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| {{#Wiki_filter:.. . ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 | | {{#Wiki_filter:. |
| * REVISED PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGE PROPOSED CHANGES September 27, 1991 1 Page
| | ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 REVISED PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGE PROPOSED CHANGES September 27, 1991 1 Page |
|
| |
|
| ===5.2 CONTAINMENT===
| | 5.2 CONTAINMENT DESI<GN FEATURES (Cont'd) 5.2.2 Penetrations |
| | : a. All penetrations through the steel -1 i ned concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design. |
| | : b. The automatically actuated containment isolation valves are designed to close upon high radiation or high pressure in the containment structure. No single component failure in the actuation system will prevent the isolation valves from functioning as designed. |
| | 5.2.3 Containment Structure Cooling Systems |
| | : a. The containment air cooling system includes four separate self-contained units which cool the containment air during normal operation and limit the pressure rise in the event of a design accident. Three units, with a total cooling water flow of 5580 gpm with an inlet temperature of 85°F, will remove 230 x 106 Btu/hr of heat. |
| | : b. The containment spray system .is capabl~ of removing 233 x 106 Btu/hr (two pumps) from the containment atmosphere at 283°F by spraying the water from the 270,000-gallon SIRW tank. |
| | Recirculation of spray water from the containment sump through heat exchangers into the containment atmosphere is also provided. Under6 this mode of operation, the heat removal capability is 167 x 10 Btu/hr based upon 4000 gpm of component cooling water flow with 114°F inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283°F inlet temperature. |
| | 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5.3.1 Primary Coolant System Design Pressure and Temperature The primary coolant system is designed, and shall be maintained: |
| | : a. In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant to the surveillance requirements, |
| | : b. For a pressure of 2500 psia, |
| | : c. For a temperature of 650°F, except the pressurizer, ~hich shall be 700°F, and |
| | : d. With a volume of approximately 10,900 cubic feet. |
| | 5-2 Amendment No. J$~ |
|
| |
|
| DESI<GN FEATURES (Cont'd) 5.2.2 Penetrations
| | ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 REVISED PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGE EXISTING PAGE WITH PROPOSED CHANGES MARKED September 27, 1991 1 Page |
| : a. All penetrations through the steel -1 i ned concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design. b. The automatically actuated containment isolation valves are designed to close upon high radiation or high pressure in the containment structure.
| |
| No single component failure in the actuation system will prevent the isolation valves from functioning as designed.
| |
|
| |
|
| ====5.2.3 Containment====
| | ~ " |
| | | ,5.,2 5.2.2 CONTAINMENT DESIGN FEATURES (Cont'd) |
| Structure Cooling Systems a. The containment air cooling system includes four separate contained units which cool the containment air during normal operation and limit the pressure rise in the event of a design accident.
| | Penetrations |
| Three units, with a total cooling water flow of 5580 gpm with an inlet temperature of 85°F, will remove 230 x 10 6 Btu/hr of heat. b. The containment spray system .is of removing 233 x 10 6 Btu/hr (two pumps) from the containment atmosphere at 283°F by spraying the water from the 270,000-gallon SIRW tank. Recirculation of spray water from the containment sump through heat exchangers into the containment atmosphere is also provided.
| | : a. All penetrations through the steel-lined concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design. |
| Under this mode of operation, the heat removal capability is 167 x 10 6 Btu/hr based upon 4000 gpm of component cooling water flow with 114°F inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283°F inlet temperature.
