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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
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ATTACHMENT 1 Consumers Power Company Palisades Plant Docket 50-255 PROPOSED HTP CORRELATION TECHNICAL SPECIFICATIONS PROPOSED PAGES 9412220068 941213 PDR ADOCK 05000255 p PnR 2 Pages 2:0 SAFETY LIMITING SAFETY SYSTEM 2.1 Safety Limit -Reactor Core The Minimum DNBR of the reactor core shall be maintained greater than or equal to the DNB correlation safety limit. Applicability Correlation XNB ANFP HTP Safety Limit 1.17 1.154 1.141 Safety Limit 2.1 is applicable in HOT STANDBY and POWER OPERATION.
Action 2.1.1 If a Safety Limit is exceeded, comply with the requirements of Specification 6.7 2.2 Safety Limit -Primary Coolant System Pressure (PCS) The PCS Pressure shall not exceed 2750 psia. App 1 i cabil i ty Safety Limit 2.2 is applicable when there is fuel in the reactor. Action 2.2.1 If a Safety Limit is exceeded, comply with the requirements of Specification 6.7 2.3 Limiting Safety System Settings -Reactor Protective System (RPS) The RPS trip setting limits shall be as stated in Table 2.3.1. Applicability Limiting Safety System Settings of Table 2.3.1 are applicable when the associated RPS channels are required to be OPERABLE by Specification 3.17.1. Action 2.3.1 If an RPS instrument setting is not within the allowable settings of Table 2.3.1, immediately declare the instrument inoperable and complete corrective action as directed by Specification 3.17.1. Amendment No. 3-!, S, 43-, -l+S, -l-3-7, W, 2-1 -2.0 BASIS -Safety and Limiting Safety System 2.1 Basis -Reactor Core Safety limit To maintain the integrity of the fuel cladding and prevent fission product release, it is necessary to prevent overheating of the cladding under normal operating conditions.
This is accomplished by operating within the nucleate boiling regime of heat transfer, wherein the heat transfer coefficient is large enough so that the clad surface temperature is only slightly greater than the coolant temperature.
The upper boundary of the nucleate boiling regime is termed "departure from nucleate boiling" (DNB). At this point, there is a sharp reduction of the heat transfer coefficient, which would result in high-cladding temperatures and the possibility of cladding failure. Although DNB is not an observable parameter during reactor operation, the observable parameters of thermal power, primary coolant flow, temperature and pressure, can be related to DNB through the use of a DNB Correlation.
DNB Correlations have been developed to predict DNB and the location of DNB for axially uniform and nonuniform heat flux distributions.
The local DNB ratio (DNBR), defined as the ratio of the heat flux that would cause DNB at a particular core location to the actual heat flux, is indicative of the margin to DNB. The minimum value of the DNBR, during steady-state operation, normal operational transients, and anticipated transients is limited to DNB correlation safety limit. A DNBR equal to the DNB correlation safety limit corresponds to a 95% probability at a 95% confidence level that DNB will not occur which is considered an appropriate margin to DNB for all operating conditions.
The reactor protective system is designed to prevent any anticipated combination of transient conditions for primary coolant system temperature, pressure and thermal power level that would result in a DNBR of less than the DNB correlation safety limit. The Palisades safety analyses uses three DNB correlations.
The XNB correlation discussed in References 1 and 2 determines the safety limit for those fuel assemblies initially loaded prior to Cycle 9. Fuel assemblies, initially loaded in cycle 9 and later, utilize a high thermal performance (HTP) design which is different than the fuel design used for cycle 8 and earlier reloads. The ANFP correlation discussed in References 4 and 5 and the HTP correlation discussed in Reference 7 determine the safety limit for those fuel assemblies initially loaded in cycle 9 and later. The ANFP correlation was developed for the HTP fuel design; the HTP correlation is an extension of the ANFP correlation and reflects the results of additional DNB testing of HTP fuel. The HTP correlation is restricted to the operating conditions specified in Reference 7, outside of which. the ANFP correlation is used. In the presence of a mixed core consisting of both HTP and non-HTP fuel assemblies, situated such that the non-HTP fuel assemblies affect the flow distribution, the minimum DNBR analyses are in accordance with Reference
- 6. References (1) XN-NF-62l(P)(A), Rev 1 (2) XN-NF-709 (3) Updated FSAR, Section 14.1. (4) ANF-1224 (P)(A), May 1989 (5) ANF-89-192(P), January 1990 (6) XN-NF-82-2l(A), Revision 1 _____ (7)_
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_ Amendment No. 1-, -H-8, 7-, tw, B 2-1 ATTACHMENT 2 Consumers Power Company Palisades Plant Docket 50-255
- PROPOSED HTP CORRELATION TECHNICAL SPECIFICATIONS EXISTING PAGES WITH PROPOSED CHANGES MARKED ------------2--pag-es--
2:0 SAFETY LIMITING SAFETY SYSTEM 2.1 Safety Limit -Reactor Core The Minimum DNBR of the reactor core shall be maintained greater than or equal to the DNB correlation safety limit. Correlation Safety Limit XNB 1.17 Applicability Safety Limit 2.1 is applicable in HOT STANDBY and POWER OPERATION.
