|
---|
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
ATTACHMENT 2 PROPOSED TECHNICAL SPECIFICATION Marked-up Technical Specifications Pages.
2-5 3/4 3-23 3/4 3-24 3/4 3-25 3/4 3-26 Note: Values which have changed as a result of this review are shown as "ballooned" changes. The other changes shown were submitted previously under letter L-90-417.
9107120109 910708 PDR ADOCK 05000250 P PDR
0 0 TABLE 2.2 (Continued)
REACTOR TRIP SYSTEH INSTRUMENTATION TRIP SETPOINTS FUNCTIONAL UNIT ALLOWANCE TA Z S TRIP SETPOINT ALLOWABLE VALUE
- 12. Steam/Feedwater Nis@atch Flow tw 40 P g.c 7 7,344 Feed Flow ~~ ~ Feed Flow+ ~3.~+>
Coincident Mith below stean flow below steaa flow q, f9 2.
Steam Generator Mater Level-Low 33',]2.
>15K of narrow range instrument g-~.f n-range instrument span span
+Ps + 7op~ Pcs l484p4 9~ ya/%pc
- 13. Undervoltage - 4.16 kV u,4',P Busses A and 8 ch-knss ~eh-bus W1
- 14. Underfrequency - Trip of Reactor Coolant Pump Breaker(s) Open
>56.1 Hz >~ Hz
- 15. Turbine Trip p +,D
- a. Auto Stop Oil Pressure >45 psig psig
- b. Turbine Stop: Valve N.A. N.A, N.A ~ Fully Closed """ Fully Closed <<~
Closure
- 16. Safety In)ection Input H.A o H.A. H.A. N. A. N.A.
from ESF
)7. Reactor Trip System Interlocks gyp/D
- a. Intermediate Range x 10-~o amp Neutron Flux, P-6 Limit switch is set when Turbine Stop Valves are fully closed. ~~
i5hznr Ju rg Fi'gg, g,t% 'S~aub 4d~+c~R~wxw~ ZFS >r ++ ~'s~ie
~~~ 57zw~
l Pl t
E' g
TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEH TRIP
@ FUNCTIONAL UNIT ALLSfANCE TA Z S SETPOINT ALLOWABLE VALUES
'i I
(
Safety -Injection (Reac0 Trip, Turbine Trip, Feebler Isolation, EA Control Rooa Ventilation Isolation, Start Diesel Generators, Contain-Qo aent Phase A Isolation (except Nanual SI), Containment Cooling Fans, Containment Filter Fans, Start Sequencer, Coeponent Cooling Water, Start Auxiliary Feedwater and Intake Cooling itater) lo,3 bb l3. p
- a. Nanual Initiation N.A N.A N.A N.A.
00 I b. Autoaatic Actuation Logic .A N.A N.A.
Col a.o +.o
- c. Containment Pressure-High psig psig lg.o 8.+ I.+ laaa ter Z,
- d. Pressurizer Pressure-Low +-+. >&&psig WWps3g
+4, I.<7 +(c + leo II+
- e. High Differential Pressure <%0-psi W~psi Be@men the Steaa Line Header and any Steaa Line.
l4.'y Z.8C
- f. Steaa Line Flaw-High <A function defined as follows: A hp corresponding to
+c lo Sfea 4t ~ (t<<<Wv) at lC load increa-ing linearly 4e-a-corres onding tp Z-3 + ~p~ few Q~ ~sa~. ~Zc simba 4'i u at ull load.
4 A f~~c4'~< Aevi'~ed ~s (et(~us: A 'De(4 $ ~ries ~<~g <o +g t 2 ! ~+ Co + 4 gree
+c. LZZ,. 4 ~ Ske~ 4'4u a4 ~[(
V Cf~ ~(e~ ~~ [f P~~$ 4l'/ ~
~ ~ I C
~~ C ~ ~ ~+ ~
<wc'+'~
s ques ae'PlL'< f< tgg@C7g %q 44gg~ ~~ lay O~ )Ct 4 0 JA'6 jI~Q Ca, cp
.mvC <<l c v C) g ~ ~ Mfi+k $O g g ~ 'w p~ J>>/ *SHAW
~ ~ 4 ~
tc ~ e~~"i~ < Ot~ 4" a%~~ p< "c Po ~
(5'~ ~,~ tmt,
~ gav.~ ~~ Qo r~g~ (.n cr p,vs~
l 7 'g~(v'. >gpwq ~ ~ ~w ~r~ee<<e~e ~
( f~gc ~J )
qt r
t%'~ egg~ ~~
ICICLE e % 0 t
)>> o, t(+
o " e a
~
c ~~
Og 5'8,
~~~~o 0 0 e o~ "+ e c~ ~~+ (0 g c"-'-~
~
~ply 3 ~
TABLE 3. 3-3 (Continued)
ENGINEEREO SAFETY FEATURES ACTUATION SYSTEH C)
TRIP
@ FUNCTIONAL UNIT ALLOWANCE TA Z S SETPOINT ALL(NABLE VALUES S.o l.tp 4(+ S88 I
Coincident sith:
Steaa Generator 1
>QS psig ++ psig EA Pressure Ler Ob or Qo T -Lee 2.0 1.0 >543'F >542.5'F
- 2. Containment Spray Zl-3 Z-7
- a. Autoaatic Actuation Logic N.A N. A N.A N.A. N.
