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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20137L1041997-04-0303 April 1997 Requests Termination of Facility Operating License DPR-34, Per 10CRF50.82(a)(9) ML20134K4591996-11-0707 November 1996 Requests That NRC Terminate Facility Operating License for Plant,Per 10CFR50.82(a) ML20082K2271995-04-14014 April 1995 Application for Amend to License DPR-34,revising Decommissioning TS to Reflect Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3251993-05-18018 May 1993 Application for Amend to License DPR-34,changing TS to Impose More Restrictive Leak Test Acceptance Criteria for Reactor Bldg Ventilation Sys HEPA Filters to Permit Use of Graphite Handling Alternatives to Minimize Exposures ML20118B2121992-09-25025 September 1992 Supplemental Application for Amend to License DPR-34, Changing Decommissioning TS to Clarify & to More Accurately Reflect Decommissioning Conditions ML20096H1881992-05-19019 May 1992 Suppl to 920319 Application for Amend to License DPR-34, Requesting Early Consideration of Decommissioning TS Provision That Deletes Current Limitations on Temp of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys ML20094L2781992-03-19019 March 1992 Application for Amend to License DPR-34,revising TS to Provide Controls & Limits Appropriate for Decommissioning ML20086T1181991-12-24024 December 1991 Application for Amend to License DPR-34,changing TS to Revise Mgt Titles to Reflect Reorganization in Jan 1992, Deleting Programs No Longer Necessary After Nuclear Fuel Removed & Deleting Requirements for Technical Advisors ML20086C5271991-11-15015 November 1991 Supplement to 911011 Application for Amend to License DPR-34 Changing Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps to Correct Page Numbering ML20091D7591991-10-11011 October 1991 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.2.15 to Permit Operation of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys at Somewhat Lower Temps than Currently Specified ML20082L9281991-08-30030 August 1991 Application for Amend to License NPF-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning ML20066A3741990-12-21021 December 1990 Application for Amend to License DPR-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning,Per Generic Ltr 89-01 ML20059L5871990-09-14014 September 1990 Application for Amend to License DPR-34,changing Tech Spec Design Feature Section 6.1,by Removing CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20055G7091990-07-20020 July 1990 Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20043F7461990-06-0606 June 1990 Application for Amend to License DPR-34,revising Physical Security Plan to Reflect Permanent Shutdown of Facility & Plant Conditions During Defueling.Encls Withheld (Ref 10CFR73.21) ML20042F3141990-04-26026 April 1990 Application for Amend to License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20006B7841990-01-25025 January 1990 Application for Amend to License DPR-34,adding Nuclear Training & Support Manager to Nfsc Membership ML19332E8831989-12-0404 December 1989 Application for Amend to License DPR-34,supplementing Proposed Tech Spec Re Reactivity Control ML19332F3531989-12-0404 December 1989 Supplemental Application for Amend to License DPR-34, Changing Tech Spec Sections 4.7 & 5.7, Fuel Handling & Storage. ML20006C5141989-11-21021 November 1989 Application for Amend to License DPR-34,restricting Reactor Operation at Any Power Level & Deleting Paragraph 2.D.(4) Which Authorizes Operation Above 2% Power After 900630 ML19351A3261989-10-13013 October 1989 Application for Amend to License DPR-34,revising Tech Spec 6.1 Re Defueling Phase Document Design Features ML19327B1311989-10-13013 October 1989 Application for Amend to License DPR-34,deleting Limiting Conditions for Operation 4.12 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding New Reactivity Control Section to Supersede Interim Tech Specs ML20248G3191989-10-0101 October 1989 Application for Amend to License DPR-34,modifying License Condition to Include Statement That Facility Will Not Be Oeprated for Electric Power Production After 890818 ML20248G4431989-09-30030 September 1989 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.4.7 & 4.4.8 & Surveillance Requirements 5.4.14 & 5.4.15 Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7761989-09-14014 September 1989 Application for Amend to License DPR-34,to Document Design Features for Defueling Phase of Operation ML20247L0771989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Limiting