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| | issue date = 11/24/1980 | | | issue date = 11/24/1980 |
| | title = Application for Tech Spec Changes to License DPR-20 Re Containment Spray Initiation Time | | | title = Application for Tech Spec Changes to License DPR-20 Re Containment Spray Initiation Time |
| | author name = DEWITT R B | | | author name = Dewitt R |
| | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), | | | author affiliation = CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.), |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:*' CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 1 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power ,Company on October 16, 1972, for the Palisades Plant be as described in s*ection I below: I. Changes A. Revise Section 3.4.1 to read as follows: "3.4.1 The primary coolant system shall not be heated above 325°F unless the following conditions are met:" B. Add the following to Section 3.4.1: c. D. "3. 4 .1. d Both containment spray headers are filled to a level greater than th'e 735-foot elevation." Delete* the following from the Basis of Section 3.4.1: "The containment spray system is redundant with the containment air circulation and cooling *system. (1) It is sized such that two of the three pumps will limit containment pressure to less than design pressure following a DBA without taking credit for the safety injection tanks. (2) Three of the four air coolers have the capability of limiting the containment pressure under the same conditions as the two Pll;lIIPS. | | {{#Wiki_filter:1 CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power ,Company on October 16, 1972, for the Palisades Plant be chang~d as described in s*ection I below: |
| 11 Add the following paragraph to the Basis of Section 3.4.1: "An.MSLB or LOCA produces a rapid pressurization of containment immediately following the break. Operation with the spray header filled to the 735-foot elevation minimizes the time prior to establishment of fully developed spray flow. Inoperability of one of the headers is permitted for a 7-day period since the other header remains* operable,. | | I. Changes A. Revise Section 3.4.1 to read as follows: |
| and heat removal capability is still provided by the containment air coolers. Spray flow is established in the zero power case, :with both spray headers drained, early enough to prevent containment pressure from exceeding the design limit." E. Revise Section 3.6.2 to .read as follows: "3.6.2 The internal pressure shall not exceed 1.0 psig (except for containment leak rate tests)." nu0880-0446a-43 | | "3.4.1 The primary coolant system shall not be heated above 325°F unless the following conditions are met:" |
| * 8 0 12 O I O:J..f-r | | B. Add the following to Section 3.4.1: |
| -, F. Revise Item 1 of Table 3.16.1 to read as follows: Functional Unit Channel Setting Limit 1 . High Co.ntainment Pressure a. Safety Injection. 5 -5.75 Psig b. Containment Spray c. Containment Isolation
| | "3. 4 .1. d Both containment spray headers are filled to a level greater than th'e 735-foot elevation." |
| : d. Containment Air Cooler DBA Mode Steam Line Isolation G. Revise Item 4 of Table 3.16.1 to read as follows: Functional Unit Low Steam Generator Pressure Channel Steam Line Isolation Feed Line Isolation H. Add Item 15 to Table 4.1.3: Setting Limit 500 Psia(3) 2 15. Containment Spray Header Level a. Check w R a. Normal Readings Observed 1 b. Calibrate II. Discussion | | : c. Delete* the following from the Basis of Section 3.4.1: |
| : b. Known Pressure Applied to Sensor A. This change will require the equipment identified in Sections 3.4.1.a, band c to be available prior to criticality.
| | "The containment spray system is redundant with the containment air circulation and cooling *system. (1) It is sized such that two of the three pumps will limit containment pressure to less than design pressure following a DBA without taking credit for the safety injection tanks. (2) Three of the four air coolers have the |
| This will add a margin of safety to the Plant since this safety equipment will be available in the event of a zero power steam line break. B. This proposed Technical Specifications change results from actions identified in the to LER 80-003 (Containment Spray). By filling both containment spray (CTS) headers to a level greater than the 735-foot elevation, the actuation time of CTS system, during an MSLB or LOCA, is reduced. A faster response by the CTS system results in a lower containment pressure during an MSLB or LOCA. C .. This paragraph in the Basis Section 3.4.1 can be deleted. It is no longer applicable to the Palisades Plant. D. The proposed paragraph to the Basis Section 3.4.1 is explanatory. | | *' capability of limiting the containment pressure under the same conditions as the two Pll;lIIPS. 11 D. Add the following paragraph to the Basis of Section 3.4.1: |
