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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to Abb C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20134H3771996-11-0606 November 1996 Proposed Tech Specs of Appendix a Re Cooling Water Sys ML20134E4551996-10-25025 October 1996 Proposed Tech Specs Changing TS 4.4.A, Containment Leakage Tests, Bases to TS Section B.4.4, Containment Sys Tests & Adding TS.6.5.J, Containment Leakage Rate Testing Program ML20129E2591996-09-24024 September 1996 Proposed Tech Specs,Changing TS 4.12 to Incorporate Revised Acceptance Criteria for SG Tubes W/Degradation in Tubesheet Region ML20117P4311996-09-11011 September 1996 Proposed Tech Specs,Revising Plant TS Governing Cw Sys ML20117B2381996-08-15015 August 1996 Proposed Tech Specs 3.3.B.2 Re Containment Cooling Sys & Bases to Conform to Supporting Analyses ML20115G8121996-07-15015 July 1996 Proposed Tech Specs Re Moveable Incore Detector Thimble Reduction ML20095J7951995-12-14014 December 1995 Proposed Tech Specs for Conformance of Administrative Controls Section 6 to Guidance of STS ML20094S2791995-11-28028 November 1995 Proposed Tech Specs Re Radiological Effluent TS Conformance ML20087F3571995-08-0909 August 1995 Proposed Tech Specs Table TS 3.15-1,Pages 1 & 2 & Bases Page B.3.15-1 Marked Up to Implement License Amend Request 1999-08-31
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211K6241999-08-31031 August 1999 Proposed Tech Specs,Changing ISFSI License Conditions 6,7 & 8 & TS 3/4.1 by Permitting Inclusion of Bpras & Thimble Plug Devices in Sf Assemblies Stored in TN-40 Casks ML20206R0621999-05-13013 May 1999 Proposed Tech Specs,Removing Plant Organization Structure Requirement ML20205S3331999-04-20020 April 1999 Proposed Tech Specs Changing Implementation Date for Relocation from TS to UFSAR of Requirements in TS 3.1.E & Flooding Shutdown Requirements in TS 5.1 ML20205Q0351999-04-12012 April 1999 Proposed Tech Specs,Relocating Shutdown Margin Requirements from TS to COLR ML20204H3601999-03-19019 March 1999 Proposed Tech Specs Removing Dates of Two NRC SERs & Correcting Dates of One SER Listed in Section 2.C.4, Fire Protection ML20207F2901999-03-0101 March 1999 Proposed Revised Tech Specs Incorporating Combustion Engineering SG Welded Tube Sleeve TR Rev ML20203A2181999-02-0505 February 1999 Proposed Tech Specs,Changing TS 4.12, SG Tube Surveillance to Incorporate Changes to Abb C-E Sleeve Design Assumptions & Installation Techniques ML20196B9721998-11-25025 November 1998 Proposed Tech Specs,Allowing Limited Inoperability of Bast Level Channels & Transfer Logic Channels to Provide for Required Testing & Maint of Associated Components ML20155G6321998-11-0303 November 1998 Proposed Tech Specs B.3.1-7 & B.3.1-7a,rev 133A Re Reactor Coolant Sys ML20154S2101998-10-23023 October 1998 Proposed Tech Specs Clarifying Conditions That Constitute Operable Irpi Sys Channels ML20195F1391998-10-0808 October 1998 Non-proprietary Version of Rev 1 to NSPNAD-97002, Steam Line Break Methodology ML20151U3651998-09-0404 September 1998 Proposed Tech Specs TS.3.1-5,TS.4.18-1 & B.4.18-1,clarifying SRs & LCOs for Operability for Reactor Coolant Vent Sys ML20237B5061998-08-12012 August 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std Tech Specs ML20151Z9181998-08-0303 August 1998 Rev 0 to 5AWI 6.1.2, Design Outputs,Review & Verification ML20151Z9011998-08-0303 August 1998 Rev 2 to 5AWI 6.1.0, Design Change General ML20236T6041998-07-20020 July 1998 Proposed Tech Specs Incorporating Elevated F* SG Tube Repair Criteria ML20249A7641998-06-11011 June 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20216G0371998-04-13013 April 1998 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20248M1421998-04-0606 April 1998 Draft NRC Insp Manual Temporary Instruction 2515/XXX Fire Protection Functional Insp (Fpfi) ML20216D0591998-03-0606 March 1998 Proposed Tech Specs Updating Heatup & Cooldown Rate Curves, Incorporating Use of Pressure & Temp Limits Rept & Changing Pressurizer PORVs Operability Temp ML20217P0061998-03-0404 March 1998 Proposed Tech Specs Re Status of Relocated Requirements ML20217N9771998-03-0202 March 1998 Proposed Tech Specs 3.8.D Re Spent Fuel Pool Special Ventilation Sys ML20217P1431998-03-0202 March 1998 Proposed