Condition for Operation 4.1.2 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding Reactivity Section ML20247J2231989-09-14014 September 1989 Application for Amend to License DPR-34,incorporating Tech Spec Upgrade Program Including Requirements for Fuel Handling Machine Operation & Fuel Storage at Facility ML20247G7201989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Fire Protection Limiting Condition for Operation & Surveillance Requirements from Tech Specs ML20246L0161989-07-14014 July 1989 Application for Amend to License DPR-34,rewording Basis for Limiting Condition for Operation 4.2.2 Re Operation of Plant Backup Bearing Water Sys from Requiring Automatic Operation to Permitting Either Automatic or Manual Operation ML20246K9841989-07-14014 July 1989 Application for Amend to License DPR-34,changing Tech Specs to Document Improvements to Battery Surveillance Procedures ML20244B3671989-06-0909 June 1989 Application for Amend to License DPR-34,adding License Condition Re Early Shutdown of Plant ML20245B3181989-04-14014 April 1989 Application for Amend to License DPR-34,extending for 90 days,4 H Check of Radiation Monitors Having Only Local Alarms to Permit Repair of out-of-svc Monitors W/O Reverting to Grab Sample Mode ML20155J6231988-10-14014 October 1988 Application for Amend to License DPR-34,revising Administrative Controls Section of Tech Specs ML20155J6051988-10-14014 October 1988 Application for Amend to License DPR-34,revising Tech Specs SR 5.0 & SR 5.2.1 Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E7931988-10-13013 October 1988 Application for Amend to License DPR-34,revising Tech Specs to Clarify Time Allowed to Ensure Proper Trip Setpoints for Linear Channel - High Neutron Flux Channels Following Power Reduction ML20155G1821988-09-23023 September 1988 Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purposes of Sampler Analysis or Instrument Calibr ML20207E1561988-08-0505 August 1988 Application for Amend to License DPR-34 ML20151S2411988-04-20020 April 1988 Application for Amend to License DPR-34,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery & Associated Battery Charger Disconnected from Dc Bus ML20151R8141988-04-20020 April 1988 Application for Amend to License DPR-34,deleting 10CFR51.5(b)2 ML20149M2851988-02-0808 February 1988 Application for Amend to License DPR-34,revising Tech Specs Re Plant Protective Sys Trip Setpoints & Operating Requirements ML20149N0371988-02-0505 February 1988 Application for Amend to License DPR-34,changing Administrative Controls to Reflect Organizational Changes ML20238C3431987-12-23023 December 1987 Application for Amend to License DPR-34,revising Tech Specs Re safety-related Cooling Sys,Per 871202-03 meetings.W/re- Drafted Tech Specs & Discussions of NRC Comments from Aug 1987 & 871202-03 Meetings ML20236C6271987-10-15015 October 1987 Application for Amend to License DPR-34,deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements from Tech Specs ML20235W8521987-10-0101 October 1987 Application for Amend to License DPR-34,revising Tech Spec Sections Elco 8.1.1 to Clarify Actions on Inoperble Halogen Monitors & ESR 8.1.1 & 8.1.2 to Clarify Conditions Re Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20216H7221987-06-25025 June 1987 Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Associated Requirements ML20210B6831987-04-23023 April 1987 Application for Amend to License DPR-34,changing Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys.Fee Paid ML20206P3811987-04-0808 April 1987 Application for Amend to License DPR-34,revising Interim Tech Spec 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserved Shutdown Sys,Per Rev 4 to FSAR ML20207Q5381987-01-21021 January 1987 Application to Amend License DPR-34,changing Tech Specs for Limiting Condition for Operation 4.6.1, Auxiliary Electric Sys, to Bring Consistency to Electrical Sys Nomenclature. Fee Paid ML20207P9891987-01-15015 January 1987 Application for Amend to License DPR-34,requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of Operable HXs ML20207D1891986-12-23023 December 1986 Application for Amend to License DPR-34,revising Tech Specs to Delete Snubber Tables & Correct Typos 1997-04-03
