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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits ML17310A5211993-08-0505 August 1993 Proposed Tech Specs Requesting to Change Word Pressurizer to RCS for Item #4 in Both Tables 3.3-10 & 4.3-7 ML17310A5151993-08-0505 August 1993 Proposed Tech Specs Changing Surveillance Frequency from Monthly to Quarterly for Channel Functional Tests for RPS & ESFAS Instrumentation ML17310A4211993-06-30030 June 1993 Proposed Tech Specs Requesting Addl Operating Margin in Time Response of Turbine Driven AF Pump to SG Low Level Signal ML17310A2981993-05-20020 May 1993 Proposed TS 4.7.9 Re SR to Ensure Operability of Snubbers ML17306B2671993-01-25025 January 1993 Proposed Tech Specs,Reflecting Revised Train a Kw Value to Be Rejected & Load Designation & Incorporation of Provisions Discussed in 920508 Ltr Re DG Full Load Rejection Testing ML17306B1451992-11-20020 November 1992 Proposed Tech Specs Revising TS 3.2.1 Lhr, & TS 3.2.4, DNBR Margin, Increasing Action from 1 H to 4 H for COLSS Allowed Out of Svc Time Before Requirements Based on More Restrictive Core Protection Calculator Limits Apply ML17306A6491992-04-13013 April 1992 Proposed TS 3.4.8.3 Re RCS - Overpressure Protection Sys ML17306A4731992-02-14014 February 1992 Proposed Tech Specs Re Implementation of Generic Ltr 89-01, Implementation of Programmatic Controls for Radiological Effluent TS in Administrative Controls Section of TS & Relocation of Procedural Details of RETS to Odcm.... ML17306A4031992-01-16016 January 1992 Proposed Tech Specs Amend to TS Section 3.6.3,table 3.6-1 Deleting Type C Testing Requirements for Eight Valves ML17306A3701991-12-30030 December 1991 Proposed Tech Spec Table 6.2-1 Re Min Shift Crew Composition ML17306A3781991-12-30030 December 1991 Proposed Tech Spec Section 3.6.1.7 Re Containment Purge Supply & Exhaust Valves 1999-09-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17300B3791999-10-0808 October 1999 Proposed Tech Specs,Waiving Requirement to Perform SR 3.8.4.8 for Unit 1 Channels A,B & C on One Time Basis ML17300B3521999-09-29029 September 1999 Revised Bases Pages,Providing Addl Discussion of Options Available to Exit Required Action G of TS 3.8.1 & Revised Page for TS 3.3.7 ML17300B3321999-09-14014 September 1999 Marked-up Tech Specs Pages to TS 5.5.2 & 5.6.2,making Noted Administrative Changes ML17313B0601999-08-31031 August 1999 Rev 1 to PVNGS TS Bases Implemented Between Aug 1998 & Jul 1999 ML17313B0081999-07-14014 July 1999 Rev 2 to Inservice Insp Program Summary Manual for PVNGS Unit 1. ML17313A9571999-05-26026 May 1999 Proposed Tech Specs,Reducing Spurious Reactor Trip Hazards Associated with Setpoints While Maintaining Plant Protection ML17313A7511998-12-16016 December 1998 Rev 2 to ISI Program Summary Manual, for PVNGS Unit 3 ML17313A4181998-06-0909 June 1998 Proposed Improved Tech Specs Sections 3.5.1 & 3.5.2,revising Safety Injection tanks-operating & Safety Injection Tanks Shutdown ML17313A1141997-11-0707 November 1997 Improved TS Pages for Section 3.0, LCO & SR Applicability, Section 3.1, Reactivity Control & Section 3.2, Power Distribution Limits. Generic Change to