Tech Specs Re Conformance of Administrative Controls Section 6 to Guidance of Std ML20202E5691998-02-10010 February 1998 Proposed Tech Specs 1-1 Re One Time Reduction of Mode 6 Reactor Coolant Sys Boron Concentration ML20198N8301998-01-15015 January 1998 Proposed Tech Specs Pages Allowing Use of Moveable Incore Detector Thimble Reduction for Unit 1,cycle 19 ML20198P0791998-01-0808 January 1998 Proposed Tech Specs Pages Re Suppl 5 to 951214 LAR on Conformance of Administrative Controls Section 6 to Guidance of STS ML20151Z9561998-01-0505 January 1998 Rev 0 to 5AWI 6.1.7, Design Change Work Orders ML20198B1471997-12-29029 December 1997 Proposed TS marked-up & Revised Pages,Incorporating Changes Associated w/951214 LAR ML20212F0471997-10-28028 October 1997 Proposed Tech Specs Pages Revising TS Section 4.12,allowing Use of voltage-based SG Tube Repair Criteria ML20151Z9441997-10-20020 October 1997 Rev 0 to 5AWI 6.1.6, Design Review & Approval ML20217F4761997-10-0303 October 1997 Suppl Proposed Tss,Allowing Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20211H7581997-10-0101 October 1997 Proposed Tech Specs Re Physical Mods to Turbine Bldg Cooling Water Header Isolation Logic ML20217C5861997-09-26026 September 1997 Proposed Tech Specs Changes to TS 3.4.B to Change Minimum Conditions for AFW & Permit Startup Operations to Continue W/Inoperable Turbine Driven AFW Pump or Associated Sys Valves Due to Inability to Complete IST Requirements ML20216E4561997-09-0404 September 1997 Proposed Tech Specs,Supporting Conformance to TS Overtime Controls to NRC Guidance Issued 950409 ML20216D1141997-09-0202 September 1997 Proposed Tech Specs,Incorporating Use of New SG Tube Sleeve Designs & Installation & Exam Techniques ML20217M6191997-08-15015 August 1997 Proposed Tech Specs Incorporating C-E SG Welded Sleeve TR, CEN-629-P,Rev 1 ML20149J0251997-06-30030 June 1997 Tech Spec Change Pages B.3.8-2 & B.3.8-5 to Amend Re Spent Fuel Pool Personnel Access Doors ML20141F5011997-05-15015 May 1997 Proposed Tech Specs 3.1.C, Reactor Coolant Sys Leakage & 4.12, SG Tube Surveillance ML20141A0871997-05-0707 May 1997 Proposed Tech Specs Re Spent Fuel Pool Special Ventilation Sys ML20137T2081997-04-10010 April 1997 Proposed Tech Specs,Clarifying Amend Request Re Conformance of Administrative Controls Section 6 to Guidance of STS ML20137W3621997-03-17017 March 1997 Rev 2 to Test Procedure TR-228, Three Hour Fire Test of One and Three Hour Versawrap Raceway Fire Barrier Sys for Conduits & Cable Trays ML20135F7481997-03-0707 March 1997 Proposed Tech Specs Re Cooling Water Sys Emergency Intake Design Basis ML20135A9401997-02-21021 February 1997 Proposed Tech Specs,Allowing Use of Credit for Soluble Boron in Spent Fuel Pool Criticality Analyses ML20134L8901997-02-12012 February 1997 Proposed Tech Specs 3.3-3 Re Safety Injection Pump Low Temp Operations ML20134J6281997-02-0606 February 1997 Proposed Tech Specs 3.3 Re Engineered Safety Features ML20134E9421997-01-29029 January 1997 Proposed Tech Specs Revising Prairie Island Design Bases Re Cooling Water Emergency Intake ML20136H0101997-01-29029 January 1997 Rev 12 to Abnormal Procedure AB-3, Earthquakes ML20135A8251996-11-27027 November 1996 Proposed Tech Specs Incorporating New SG Tube Sleeve Designs & Installation & Exam Techniques ML20135A5091996-11-25025 November 1996 Proposed Tech Specs Implementing Mods Proposed by Suppl to License Amend Request & Revising TS Pp in Final Form to Reflect Changes Proposed by Suppl ML20138G8751996-11-0808 November 1996 Rev 2 to TN-40 Cask Unloading Procedure 1999-08-31
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) EXHIBIT B Prairie Island Nuclear Generating Plant - ,)
License Amendment Recuest Dated November 3. 1987 >
Exhibit'B consists.of marked up pages of the Prairie Island Technical' Specifications showing the proposed changes listed below:
Pace: .-
TS.2.3-1 I
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l 8711100441 B71103 PDR ADOCK 05000202 p PDR
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/ TS.2 3-1' REV 26 9/6/'9 1
l 23 LIMITING SAFETY SYSTEM SETTINOS, PROTECTIVE INSTRUMENTATION applicability Applies to trip settings fo'r instruments. monitoring reactor power <
.and reactor coolant pressure, temperature, flow, and pressurizer level.