| | : b. The automatically actuated containment isolation valves are designed to close upon high radiation or high pressure in the containment structure. No single component failure in the actuation system will prevent the isolation valves from functioning as designed. |
| | | 5.2.3 Containment Structure Cooling Systems |
| ===5.3 NUCLEAR===
| | : a. The containment air cooling system includes four separate self-contained units which cool the containment air during normal operation and limit the pressure ris&.i.in the event of a design accident. Three units, each with a~cooling water flow of ~875 ssso gpm with an in 1et temperature of ~F, wi 11 remove~ x 106 Btu/hr of heat. es i3o |
| STEAM SUPPLY SYSTEM (NSSS) 5.3.1 Primary Coolant System Design Pressure and Temperature The primary coolant system is designed, and shall be maintained:
| | : b. The containment spray system is capable of removing 233 x 106 Btu/hr (two pumps) from the containment atmosphere at 283°F by spraying the water from the 270,000-gallon SIRW tank. |
| : a. In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant to the surveillance requirements, b. For a pressure of 2500 psia, c. For a temperature of 650°F, except the pressurizer, shall be 700°F, and d. With a volume of approximately 10,900 cubic feet. 5-2 Amendment No.
| | Recirculation of spray water from the containment sump through heat exchangers into the containment atmosphere is also provided. |
| ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255
| | Under6 this mode of operation, the heat removal capability is 167 x 10 Btu/hr based upon 4000 gpm of component cooling water flow ) |
| * REVISED PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGE EXISTING PAGE WITH PROPOSED CHANGES MARKED September 27, 1991 1 Page
| | with 114°F inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283°F inlet temperature. |
| " .. . ,5.,2 5.2.2
| | 5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5.3.1 Primary Coolant System Design Pressure and Temperature The primary coolant system is designed, and shall be maintained: |
| * CONTAINMENT DESIGN FEATURES (Cont'd) Penetrations
| | : a. In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal \. I degradation pursuant to the surveillance requirements, ' |
| : a. All penetrations through the steel-lined concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design. b. The automatically actuated containment isolation valves are designed to close upon high radiation or high pressure in the containment structure. | | .' I I |
| No single component failure in the actuation system will prevent the isolation valves from functioning as designed. | | : b. For a pressure of 2500 psia, |
| | | : c. For a temperature of 650°F, except the pressurizer, which shall 'I* |
| ====5.2.3 Containment====
| | be 700°F, and |
| | | .~ i |
| Structure Cooling Systems a. The containment air cooling system includes four separate contained units which cool the containment air during normal operation and limit the pressure ris&.i.in the event of a design accident. | | : d. With a volume of approximate1y 10,900 cubic feet. |
| Three units, each with water flow of ssso gpm with an in 1 et temperature of wi 11 x 10 6 Btu/hr of heat. es i3o b. The containment spray system is capable of removing 233 x 10 6 Btu/hr (two pumps) from the containment atmosphere at 283°F by spraying the water from the 270,000-gallon SIRW tank. Recirculation of spray water from the containment sump through heat exchangers into the containment atmosphere is also provided. | | 5-2}} |
| Under this mode of operation, the heat removal capability is 167 x 10 6 Btu/hr based upon 4000 gpm of component cooling water flow ) with 114°F inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283°F inlet temperature.
| |
| | |
| ===5.3 NUCLEAR===
| |
| STEAM SUPPLY SYSTEM (NSSS) 5.3.1 Primary Coolant System Design Pressure and Temperature The primary coolant system is designed, and shall be maintained: | |
| : a. In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant to the surveillance requirements, b. For a pressure of 2500 psia, c. For a temperature of 650°F, except the pressurizer, which shall be 700°F, and d. With a volume of approximate1y 10,900 cubic feet. 5-2 \. I ' I . ' I ' I* . i}} | |
|
|---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML18066A6641999-09-30030 September 1999
Proposed Tech Specs Re Surveillance Implementation
ML18066A6501999-09-17017 September 1999
Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8
ML18066A5911999-07-30030 July 1999
Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432
ML18066A5691999-07-19019 July 1999
Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS
ML18066A5011999-06-11011 June 1999
Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9
ML18068A5851999-05-0303 May 1999
Proposed Tech Specs Section 3.5,converting to ITS
ML18066A4551999-04-0707 April 1999
Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1
ML18066A4431999-03-30030 March 1999
Proposed Tech Specs Section 3.7,converting to ITS
ML18066A4251999-03-22022 March 1999
Revised TS Pages for ITS Section 3.4
ML20207B2501999-03-0101 March 1999
Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS
ML18066A3281998-11-0909 November 1998
Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17
ML20195E4451998-11-0909 November 1998
Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI
ML20154N2901998-10-12012 October 1998
Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs
ML20151Z8111998-09-14014 September 1998
Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1
ML18066A3021998-09-14014 September 1998
Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages
ML18066A2011998-06-17017 June 1998
Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses
ML18065B1801998-03-13013 March 1998
Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown
ML18067A8161998-01-26026 January 1998
Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20
ML18066A4901998-01-20020 January 1998
Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment.