NUREG-1432,Rev 1 Incorporated Into Section 3.0 & 3.1 ML17312B6411997-08-28028 August 1997 Proposed Tech Specs,Allowing one-time Extension of Required Surveillance Interval for Msi Sys Portion Only of ESFAS Logic ML20217Q6801997-08-22022 August 1997 Proposed Tech Specs,Clarifying Wording in TS Bases 3/4.6.1.4, Internal Pressure ML20141H7831997-07-18018 July 1997 Proposed Improved Tech Specs Section 3.8, Electrical Power Sys ML20141H7461997-07-18018 July 1997 Proposed Tech Specs,Providing Addl Info Re Improved TS Section 3.4, Rcs ML17312B0311996-11-0606 November 1996 Proposed Tech Specs 3/4.8.1.1 Re A.C. Sources - Operating ML17300B2651996-06-17017 June 1996 Proposed Tech Specs,Changing Section 1.10 & 3.2.8 & Associated Bases for Obtaining Thyroid Dcfs Used in Definition of Dose Equivalent I-131 ML17312A9451996-05-14014 May 1996 Rev 3 to Significant Condition Investigation. ML17312A6491996-04-0101 April 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Temporarily Allow Use of Hoist Instead of Refueling Machine for Movement of Fuel Assembly at Core Location A-07 ML17312A6401996-03-26026 March 1996 Proposed Tech Specs 3/4.9.6,increasing Refueling Machine Overload Cut Off Limit to 2,000 Lb,In 50 Lb Increments,For Removal of Stuck Fuel Assembly from Core Location A-06 ML17312A6321996-03-26026 March 1996 Proposed Tech Specs,Revising TS 3/4.9.6 to Relocate Refueling Machine Overload Cut Off Limit from TS 3/4.9.6 to Plant UFSAR Per Criteria in 10CFR50.36 & Rev 1 of NUREG-1432 STS for C-E Plants. ML17312A6371996-03-23023 March 1996 Proposed Tech Specs,Revising TS SR 4.8.2.1.e, DC Sources, to Suspend Provision of TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Entry Into Mode 4 Following Sixth Refueling Outage ML17312A5691996-03-0505 March 1996 Revised Pages to ISI Program Summary Manual ML17312A5011996-01-17017 January 1996 Revised Page 5-1 Changing Section 5.2.2 to Include Description of Material Used for Control Element Assemblies ML17311B3221995-12-20020 December 1995 Proposed Tech Specs,Reducing Setpoint for MSIS & Rt on Low SG Pressure ML17311B3181995-12-20020 December 1995 Revised Pages to ISI Program Summary Manual ML17311B0301995-07-0303 July 1995 Proposed Tech Specs Re Temp Method to Respond to Sustained Degraded Switchyard Voltage ML17311A9771995-06-21021 June 1995 Proposed Tech Specs,Modifying Tables 3.3-4 & 3.3-5 of Section 3/4.3.2 of Esfa Sys Instrumentation ML17311A8651995-05-0202 May 1995 Proposed TS 3.1.2.6,Figure 3.1-1, Min Borated Water Vols, Relocating Elevations That Correspond to Min Required Water Vols for Spent Fuel Pool Into Site Procedures ML17311A8231995-04-18018 April 1995 Proposed Tech Specs Section 3/4.4.4 Re Sleeving Process for SG Tube Repair ML17312A9381995-02-0303 February 1995 Corrective Action Program. ML17311A5631994-12-28028 December 1994 Proposed TS Sections 3.9.6 & 4.9.6.1 Re Refueling Machine ML17311A5021994-12-0707 December 1994 Proposed Tech Specs,Changing Note 5 to Table 4.3-1 of TS 3/4.3.1 to Allow Verification of Shape Annealing Matrix Elements Used in Core Protection Calculators ML17311A4341994-11-30030 November 1994 Proposed TS 3/4.4.2,changing Pressurizer Code Safety Valve Lift