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20141K9941997-05-0505 May 1997 Amend 89 to License DPR-34,designating All Elements of Approved Decommissioning Plan as License Termination Plan ML20137L1041997-04-0303 April 1997 Requests Termination of Facility Operating License DPR-34, Per 10CRF50.82(a)(9) ML20134K4591996-11-0707 November 1996 Requests That NRC Terminate Facility Operating License for Plant,Per 10CFR50.82(a) ML20082K2271995-04-14014 April 1995 Application for Amend to License DPR-34,revising Decommissioning TS to Reflect Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3251993-05-18018 May 1993 Application for Amend to License DPR-34,changing TS to Impose More Restrictive Leak Test Acceptance Criteria for Reactor Bldg Ventilation Sys HEPA Filters to Permit Use of Graphite Handling Alternatives to Minimize Exposures ML20118B2121992-09-25025 September 1992 Supplemental Application for Amend to License DPR-34, Changing Decommissioning TS to Clarify & to More Accurately Reflect Decommissioning Conditions ML20096H1881992-05-19019 May 1992 Suppl to 920319 Application for Amend to License DPR-34, Requesting Early Consideration of Decommissioning TS Provision That Deletes Current Limitations on Temp of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys ML20094L2781992-03-19019 March 1992 Application for Amend to License DPR-34,revising TS to Provide Controls & Limits Appropriate for Decommissioning ML20086T1181991-12-24024 December 1991 Application for Amend to License DPR-34,changing TS to Revise Mgt Titles to Reflect Reorganization in Jan 1992, Deleting Programs No Longer Necessary After Nuclear Fuel Removed & Deleting Requirements for Technical Advisors ML20086C5271991-11-15015 November 1991 Supplement to 911011 Application for Amend to License DPR-34 Changing Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps to Correct Page Numbering ML20091D7591991-10-11011 October 1991 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.2.15 to Permit Operation of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys at Somewhat Lower Temps than Currently Specified ML20082L9281991-08-30030 August 1991 Application for Amend to License NPF-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning ML20066A3741990-12-21021 December 1990 Application for Amend to License DPR-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning,Per Generic Ltr 89-01 ML20059L5871990-09-14014 September 1990 Application for Amend to License DPR-34,changing Tech Spec Design Feature Section 6.1,by Removing CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20055G7091990-07-20020 July 1990 Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20043F7461990-06-0606 June 1990 Application for Amend to License DPR-34,revising Physical Security Plan to Reflect Permanent Shutdown of Facility & Plant Conditions During Defueling.Encls Withheld (Ref 10CFR73.21) ML20042F3141990-04-26026 April 1990 Application for Amend to License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20006B7841990-01-25025 January 1990 Application for Amend to License DPR-34,adding Nuclear Training & Support Manager to Nfsc Membership ML19332E8831989-12-0404 December 1989 Application for Amend to License DPR-34,supplementing Proposed Tech Spec Re Reactivity Control ML19332F3531989-12-0404 December 1989 Supplemental Application for Amend to License DPR-34, Changing Tech Spec Sections 4.7 & 5.7, Fuel Handling & Storage. ML20006C5141989-11-21021 November 1989 Application for Amend to License DPR-34,restricting Reactor Operation at Any Power Level & Deleting Paragraph 2.D.(4) Which Authorizes Operation Above 2% Power After 900630 ML19327B1311989-10-13013 October 1989 Application for Amend to License DPR-34,deleting Limiting Conditions for Operation 4.12 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding New Reactivity Control Section to Supersede Interim Tech Specs ML19351A3261989-10-13013 October 1989 Application for Amend to License DPR-34,revising Tech Spec 6.1 Re Defueling Phase Document Design Features ML20248G3191989-10-0101 October 1989 Application for Amend to License DPR-34,modifying License Condition to Include Statement That Facility Will Not Be Oeprated for Electric Power Production After 890818 ML20248G4431989-09-30030 September 1989 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.4.7 & 4.4.8 & Surveillance Requirements 5.4.14 & 5.4.15 Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7761989-09-14014 September 1989 Application for Amend to License DPR-34,to Document Design Features for Defueling Phase of Operation ML20247G7201989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Fire Protection Limiting Condition for Operation & Surveillance Requirements from Tech Specs ML20247L0771989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Limiting Condition for Operation 4.1.2 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding Reactivity Section ML20247J2231989-09-14014 September 1989 Application for Amend to License DPR-34,incorporating Tech Spec Upgrade Program Including Requirements for Fuel Handling Machine Operation & Fuel Storage at Facility ML20246J3091989-08-30030 August 1989 Amend 72 to License DPR-34,imposing Early Shutdown on Plant by Limiting Reactor Power to 2% of Full Power After 900630 ML20245J3671989-08-14014 August 1989 Amend 71 to License DPR-34,revising Provisions in Tech Specs Re Radiological Effluents ML20246K9841989-07-14014 July 1989 Application for Amend to License DPR-34,changing Tech Specs to Document Improvements to Battery Surveillance Procedures ML20246L0161989-07-14014 July 1989 Application for Amend to License DPR-34,rewording Basis for Limiting Condition for Operation 4.2.2 Re Operation of Plant Backup Bearing Water Sys from Requiring Automatic Operation to Permitting Either Automatic or Manual Operation ML20244B3671989-06-0909 June 1989 Application for Amend to License DPR-34,adding License Condition Re Early Shutdown of Plant ML20245C4991989-04-18018 April 1989 Amend 70 to License DPR-34,changing Amount of Radioactive Matl to Be Possessed for Analysis & Instrument Calibr ML20245B3181989-04-14014 April 1989 Application for Amend to License DPR-34,extending for 90 days,4 H Check of Radiation Monitors Having Only Local Alarms to Permit Repair of out-of-svc Monitors W/O Reverting to Grab Sample Mode ML20248D6461989-03-31031 March 1989 Amend 69 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20236A1351989-02-27027 February 1989 Amend 68 to License DPR-34,modifying Limiting Condition for Operation 4.4.1 & Surveillance Requirement 5.4.1 to Include Fixed High Temp Trip Setpoint for Steam Line Rupture & Detection Sys ML20205F9781988-10-24024 October 1988 Amend 65 to License DPR-34,amending Tech Specs Paragraph 2.D(3) to Require Compliance W/Amended Physical Security Plan & to Conform to 10CFR73.55 Requirements ML20155J6051988-10-14014 October 1988 Application for Amend to License DPR-34,revising Tech Specs SR 5.0 & SR 5.2.1 Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20155J6231988-10-14014 October 1988 Application for Amend to License DPR-34,revising Administrative Controls Section of Tech Specs ML20204E7931988-10-13013 October 1988 Application for Amend to License DPR-34,revising Tech Specs to Clarify Time Allowed to Ensure Proper Trip Setpoints for Linear Channel - High Neutron Flux Channels Following Power Reduction ML20155G1821988-09-23023 September 1988 Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purposes of Sampler Analysis or Instrument Calibr ML20154J4561988-09-15015 September 1988 Amend 63 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20154J7931988-09-15015 September 1988 Amend 64 to License DPR-34,changing Tech Specs for Plant DC Power Sys & Allowing for Future Changes to Station Batteries ML20207E1561988-08-0505 August 1988 Application for Amend to License DPR-34 ML20207F2141988-08-0505 August 1988 Amend 62 to License DPR-34,deleting Ref in App B of Tech Specs to 10CFR51.5(b)2 ML20207F0061988-08-0505 August 1988 Amend 61 to License DPR-34,deleting Requirement to Monitor Temp of Dew Point Moisture Monitors in Section 4.4 ML20151A9921988-06-20020 June 1988 Amend 60 to License DPR-34,revising Certain Setpoints for Protective Sys to Allow for Instrumentation Error ML20151S2411988-04-20020 April 1988 Application for Amend to License DPR-34,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery & Associated Battery Charger Disconnected from Dc Bus 1997-05-05
[Table view] |
Text
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h Public Service' P.O. Box 840 Denver CO 80201- 0840 .l l
A. Clegg Crawford UuciehIpe*r"[tions July 14, 1989 Fort St. Vrain Unit No. 1 P-89264 U. 5. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.'C. 20555 ATTN: Mr. Fredrick J. Hebdon, Director Project Directorate IV Docket No. 50-267
SUBJECT:
Proposed Technical Specification Change-Emergency Power Systems
REFERENCES:
- 1) PSC letter, Brey to Calvo, dated May 27, 1988, (P-88184)
- 2) NRC letter, Heitner to Williams, dated April 19, 1989, (G-89145)
Dear Mr. Hebdon:
This is an amendment request to the Fort St. Vrain Technical Specifications to document improvements to Battery Surveillance Procedures. These improvements have been made in accordance with the Technical Specification Upgrade Program (TSUP), IEEE Standard 450-1987, battery vendor recommendations, Regulatory Guide 1.129, Revision 1, and Westinghouse Standard Technical Specifications.