Objective To provide for automatic protective action in the event that ;
the principal process variables approach a safety limit.
Specification I
A. Protective instrumentation settirgs for reactor trip shall l i be as follows: l l
- 1. Startup protection I
l a. High flux, intermediate range (high, set point) -
current equivalent to 140% of full power.
- b. High flux, power range (low set point) -
IGM of rated power.
Ydb c. High flux, soureg range -
neutron flux 110 counts /second 4
- 2. Core protection
,l I
- a. l
! High flux, power range (high set point) - l 1108% of rated power.
- b. High pressurizer pressure - $2385 psig. i i
- c. Low pressurizer pressure - >1815 prig. )
'1
- d. Overtemperature AT ;
y l AT S AT, [K1 ~K2 (T-T') (1+t 14g ,s) + 3K (P-P') - f ( AI)]
2 s
where AT, = Indicated A T at rated power T =
Average temperature, F j T' = 567.3 F ']
P = Pressurizer pressure, psig }
P' = psig 2235 g i 1.11 K
2
= 0 0090 i K
3
= 0.000566 c
1
= 30 sec ,
t2 = 4 see 1 4
( _ . . . _ _ _ _ _ _ _m.__ ____._ . _ - - - - -
=
.I
,1
\
EXHIBIT C i j
Prairie Island Nuclear Generating Plant License Amendment Recuest Dated November 3. 1987
. Exhibit C consists of retyped pages of the Prairie Island Technical Specifications showing the proposed changes' listed below:
Page.: i TS.2.3-1 l
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i 1
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j
TS.2.3-1 REV 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION Applicability Applies to trip settings for instruments monitoring reactor power and reactor coo} ant pressure, temperature, flow, and pressurizer level.
Objective To provide for automatic protective action in the event that the principal process variables approach a safety limit.
l
! Specification 1
~
A. Protective instrumentation settings for reactor trip shall be as follows:
- 1. .Startup protection l l
l a. High flux, intermediate range (high set point.) -
l current equivalent to 140% of full power.
l l
-\
- b. High flux, power range (low set point) - '
140% of rated power.
{
I'
- c. High flux, soureg range -
1 neutron flux <10 counts /second
- 2. Core protection
- a. High flux, power range (high set point)~-
1108% of rated power.
- b. High pressurizer pressure - 12385 psig.
l c. Low pressurizer pressure-- >1815 psig.
- d. I Overtemperature 6T j ATt i o 1
~
2(- (1+ ) +' 3(P- M - f (AI)]
where j AT = Indicated AT at rated power T = Average temperature, 'F i
T' = 567.3*F P =
Pressurizer pressure, psig 1 I
P' = psig 2235 j K < l.11 j K - 0.0090 -j K
3
=
0.000566 !
t =
30 sec '
t 2
= 4 sec
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s , ,
l l
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EXHIBIT D I
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Prairie Island Nuclear Generating Plant -
i License Amendment Reauest Dated November 3.'1987' )
.1 ,
Exhibit D consists of NSPNAD-8725, " Analysis of the Revised Low Setpoint
)
j for High Flux, Power Range", October, 1987. ,
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