Action 2.1.1 If a Safety Limit is exceeded, comply with the requirements of Specification 6.7 2.2 Safety Limit -Primary Coolant System Pressure (PCS) The PCS Pressure shall not exceed 2750 psia. Applicability Safety Limit 2.2 is applicable when there is fuel in the reactor. Action 2.2.1 If a Safety Limit is exceeded, comply with the requirements of Specification 6.7 2.3 Limiting Safety System Settings -Reactor Protective System (RPS) The RPS trip setting limits shall be as stated in Table 2.3.1. Applicability Limiting Safety System Settings of Table 2.3.l are applicable when the associated RPS channels are required to be OPERABLE by Specification 3.17.1. Action 2.3.l If an RPS instrument setting is not within the allowable settings of Table 2.3.1, immediately declare the instrument inoperable and complete corrective action as directed by Specification 3.17.1. Amendment No-. '/JJ,
_J.'/Jl, _.f-W _ July 15, 1992 2-1 2.0 2.1 BASIS -
and Limiting Safety Reactor Core Safety limit T.o*maintain the inte9rity of the fuel cladding and prevent fission _ product release, it is necessary to Qrevent overheating of the cladding under normal operating conditions.
This is accomplished by operating within the nucleate boiling regime of heat transfer, wherein the heat transfer coefficient is large enough so that the clad surface temperature is only slightly greater than the coolant temperature.
The upper boundary of the nucleate boiling regime is termed "aeparture from nucleate boiling" (DNB). At this point, there is a sharp reduction of the heat transfer coefficient, which would result in high-cladding temperatures and the possibility of cladding failure. Although DNB is not an observable parameter during reactor operation, the observable parameters of thermal power, primary coolant flow, temperature and g ressure, can be related to DNB through the use of a DNB Correlation.
NB Correlations have been developed to predict DNB and the location of DNB for axially uniform and nonuniform heat flux distributions.
The local DNB ratio (DNBR)i defined as the ratio of the heat flux that would cause DNB at a particu ar core location to the actual heat flux, is indicative of the margin to DNB. The minimum value of the DNBR, during steady-state operation, normal operational transients, and anticipated transients is limited to DNB correlation safety limit. A DNBR equal to the DNB correlation safety limit corresponds to a 95% probability at a 95% confidence level that DNB will not occur which is considered an appropriate margin to DNB for all operating conditions.
The reactor protective system is designed to prevent any anticipated combination of transient conditions for primary coolant system temperature, pressure and thermal power level that would result in a DNBR of less than the DNB ...... c.o.r.relation safety limit. The Palisades safety analyses uses twe t.:b.Jtel DNB correlations.
The XNB correlation discussed in References l"""arfcf"""2 determines the safety limit for those fuel assemblies initially loaded prior to Cycle 9. The ANFP correlatioR discussed iR RefereRces 4 aRd S determiRes the safety limit for those fuel assemblies iRitially loaded iR Cycle 9 aRd later. Fuel assemblies iRitially loaded prior to Cycle 9 are of a differeRt coRstructioR thaR The miRimum DNBR aRalyses are iR accordaRce with RefereRce
- 6. References XN-NF-62l(P)(A), Rev 1 2 XN-NF-709 3 Updated FSAR, Section 14.1. 4 ANF-1224 (P)(A), May 1989 5 ANF-89-192f PA January 1990 Amendment No. 3-1-, 43-, H-8, 3-7, §G, §.e, Jw=ie 16, 1993 B 2-1