ML18067A7071997-10-0101 October 1997
Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12
ML18067A6731997-09-0303 September 1997
Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys
ML18067A6771997-09-0303 September 1997
Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16
ML18067A6001997-06-27027 June 1997
Proposed Tech Specs Revising Electrical Power Systems
ML18067A4701997-03-28028 March 1997
Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174
ML20137H5901997-03-27027 March 1997
Proposed Tech Specs Change Request Re Change in Co Name
ML18067A4531997-03-26026 March 1997
Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown
ML18065B0331996-10-25025 October 1996
Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS
ML18065B0171996-10-18018 October 1996
Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR
ML18065A9551996-10-0202 October 1996
Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves
ML18065A9111996-09-0404 September 1996
Proposed Tech Specs 3.7, Electrical Power Systems.
ML20117K9581996-09-0303 September 1996
Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments
ML18065A8631996-08-14014 August 1996
Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items
ML18065A5861996-03-29029 March 1996
Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1
ML18065A4911996-02-0606 February 1996
Proposed Tech Specs Re Removal of cross-train Testing Requirements from LCO Action Statements
ML18065A4411996-01-18018 January 1996
Proposed Tech Specs Allowing Use of 10CFR50 App J Option B Containment Testing & Use of Warning Light to Identify Certain High Radiation Areas
ML18065A4361996-01-18018 January 1996
Proposed Tech Specs Re Primary Coolant Pump Flywheel Insps
ML18065A4111996-01-10010 January 1996
Proposed Tech Specs,Requesting Exemption from 10CFR50 App J & TS Change Request Concerning Local Leak Test Requirements for Emergency Escape Airlock in Plant Containment Bldg
ML18065A3841996-01-0505 January 1996
Proposed Tech Specs,Revising SDC Requirements & Bases for TS Section 3.1.9.3 Prior to 1996 Refueling Outage
ML18065A3771995-12-27027 December 1995
Proposed Tech Specs,Rewriting Electrical Power Sys Sections of TS & Bases to Closely Emulate STS
ML18065A3481995-12-11011 December 1995
Proposed Tech Specs,Revising Administrative Controls Section to Emulate CE STS by Removing Review & Audit Requirements of Section 6.5 & Record Retention Requirements of Section 6.10 of TS Relocating in CPC Quality Program Description
ML18065A3341995-12-0606 December 1995
Proposed Tech Specs,Relocating Crane Operation & Movement of Heavy Loads Requirements & Bases from TS to Other Plant Documents Prior to 1996 Refueling Outage
ML18065A1761995-10-17017 October 1995
Proposed Tech Specs,Changing Pressurizer Cooldown Limit from 100 to 200 F/H,Adding Word Shall to TS 3.1.2c,adding Average Hourly to Column Headings in TS 3.1.2c & Removing Action 3.3.3C from Page 3-31 to 3-30
ML18065A1241995-09-21021 September 1995
Proposed Tech Specs Re Diesel Generator Testing
ML18064A8411995-07-0505 July 1995
Proposed Tech Specs,Deleting Section 6.4, Training, & Revising Sections 6.5.1.2 on Plant Review Committee Composition & 6.5.3.1 & 6.5.3.2,clarifying & Modifying Function & Composition of Plant Safety & Licensing Staff
ML18064A7611995-05-0101 May 1995
Proposed Tech Specs Re Requirements for Periodic DG Peak Load Tests
ML18064A7331995-04-27027 April 1995
Revised Proposed Ts,Consisting of Changes to Basis in First Paragraph of Page 3-2 & Rev to List of Approved Methodology Repts
ML18064A7361995-04-27027 April 1995
Proposed Tech Specs,Supporting Action Statements for Inoperable Safety Valves in Proposed Specs 3.1.7 of TS Change Request of 950103
ML18064A6631995-03-30030 March 1995
Proposed Tech Specs for One Time Surveillance Deferment
ML18064A6691995-03-24024 March 1995
Proposed TS Re pressure-temp Limits
ML18064A6221995-02-20020 February 1995
Proposed TS Figure 3-4, LTOP Setpoint Limit.