| E. The proposed change for Section 3.6.2 changes the internal containment pressure limit, during operation, from 3 psig to 1 psig. Analysis shows if the initial containment pressure is greater than 1 psig that, in the event of a LOCA o.r MSLB, the containment pressure design will be exceeded. | | "An.MSLB or LOCA produces a rapid pressurization of containment immediately following the break. Operation with the spray header filled to the 735-foot elevation minimizes the time prior to establishment of fully developed spray flow. Inoperability of one of the headers is permitted for a 7-day period since the other header remains* operable,. and heat removal capability is still provided by the containment air coolers. Spray flow is established in the zero power case, :with both spray headers drained, early enough to prevent containment pressure from exceeding the design limit." |
| From an operational standpoint, 1 psig is achievable. | | E. Revise Section 3.6.2 to .read as follows: |
| nu0880-0446a-43 | | "3.6.2 The internal pressure shall not exceed 1.0 psig (except for containment leak rate tests)." |
| ........ l | | nu0880-0446a-43 |
| | *8 0 12 O I O:J..f-r |
| | |
| | *~ |
| | 2 F. Revise Item 1 of Table 3.16.1 to read as follows: |
| | Functional Unit Channel Setting Limit |
| | : 1. High Co.ntainment a. Safety Injection. 5 - 5.75 Psig Pressure b. Containment Spray |
| | : c. Containment Isolation |
| | : d. Containment Air Cooler DBA Mode e~ Steam Line Isolation G. Revise Item 4 of Table 3.16.1 to read as follows: |
| | Functional Unit Channel Setting Limit Low Steam Generator Steam Line Isolation ~ 500 Psia(3) |
| | Pressure Feed Line Isolation H. Add Item 15 to Table 4.1.3: |
| | : 15. Containment Spray a. Check w a. Normal Readings Observed1 Header Level b. Calibrate R b. Known Pressure Applied to Sensor II. Discussion A. This change will require the equipment identified in Sections 3.4.1.a, band c to be available prior to criticality. This will add a margin of safety to the Plant since this safety equipment will be available in the event of a zero power steam line break. |
| | B. This proposed Technical Specifications change results from actions identified in the follow~up to LER 80-003 (Containment Spray). By filling both containment spray (CTS) headers to a level greater than the 735-foot elevation, the actuation time of CTS system, during an MSLB or LOCA, is reduced. A faster response by the CTS system results in a lower containment pressure during an MSLB or LOCA. |
| | C. . This paragraph in the Basis Section 3.4.1 can be deleted. It is no longer applicable to the Palisades Plant. |
| | D. The proposed paragraph to the Basis Section 3.4.1 is self-explanatory. |
| | E. The proposed change for Section 3.6.2 changes the internal containment pressure limit, during operation, from 3 psig to 1 psig. |
| | Analysis shows if the initial containment pressure is greater than 1 psig that, in the event of a LOCA o.r MSLB, the containment pressure design will be exceeded. From an operational standpoint, ~ 1 psig is achievable. |
| | nu0880-0446a-43 |
| | ........ l |
| | * 3 F. The addition of steam line isolation to Table 3.16.1, Item 1, is a result of the analysis performed in conjunction with LER 80-003. |
| | The purpose of this change is to reduce the mass and energy added to containment in the event of a main steam line break incident. |
| | G. The addition of the feedwater line to Table 3.16.1, Item 4, is a result of a modification made in conjunction with LER 80-003. The purpose of this modification is to provide feedwater isolation when steam generator pressure falls below 500 psia. |
| | D H. These changes are needed ~o provide continuity with the proposed Technical Specifications changes (Item B above) that have resulted from LER 80-003 (Containment Spray initiation times). |
| | III. Conclusion Based on the foregoing, both the Palisades Plant Review Committee and the Safety and Audit Review Board have reviewed these changes and find them acceptable. |
| | CONSUMERS POWER COMPANY Bya~&lltl~tt Nuclear Operations Sworn and subscribed to before me this 24th day of November 1980. |
| | Linda K_Carstens, Notary Public Jackson County, Michigan |
| | *My commission expires June 10, 1981. |
| ** ,,r*.) | | ** ,,r*.) |
| * F. The addition of steam line isolation to Table 3.16.1, Item 1, is a result of the analysis performed in conjunction with LER 80-003. 3 The purpose of this change is to reduce the mass and energy added to containment in the event of a main steam line break incident.
| | . . :.,.J,.:,,.J |
| G. The addition of the feedwater line to Table 3.16.1, Item 4, is a result of a modification made in conjunction with LER 80-003. The purpose of this modification is to provide feedwater isolation when steam generator pressure falls below 500 psia. D H. These changes are needed provide continuity with the proposed Technical Specifications changes (Item B above) that have resulted from LER 80-003 (Containment Spray initiation times). III. Conclusion Based on the foregoing, both the Palisades Plant Review Committee and the Safety and Audit Review Board have reviewed these changes and find them acceptable.