Setting from 2,500 Psia to 2,475 Psia in LCOs 3.4.2.1 & 3.4.2.2 ML17311A3851994-10-31031 October 1994 Proposed Tech Spec Sections 3.9.6 & 4.9.6.1, Refueling Machine. ML17311A3341994-10-0909 October 1994 Proposed Tech Specs Suspending TS 4.0.1 & 4.0.4 for Battery Capacity Testing Requirements Until Mode 4 Following Fifth Refueling Outage ML17311A2171994-08-18018 August 1994 Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss. ML17310B4511994-07-12012 July 1994 Proposed Tech Specs Amend to Add One Action Statement to Table 3.3-3,entry 8 ML17310B4151994-07-0101 July 1994 Proposed Tech Specs Re Reactor Coolant Cold Leg Temperature Vs Core Power Level of TS 3.2.6 ML17310B4331994-06-20020 June 1994 Proposed Tech Specs Sections 5.3.1 & 5.6.1, & New TS Section 3/4.9.13 & Bases 3/4.9.13 ML17310B4091994-06-17017 June 1994 Proposed Tech Specs Removing Five Tables of Component Lists Per GL-91-08 ML17310B1661994-03-28028 March 1994 Proposed Tech Specs Re Min Condensate Storage Tank Indicated Level ML17310B0911994-03-0202 March 1994 SG Tube Insp Plan. ML17310B0771994-02-24024 February 1994 PVNGS Unit 1 Cycle 5 Startup Rept. ML17310B0611994-02-18018 February 1994 Proposed Tech Specs Figure 3.2-1,Section 3/4.1.1.4 & Bases 3/4.1.1.4,establishing Min Temp for Criticality at 545 F for Facilities ML17310B0251994-01-27027 January 1994 Unit 2 Steam Generator Tube Insp Plan Addendum. ML17310B0001994-01-19019 January 1994 Proposed Tech Specs of AF Automatic Actuation Logic Surveillance Frequency Extension ML17310A8361993-11-16016 November 1993 Proposed Tech Specs Table 4.2-4, Min Staffing Requirements for PVNGS Emergencies, in Support of Proposed Rev to Emergency Plan ML17310A7421993-10-27027 October 1993 Revised Unit 1 SG Tube Insp Plan. ML17310A7351993-10-26026 October 1993 Proposed Tech Specs Changing Maximum Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core ML17310A6501993-09-17017 September 1993 Unit 1 SG Tube Insp Plan. ML17310A6161993-09-0808 September 1993 Proposed Tech Specs Section 6.9.1.10 Re Sys 80 Inletflow Distribution to List of Methods Used to Determine Core Operating Limits 1999-09-29
[Table view] |
Text
REACTIVITY CONTROL SYSTEMS MINIMUM TEMPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION
- 3. l. 1.4 The Reactor Coolant System lowest operating loop temperature (T )
shall be greater than or equal to ~F.
S'VN 1
APPLICABILITY: MODES 1 and 28.
ACTION:
With a Reactor Coolant System operating loop temperature (T ld) less than sy6'&2 F, restore T ld to within its limit within 15 minutes or be in HOT STANDBY within the next 15 minutes.
SURVEILLANCE RE UIREMENTS
- 4. l. 1.4 The Reactor Coolant System temperature (T ld) shall be determined to be greater than or equal to 4&2'F:
SVs'.
Within 15 minutes prior to achieving reactor criticality, and
- b. At least once per 30 minutes when the reactor is critical and the ld is less than Reactor Coolant System T cold 5&7'F.
S5'6 than or equal to 1.0.
PWith K ff greater eff PALO VERDE " UNIT 1 3/4 1"5 AMENOMENT NO. EA, 69 P,,
9403020084 9'40218 PDR ADOCK 05000528 FADR
ye ~~<<voarx~vtot<<oNc ~
/Peplos-ce ~ I wi 4g Z < s,e ~ 4 REAC R COOLANT LD LfG T PERATURE vs RE POWER VEI.