1999-09-30
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML18066A6641999-09-30030 September 1999
Proposed Tech Specs Re Surveillance Implementation
ML18066A6501999-09-17017 September 1999
Final Clean Copies of ITS & Bases Pages Incorporating Proposed Changes,Editorial Changes & Bases Clarifications as Result of Ongoing Reviews to ITS LCOs 3.5.2,3.6.3,3.6.6, 3.7.5 & 3.7.7 & 3.7.8
ML18066A5911999-07-30030 July 1999
Proposed Tech Specs Sections 3.3,3.5 & 3.6,converting to Its,Per NUREG-1432
ML18066A5691999-07-19019 July 1999
Proposed Tech Specs Section 3.7, Plant Systems, Converting to ITS
ML18066A5011999-06-11011 June 1999
Proposed Tech Specs Pages Re 980126 Submittal & Replacement Pages for Sections 3.3,3.4 & 3.9
ML18068A5851999-05-0303 May 1999
Proposed Tech Specs Section 3.5,converting to ITS
ML18066A4551999-04-0707 April 1999
Proposed ITS Pages 3.1.4-2 & 3.1.4-8,revising Completion Time for Action D.1
ML18066A4431999-03-30030 March 1999
Proposed Tech Specs Section 3.7,converting to ITS
ML18066A4251999-03-22022 March 1999
Revised TS Pages for ITS Section 3.4
ML20207B2501999-03-0101 March 1999
Proposed Tech Specs Sections 2.0,3.1 & 3.2,converting to ITS
ML18066A3281998-11-0909 November 1998
Proposed Tech Specs,Deleting CVCS Operability Requirements Currenty in LCOs 3.2 3.17.6 & Associated Testing Requirements Currently in SRs 4.2 & 4.17
ML20195E4451998-11-0909 November 1998
Proposed Tech Specs,Converting to Its,Consistent with NUREG-1432,Rev 1,in Response to 980824 RAI
ML20154N2901998-10-12012 October 1998
Proposed Tech Specs Sections 1.0,3.0,4.0 & 5.0,converting to Improved Tech Specs
ML18066A3021998-09-14014 September 1998
Proposed Tech Specs Markups of Previously Submitted Pages & Revised ITS Submittal Pages
ML20151Z8111998-09-14014 September 1998
Proposed Tech Specs Converting to Improved Tss, Consistent with NUREG-1432,Rev 1
ML18066A2011998-06-17017 June 1998
Proposed Tech Specs,Reflecting Reduced Min Reactor Vessel Flow Rate Assumption in Accident Analyses
ML18066A1841998-06-10010 June 1998
Simulator Four-Year Test Rept & Schedule for Performance Testing for Next Four-Year Period.
ML18068A3451998-04-29029 April 1998
Rev 9 to EI-9, Offsite Radiological Monitoring.
ML18068A3441998-04-28028 April 1998
Rev 3 to EI-6.6, Gamma E Determination.
ML18065B2271998-04-21021 April 1998
Reactor Vessel Neutron Fluence Methodology.
ML20217C3101998-03-24024 March 1998
Palisades,Review of Actual Fluence Determination
ML18065B1801998-03-13013 March 1998
Proposed Tech Specs Allowing Installation of Plant Mod W/O Requiring Plant Shutdown
ML18065B2021998-03-10010 March 1998
Rev 7 to Relocated TS Per GL 89-09.
