.18 1.67 >18.5% %f >17.8%Aof Start Turbine-Driven Pump
- 2. **rr " "*" i"""** "*"
(2/< S)* ('fr * ') ^ instrument instrument
- V* Y" ! S * 'Y InSiY: N e p rei,//e d g j, fe ,. ,,,,f,. ,/,/,j,, f(g l l ,5 J/,] _ jg a,a,as aaa,,_n.a;a u_a an,a, w w ,u.,_,c .
- n .
.3 :
er TABLE 2.2-1 (Continued) 8 REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS
_C' EN 101AL SENSOR c= ALLOWANCE ERROR se (S) TRIP SETPOINT ALLOWA8LE VALUE FUNCTIONAL UNIT (TA) ,Z.
l
(( 21950 psig
' 3.1 0.71 1.67 21960 psig**
- 9. Prestsrizer Pressure-tow
"' (Pi -0455A,0&C, PI-0456 &
- PI-0456A, PI-0451 & PI-0457A,
"* PI-0458 & PI-0458A) 0.71 1.67 $2385 psig 12395 psig
- 10. Pressurizer Pressure-High 3.1 (PI-0455A,8&C, PI-0456 &
PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-0458A)
Pressurizer Water Level-High 8.0 2.18 1.67 192% of instrument $93.9% of instrument
- 11. span span f (LI-0459A, LI-0460A, LI-0461) 1.87 0.60 290% of loop 289.4% of loop
- 12. Reactor Coolant flow-Low 2.5 design flow
- LOOP 2 LOOP 3 LOOP 4 (LOOP 1 S# FI-0414 FI-0424 FI-0434 FI-0444 FI-0415 FI-0425 FI-0435 FI-0445 FI-0416 FI-0426 FI-0436 FI-0446) 18.5 17.18 1.67 218.5% (37.8)*** 217.00-(35.9)***
- 13. Steam Generator Water Level of narrow range of narrow range Low-Low (21.8)*** (18.21)*** instrument span instrument span LOOP 2 LOOP 3 LOOP 4 (LOOP 1 LI-0517 LI-0527 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 L I-0519 LI-0529 LI-0539 LI-0549 LI-0551 LI-0552 LI-0553 LI-0554) 6.0 0.58 0 29600 volts 29481 volts
- 14. Undervoltage - Reactor (70% bus voltage) (69% bus voltage)
Coolant Pumps 3.3 0.50 0 257.3 Hz 257.1 Hz
- 15. Underfrequency - Reactor Coolant Pumps
- Loop design flow = 95,700 gpm
- Iime constants utilized in the lead-lag controller for Pressurizer Pressure-Low are 10 seconds for lead and 1 second- for lag. CHANNFL CALIBRATIDN shall ensure that these time constants are adjusted to these values.
- The val.se stated inside the parenthesis is for instrumentation that has the-lower tap at elevation 333";
the value stated outside the parenthesis 'is for instrumentation that has the lower tap at elevation 438".
~'
-?
i- ,,.
' TABLE _?.3-3 (Continuedl - ...
" =j .
5 * -
ca 140 ENGINEERED SAFETY FEATURES ACTUAT10N SYSTEM INSTRUMENIATION 1 RIP SEIPOINTS 10iAL S[N50R c= ERROR . .
ALLOWANCE man,
' 2:
(5) _ TRIP SEfPOINT AltDWABLE VAtUE (TA) Z fkFUNCTIONALUNil
- 5. lurbine trip and Feedwater Isolation (Continued) e 1.67 $79.9% (87.9)*
5.1 2.18 $78.0% (86.0)* of of narrow range ro c. Steam Generator Water (8.62)* instrument Level--High-High (P-14) (14.0)* span. Instrument span.
LOOP 2 LOOP 3 LOOP 4 (LOOP 1 11-0517 L1-0527 LI-0537 LI-0547 L1 -0516 LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549 LI-055 LI-0552 .LI-0553 L1-0554)
Safety Injection See f unctional Unit I above f or all Safety injection trip
- d. Setpoints and Allowable Values.
N#* 6. Auxiliary f eedwater w N.A. N.A. N.A. N.A.
- a. Automatic Actuation Logic N.A.
da
"" and Actuation Relays
- b. Steam Generator Water Level--
Low-Low LOOP 2 LOOP 3 LOOP 4 (LOOP 1 LI-0517 L I -052 7 LI-0537 LI-0547 LI-0518 LI-0528 LI-0538 LI-0548 L 1 -0519 LI-0529 LI-0539 LI-0549 L1-0551 LI-0552 LI-0553 LI-0554)
Star'. Motor-Driven Pumps 18.5 17.18 1.67 218.5% (37.8)* of 217.8% {35.9)* of
- 1. narrow range narrow range (21.8)* (18.21)* instrument span.
instrument span.
Sta-t Turbine-Oriven Pump 18.5 17.18 1.67 .218.5% (37.8)* of' 317.8% (35.9)* of
- 2. narrow range narrow range -
(21.8)* (18.21)* instrument instrument span. span.
- The value stated inside the parenthesis is for instrumentation that has the lower tap at elevation 333"; the value stated outside the parenthesis is for instrumentation that has~ the lower tap at elevation 438*.
t =- ___ . . .