575 570
- g. 5 0 568
~ 565 I
REA OF ACC TABLE OP E RATIO 0
g 555 Q
o 55 540
'IO 20 30 0 50 0 70 CORE POWE EVEL,% OF ATED THERM POWER FIGURE 3.2"1 ACTOR COOLA COLD LEG TEMPE URE VS CORE OWER LEVEL PALO VERDE - UNIT l 3/4 2-8 AMEHPMEHT HO. 69
k Z'arses +
REACTOR COOLANT COLD LEG TEMPERATURE vs. CORE POWER LEVEL 580 575 570 568 568 565 AREA OF ACCEPTABLE OPERATION 560 555 CI 552 O 550 u
545 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL,% OF RATED THERMAL POWER FIGURE 3.2-1 REACTOR COOLANT COLD LEG TEMPERATURE vs. CORE POWER LEVEL
~ 'I ~ > T l l
II
REACTIVITY CONTROL SYSTEMS BASES SHUTDOtw MARGIN AND KN 1
(continued)
Other technical specifications that reference the Specifications on SHUT-DOMN MARGIN or K are: 3/4.1.2, BORATION SYSTEMS, 3/4. 1.3, MOVABLE CONTROL ASSEMBLIES, 3/4.3. $ , REFUELING OPERAT10NS-BORON CONCENTRATION, 3/4. 10. 1, SHUTDOMN MARGIN AND K - CEA WORTH TESTS, and 3/4.10.9, SHUTDOMN MARGIN AND KN CEDMS TFST"N 1
3/4. 1.1.3 MODERATOR TEMPERATURE COEFFICIENT (MTC)
The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured
" MTC value is within its limit provides assurances that the coefficient will be maintained within acceptable values throughout each fuel cycle.
3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY s'e5 This specification ensures that the reactor will not be made critical with the Reactor Coolant System cold leg temperature less than SSB F. This limita-tion is required to ensure (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating range, (9 o winiwv~ Vc.mph.~Sure. lc pI ops d'e a/ I 4o~ Sic.eicos J 7e s ~ +>A'. fd. ~
t- +) +A.~ u-e~c- ~a~ Vc.ss ~l i's ~hove, w jn I ~ v~ N7 ~~~
PALO VERDE - UNIT 1 B 3/4 1-la AMENDMENT NO. 23
R INFORMATION ONL HINIHUH TEHPERATURE FOR CRITICALITY LIHITING CONDITION FOR OPERATION re" ~
- 3. L 1.4. The Reactor Coolant System lowest operating loop temperature (T shall be greater than or equal to ~F.
++5 ld)
APPLICABILITY: HODES 1 and 2¹.
ACTION:
With a Reactor Coolant System operating loop temperature (T ld) less than EV5'5R? F, restore T old to within its limit within 15 minutes or be in HOT cold STANDBY within the next 15 minutes.
SURVEILLANCE RE UIREHENTS
- 4. l. 1.4 The Reactor Coolant System temperature (T ld) shall be determined to be greater than or equal to $ 82'F:
- a. Within 15 minutes prior to achieving reactor criticality, and
- b. At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T ld is less than 5&F F.
+88, than or equal to 1.0.
¹With K ff greater eff PALO VERDE - UNIT 2 3/4 1"5 AHENDHENT NO. 88
f J
)R IMFORViATIOR ONLY REACTIVITY CONTROL SYSTEMS BASES SHUTDOWN MARGIN and K (continued)
Other technical specifications that reference the Specifications on SHUTDOWN MARGIN or K are: 3/4.1.2, BORATION SYSTEMS, 3/4.1.3, MOVABLE CONTROL ASSEHBLIES, 3/k. 9.1, REFUELING OPERATIONS"BORON CONCENTRATION, 3/4.10.1, SHUTDOWN HARGIN AND KN 1
- CEA WORTH TESTS, and 3/4.10.9, SHUTDOWN MARGIN AND CEDMS TESTING.
KN 1
.,3/4. 1. 1. 3 HODERATOR TEMPERATURE COEFFICIENT MTC The limitations on moderator temperature coefficient (MTC) are pro-vided to ensure that the assumptions used in the accident and the transient analysis remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to'he reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the coeffi-cient will be maintained within acceptable values throughout each fuel cycle.
3/4. 1.1. 4 MINIMUM TEMPERATURE FOR CRITICALITY g d5 This specification ensures that the reactor will not be made critical with the Reactor Coolant System cold leg temperature less than 592'F. This limitation is required to ensure (1) the moderator temperature coefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating r ange, (g) ~ ~- ~~~ gg~qc,v ~ 4LJ vc. ss p...'ec J 4, Sp~cc' e>ccg4io >H o ~ +)
vasss e,l ls a 6ou4
]4g Mtwlw>~ ~ ~4)'r ~<~ P
~
PALO VERDE - UNIT 2 B 3/4 1-la av)voxEW'o.