ML18067A8161998-01-26026 January 1998
Proposed Tech Specs Converting to Improved Ts,Consistent W/ NUREG-1432,Rev 1.Includes Vols 1-20
ML18066A4901998-01-20020 January 1998
Proposed Tech Specs Re Partial Response to 990126 Request RAI for ITS Section 3.6, Containment.
ML20197G3851997-12-17017 December 1997
Rev 17 to Palisades Nuclear Plant Suitability,Training & Qualification Plan
ML18065B2321997-10-24024 October 1997
Rev 5 to Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18067A7071997-10-0101 October 1997
Proposed Tech Specs,Stating That TS Flywheel Insp Period Be Lengthened to Ten Years & Deleting Note of Insp at End of Cycle 12
ML18067A6731997-09-0303 September 1997
Proposed Tech Specs,Updating TS to Reflect Capabilities of Installed CR Ventilation Equipment & to Emulate Std TS, CE Plants - NUREG 1432 Requirements for That Sys
ML18067A6771997-09-0303 September 1997
Proposed Tech Specs,Deleting Snubber Operability Requiements in LCO 3.20 & Snubber Testing Requirements Currently in SR 4.16
ML18067A6001997-06-27027 June 1997
Proposed Tech Specs Revising Electrical Power Systems
ML18067A4701997-03-28028 March 1997
Proposed Tech Specs Pp Supporting Completion of Administrative Control Changes Proposed in 951211 Safety Evaluation for Amend 174
ML20137H5901997-03-27027 March 1997
Proposed Tech Specs Change Request Re Change in Co Name
ML18067A4531997-03-26026 March 1997
Proposed Tech Specs,Allowing Entry Into Air Lock to Perform Repairs on Inoperable Air Lock Door & Thereby Avoid Potential for Unnecessary Plant Shutdown
ML18067A5151997-02-11011 February 1997
Rev 5 to Health Physics Procedure HP 10.10, Palisades Radiological Environ Program Sample Collection & Shipment.
ML18065B2011996-12-24024 December 1996
Rev 11 to Offsite Dose Calculation Manual.
ML18065B0861996-11-27027 November 1996
Corrected Pages 14 & 15 to Rev 18 to EM-09-02, Inservice Testing Program Relief Request Valve Relief Request 20.
ML20134P4071996-11-19019 November 1996
Suitability,Training & Qualification Plan, Rev 16
ML20137G3871996-10-29029 October 1996
Rev 6 to Relocated TS Per NRC GL 89-09
ML18065B0331996-10-25025 October 1996
Proposed Tech Specs Change Request,Revising Administrative Controls Sections of Plant TS
ML18065B0171996-10-18018 October 1996
Proposed Tech Specs,Providing Info Necessary for Completion of Review & Approval Process Re Writting Commitment Be Made That Description of Palisades Operating Requirements Manual Will Be Added to FSAR
ML18065A9551996-10-0202 October 1996
Proposed Tech Specs 4.6.1 Re Safety Injection sys,4.6.2 Re Containment Spray sys,4.6.3 Re Pumps & 4.6.4 Re Valves
ML18065A9111996-09-0404 September 1996
Proposed Tech Specs 3.7, Electrical Power Systems.
ML20117K9581996-09-0303 September 1996
Proposed Tech Specs,Revising Administrative Control & Resolution of NRC Comments
ML18065A8631996-08-14014 August 1996
Proposed TS Table 4.3.2 Re Miscellaneous Surveillance Items
ML18065A7661996-06-10010 June 1996
Expired Temporary Change O-96-044 to Rev 17 to SOP-17A, Clean Radwaste Sys.
ML18065A7651996-06-10010 June 1996
Cancelled Tcn O-96-045 to Rev 17 to SOP-17B, Dirty Radwaste Sys.
ML18065A5861996-03-29029 March 1996
Proposed Tech Specs,Upgrading Plant TS & Bases to Emulate STS for Combustion Engineering Plants,NUREG-1432,Rev 1
ML18065A8021996-02-21021 February 1996
Rev 2 to EM-09-13, ISI Pressure Testing Program.