| | . J ( L |
| CONSUMERS POWER COMPANY Nuclear Operations Sworn and subscribed to before me this 24th day of November 1980. Linda K_Carstens, Notary Public Jackson County, Michigan *My commission expires June 10, 1981. -,., .... :.,.J,.:,,.J . J ( L ,ft '* ' ' ..... nu0880-0446a-43}}
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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
[Table view] |
Text
1 CONSUMERS POWER COMPANY Docket 50-255 Request for Change to the Technical Specifications License DPR-20 For the reasons hereinafter set forth, it is requested that the Technical Specifications contained in the Provisional Operating License DPR-20, Docket 50-255, issued to Consumers Power ,Company on October 16, 1972, for the Palisades Plant be chang~d as described in s*ection I below:
I. Changes A. Revise Section 3.4.1 to read as follows:
"3.4.1 The primary coolant system shall not be heated above 325°F unless the following conditions are met:"
B. Add the following to Section 3.4.1:
"3. 4 .1. d Both containment spray headers are filled to a level greater than th'e 735-foot elevation."
- c. Delete* the following from the Basis of Section 3.4.1:
"The containment spray system is redundant with the containment air circulation and cooling *system. (1) It is sized such that two of the three pumps will limit containment pressure to less than design pressure following a DBA without taking credit for the safety injection tanks. (2) Three of the four air coolers have the
- ' capability of limiting the containment pressure under the same conditions as the two Pll;lIIPS. 11 D. Add the following paragraph to the Basis of Section 3.4.1:
"An.MSLB or LOCA produces a rapid pressurization of containment immediately following the break. Operation with the spray header filled to the 735-foot elevation minimizes the time prior to establishment of fully developed spray flow. Inoperability of one of the headers is permitted for a 7-day period since the other header remains* operable,. and heat removal capability is still provided by the containment air coolers. Spray flow is established in the zero power case, :with both spray headers drained, early enough to prevent containment pressure from exceeding the design limit."
E. Revise Section 3.6.2 to .read as follows:
"3.6.2 The internal pressure shall not exceed 1.0 psig (except for containment leak rate tests)."
nu0880-0446a-43
2 F. Revise Item 1 of Table 3.16.1 to read as follows:
Functional Unit Channel Setting Limit
- 1. High Co.ntainment a. Safety Injection. 5 - 5.75 Psig Pressure b. Containment Spray
- c. Containment Isolation
- d. Containment Air Cooler DBA Mode e~ Steam Line Isolation G. Revise Item 4 of Table 3.16.1 to read as follows:
Functional Unit Channel Setting Limit Low Steam Generator Steam Line Isolation ~ 500 Psia(3)
Pressure Feed Line Isolation H. Add Item 15 to Table 4.1.3:
- 15. Containment Spray a. Check w a. Normal Readings Observed1 Header Level b. Calibrate R b. Known Pressure Applied to Sensor II. Discussion A. This change will require the equipment identified in Sections 3.4.1.a, band c to be available prior to criticality. This will add a margin of safety to the Plant since this safety equipment will be available in the event of a zero power steam line break.
B. This proposed Technical Specifications change results from actions identified in the follow~up to LER 80-003 (Containment Spray). By filling both containment spray (CTS) headers to a level greater than the 735-foot elevation, the actuation time of CTS system, during an MSLB or LOCA, is reduced. A faster response by the CTS system results in a lower containment pressure during an MSLB or LOCA.
C. . This paragraph in the Basis Section 3.4.1 can be deleted. It is no longer applicable to the Palisades Plant.
D. The proposed paragraph to the Basis Section 3.4.1 is self-explanatory.
E. The proposed change for Section 3.6.2 changes the internal containment pressure limit, during operation, from 3 psig to 1 psig.
Analysis shows if the initial containment pressure is greater than 1 psig that, in the event of a LOCA o.r MSLB, the containment pressure design will be exceeded. From an operational standpoint, ~ 1 psig is achievable.
nu0880-0446a-43
........ l
- 3 F. The addition of steam line isolation to Table 3.16.1, Item 1, is a result of the analysis performed in conjunction with LER 80-003.
The purpose of this change is to reduce the mass and energy added to containment in the event of a main steam line break incident.
G. The addition of the feedwater line to Table 3.16.1, Item 4, is a result of a modification made in conjunction with LER 80-003. The purpose of this modification is to provide feedwater isolation when steam generator pressure falls below 500 psia.
D H. These changes are needed ~o provide continuity with the proposed Technical Specifications changes (Item B above) that have resulted from LER 80-003 (Containment Spray initiation times).
III. Conclusion Based on the foregoing, both the Palisades Plant Review Committee and the Safety and Audit Review Board have reviewed these changes and find them acceptable.
CONSUMERS POWER COMPANY Bya~&lltl~tt Nuclear Operations Sworn and subscribed to before me this 24th day of November 1980.
Linda K_Carstens, Notary Public Jackson County, Michigan
- My commission expires June 10, 1981.
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