0 MINIMUM TEHPERATURE FOR CRITICALITY LIMITING CONDITION FOR OPERATION 3.1.1.4 The Reactor Coolant System lowest operating loop temperature (T ld) shall be greater than or equal to SSZ F.
HODES 1 and 2¹. 6'g5'PPLICABILITY:
ACTION:
- rq, With a Reactor Coolant System operating loop temperature (T ld) less than 5'VS $ 62'F, restore T ld to within its limit within 15 minutes or be in HOT cold STANDBY within the next 15 minutes.,
SURVEILLANCE RE UIREMENTS 4.1. 1.4 The Reactor Coolant System temperature (T ld) shall be determined to be greater than or equal to 5824F:
- a. Within 15 minutes prior to achieving reactor criticality, and
- b. At least once per 30 minutes when the reactor is critical and the Reactor Coolant System T ld is less than $ 97'F.
/SZ than or equal to 1.0.
¹With K eff greater PALO VERDE " UNIT 3 3/4 1-5 AMENDMENT NO. 27i 42
.~
r 1
IPgp la c,e uvi 44 REACT R CO ANT CO LEG EMPER URE vs ORE P R LEVE 58 575 70 O 568
~ 5 C
EA OF A EPTABLE
- n. 5 PERATI W
~ 555 0
o
>0 20 0 40 50 0 7 80 80 OO CORE P ER LEV,%OF TEDT ERMAL WER FIGU 3. 2-REACTOR OOLANT OLD TEHPE TURE . COR PONE EVE PALO VERDE - UNIT 3 3/4 2"8 AHENDHENT NO 42
I I
REACTOR COOLANT COLD LEG TEMPERATURE vs. CORE POWER LEVEL 580 575 570 568 568 565 AREA OF ACCEPTABLE OPERATION 560 555 O 552 550 u
545 10 20 30 40 50 60 70 80 90 100 CORE POWER LEVEL,% OF RATED'THERMALPOWER FIGURE 3.2- I REACTOR COOLANT COLD LEG TEMPERATURE vs. CORE POWER LEVEL
I r
/
iR INFORMATION ONL REACTIYITY CONTROL SYSTEMS BASES SHUTDOWN MARGIN AND KN 1
(continued)
Other technical specifications that reference the Specifications on SHUT-DOMN MARGIN or KN' are: 3/4.1.2, BORATION SYSTEMS, 3/4.1.3, MOVABLE CONTROL ASSEMBLIES, 3/4.9.1, OPERATIONS-BORON CONCENTRATION, 3/4.10.1, SHUT" DOMN MARGIN AND KN -REFUELING CEA MORTH TESTS, and 3/4.10.9, SHUTDOWN MARGIN AND 1
K1
- CEDHS TESTING.
3/4.1.1. 3 MODERATOR TEMPERATURE COEFFICIENT HTC The limitations on moderator temperature coefficient (MTC) are provided to ensure that the assumptions used in the accident and transient analysis remain valid through each fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confirm the MTC value since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup. The confirmation that the measured HTC value is within its limit provides assurances that the coeffi-cient will be maintained within acceptable values throughout each fuel cycle.
4 MINIMUM TEMPERATURE FOR CRITICALITY t'/4.1.1.
This specification ensures that the reactor will not be made critical with the Reactor Coolant System cold leg temperature less than 592'F. This limita-tion is required to ensure (1) the moderator temperature oefficient is within its analyzed temperature range, (2) the protective instrumentation is within its normal operating range, L fg)
C ) m mt~ i~u~ ~eWPQI ~4uWC SW PmutOCaf
~4v ~pep Ib- ) Ti a 4 H> 48p4ion ~/i/. J()
J C~3 +ABC, t"Ca a 44 v L/CAB tt n.4o ve.
JVP~
4C w,P g.vA PALO YERDE - UNIT 3 B 3/4 1-la AMENDMENT NO. 2
A, ~
4%4(
'S 1
1 1
h