ML20137G3631996-02-16016 February 1996
Rev 10 to Offsite Dose Calculation Manual
1999-09-30
[Table view] |
Text
.
ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 REVISED PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGE PROPOSED CHANGES September 27, 1991 1 Page
5.2 CONTAINMENT DESI<GN FEATURES (Cont'd) 5.2.2 Penetrations
- a. All penetrations through the steel -1 i ned concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design.
- b. The automatically actuated containment isolation valves are designed to close upon high radiation or high pressure in the containment structure. No single component failure in the actuation system will prevent the isolation valves from functioning as designed.
5.2.3 Containment Structure Cooling Systems
- a. The containment air cooling system includes four separate self-contained units which cool the containment air during normal operation and limit the pressure rise in the event of a design accident. Three units, with a total cooling water flow of 5580 gpm with an inlet temperature of 85°F, will remove 230 x 106 Btu/hr of heat.
- b. The containment spray system .is capabl~ of removing 233 x 106 Btu/hr (two pumps) from the containment atmosphere at 283°F by spraying the water from the 270,000-gallon SIRW tank.
Recirculation of spray water from the containment sump through heat exchangers into the containment atmosphere is also provided. Under6 this mode of operation, the heat removal capability is 167 x 10 Btu/hr based upon 4000 gpm of component cooling water flow with 114°F inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283°F inlet temperature.
5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5.3.1 Primary Coolant System Design Pressure and Temperature The primary coolant system is designed, and shall be maintained:
- a. In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal degradation pursuant to the surveillance requirements,
- b. For a pressure of 2500 psia,
- c. For a temperature of 650°F, except the pressurizer, ~hich shall be 700°F, and
- d. With a volume of approximately 10,900 cubic feet.
5-2 Amendment No. J$~
ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255 REVISED PROPOSED TECHNICAL SPECIFICATIONS PAGE CHANGE EXISTING PAGE WITH PROPOSED CHANGES MARKED September 27, 1991 1 Page
~ "
,5.,2 5.2.2 CONTAINMENT DESIGN FEATURES (Cont'd)
Penetrations
- a. All penetrations through the steel-lined concrete structure for electrical conductors, pipe, ducts, air locks and doors are of the double-barrier design.
- b. The automatically actuated containment isolation valves are designed to close upon high radiation or high pressure in the containment structure. No single component failure in the actuation system will prevent the isolation valves from functioning as designed.
5.2.3 Containment Structure Cooling Systems
- a. The containment air cooling system includes four separate self-contained units which cool the containment air during normal operation and limit the pressure ris&.i.in the event of a design accident. Three units, each with a~cooling water flow of ~875 ssso gpm with an in 1et temperature of ~F, wi 11 remove~ x 106 Btu/hr of heat. es i3o
- b. The containment spray system is capable of removing 233 x 106 Btu/hr (two pumps) from the containment atmosphere at 283°F by spraying the water from the 270,000-gallon SIRW tank.
Recirculation of spray water from the containment sump through heat exchangers into the containment atmosphere is also provided.
Under6 this mode of operation, the heat removal capability is 167 x 10 Btu/hr based upon 4000 gpm of component cooling water flow )
with 114°F inlet temperature through the heat exchanger and 1420 gpm of spray water flow at 283°F inlet temperature.
5.3 NUCLEAR STEAM SUPPLY SYSTEM (NSSS) 5.3.1 Primary Coolant System Design Pressure and Temperature The primary coolant system is designed, and shall be maintained:
- a. In accordance with the Code requirements specified in Section 4.2 of the FSAR with allowance for normal \. I degradation pursuant to the surveillance requirements, '
.' I I
- b. For a pressure of 2500 psia,
- c. For a temperature of 650°F, except the pressurizer, which shall 'I*
be 700°F, and
.~ i
- d. With a volume of approximate1y 10,900 cubic feet.
5-2