and Actuation Relays Zc>.o Containaent Pressure b.. High High- <39-.$ psig sig Coincident Hth: q:o Cab I Contairaent Pressure-High <6-.0 psi g psig
- 3. Contairaent Isolation lo. $
- a. Phase "A" Isolation
- 1) Nanual Initiation N.A N.h. N.h. N.A. N.A.
- 2) Autoaatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
and Actuation Rel~s
- 3) Safety Injection see itea 1 See Itea 1 above for all Safety Injection Trip Setpoints and All twable Values.
- b. Phase "8" Isolation
- 1) Nanual Initiation N.A. N.A. N.A. N.A. N.A.
I
+V; t ~
ag
~
I Q Q I
l~ Q
~l
~p o~a e
/t hi(
, f~n 0
I ci
~
TABLE 3.3-3 (Continued)
ENGINEEREO SAFETY FEATURES ACTUATION SYSTEH TRIP
~ FUNCTIONAL UNIT ALLO/ANCE TA Z S SETPOINT ALLOWABLE VALUES I
g 3. Centerment Ieolet140'Ironed) R.7
? 1-3 CA 2) Autoaatic Actuation Logic N.A. N A. N.A. N.A. N.A.
Ca> and Actuation Relays 70 O
- 3) Containment Pressure-High-High
<39-.0 psi g ~~sig Coincident Ath: 0+ 6,O + O Contairaent Pressure-High <6-.8 psig psig lc. 3
- c. Containaent Ventilation Isolation
- 1) Containeent Isolation N.A. N.A. N.A. N.A. N.A.
Nanual Phase A or Manual Phase B
- 2) Autoaatic Actuation Logic N.A. N.A. N.A. N.A. N.A.
and Actuation Relays
- 3) Safety Injection see itea 1 See Itea 1. above for all Safety Injection Trip Setpoints and Allowable Values.
N.A. e.A
- 4) Contairaont Radio- Particulate (R-ll) activity-High (1) <6.1 x 10s.CPH t'aseous (R-12)
See (2) ( ws6g.w)
<
5
~
- 4. SteaN Line Isolation
- a. Nanual Initiation N.A. N.A. N.A. N.A. N.A C7
+av'heebie (R- l<3 ~ a B x to+ gt~
4a.se,ou.~ (.w- la. ) gee. (. a-)
~ )
k Pc%
~ >>
ya 4>>
>>
g'r
~ r P ~
~
rI I I >>
~ y
'>> ~ ~
>> >>
>> 'I
>> ~ >>
l ~
I
~
- ~
I, ~
>>
~ a P
C
~,>>
~ A .<~~~~'o< a~u,~ea
~~""" < aV a ~~spo~O~~g +-
TASLE 3.3-3 (Continued) ~~~asi ~[ t,'
ENGINEEREO SAFETY FEATURES ACTUATION SYSTEN
'-~.~~~ vt I Zp, ( +/
TRIP
~ FUNCTIONAL UNIT ALLOWANCE TA Z S SETPOINT ALLSOSLE VALUEg I
Q4 Stem Line Isolation fgiiaCinued) '2.7 M 2Z ~
CA b. Automatic Actuation Logic N.A. N.A N.A. N.A. N.A..
Ob and Actuation Relays 7o.o Qo
- c. Contairaent Pressure-High- <%48-psi g psig High Coincident with: 9:o +. 5 Containment Pressure-High Z.sb tlP.w psig psig
- f. Stem Line Flow-High <A function defined [ 3 as follows: A hp corresponding to 9.o / sk~ (tow at OX load increas-ing linearly 4o-a Zo (~ l~aJ 4 a. va.tw corres onding to lZO (e g fcwd at full load.
I 3'.o lV Z3 4 t'F S88 Coincident with: +-w >688 psig ~~psig Stem Line Pressure-Low or T -Low 4.0 2.0 1.0 >5434F )542. 54F g5. Feedwater Isolation 5 a. Automatic Actuation Logic N.A. N.A N.A. N.A. N.A.
and Actuation Relays 8 b. Safety Injection see item 1 See Itea 1. above for all Safety Injec't$ on Trip Setpoints and Allowable Values.
R C
~e I 0 CA
\ Jt
~ ga A
0 0
0