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P-89264 . July 14, 1989' History:
PSC has- been in 'the process of preparing an. upgraded-Technical-Specification using . the Westinghouse : Standard Technical Specifications for guidance as submitted in P-88184, Reference 1. The .
NRC presented comments on the submittal -in G-89145,- Reference.c2.
These Technical . Specifications have been .further revised to accommodate the new Lead Antimony Batteries installed in late 1988.
The additional revisions-are described in Attachment 1.
The revisions-to'SR 5.6.2 add a surveillance'of the battery chargers that will. be ' performed on an eighteen month frequency :and a Performance Discharge Test that will be regularly performed on a 60 month frequency. The Service Discharge Test' currently required by SR.'
5.6.2 is. being revised -from a 12 month ~ frequency.to an;18~ month frequency in accordance with the Standard Technical Specifications.
The . Service Discharge Test on each. battery was ' performed . in late -
1988. The Performance Discharge Test.on each . battery will be performed in place of- the -Service Discharge Test in mid 1990.or sooner. IEEE-450 requires the Performance Discharge Test within 2 years of the installation of a new battery. The'mid 1990 s'chedule-will satisfy'this requirement. The' battery < charger surveillance will be '-performed during a plant shutdown at the first outage ofL one week duration or more fo116 wing the effective date of this amendment 'or
~
sooner.
'Three attachments are included with this proposed amendment:
Attachment 1 - Summary.of Proposed Changes Attachment 2 - Proposed Changes Attachment 3 - No Significant Hazards Consideration Analysis This submittal includes proposed revisions to SR 5.6.1 and SR 5.6.2 sections.
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.$ LP-89264$ -3 ' July la, 1989
- If you .have any. questions or comments . concerning. the enclosed -
infonnation please call Mr. M. H. Holmes at (303) '480-6960.
Very trul.y purs,-
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A. Clegg Crawford.
Vice President, t!uelear Operations I -- ACC/JMW/km.
Attachments cc: Regional Administrator, Region IV ATTN: . Mr. T. F. Westerman, Chief
- Projects Section B Mr.-Robert Farrell Senior Resident Inspector Fort St. Vrain Mr. Robert M.'Quillen.
Colorado Department of Health 1
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UNITED. STATES OF AMERICA NUCLEAR. REGULATORY COMMISSION In the Matter )
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Public Service Comoary of Colorado :) Docket No, 50-267
' Fort St. Vrain Unit No. 1 )
AFFIDAVIT A. Clegg Crawford, being'first duly sworn, deposes and says: That he is Vice President,; Nuclear Operations, of Public Service Comp 3ny of Colorado, -the: Licensee herein, that he has read the foregoing Application for Amendment to Apptndix A'of Facility Operating License and knows the' contents.therenf, and that the statements and matters set forth therein.are true and correct to the best of his knowledge,
-information and belief.
W A. Clegg~Crawforf W
Vice President, Nuclear Operaticas STATE OF (O{LnCdC )
)
COUNTY OF Sntdcite ) .
i Subscribe and sworn to before me, a Notary Public on this
\ Vb' day of T u (o g
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No~tary Public My commission expires Q lb , 193;L'
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BEFORELTHE:.
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.UNITEDSTATES'NUCLEARREGULATORYLCOMMISSION r
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'N .In the' Matter of the' Facility Operating License)
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~ PUBLIC:-SERVICE. COMPANY.-0F COLORADO )
' Application for Amendment to Appendix A of Facility Operating License License No. DPR-34 *
- OF THE PUBLIC SERVICE COMPANY OF COLORADO FOR.THE
' FORT ST. ' VRAIN NUCLEAR GENERATING STATION This-application:for Amendment to Appendix A'of
- Facility Operating License, Licensi No. DPR-34,
- is submitted for NRC review and approval.
Respectfully submitted, PUBLIC SERVICE COMPANY OF COLORADO.
By-A. Clegg Crawford Vice President, Nuclear Operations KELLY,.STANSFIELD & 0'DONNELL James.K. Tarpey Mark A. Davidson
'Public Service Company Building Denver, Colorado 80202 Attorneys for Applicant zw---
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.F ATTACHMENT 1 To P-89264
SUMMARY
OF PROPOSED CHANGES
_ - _ _ _ _ _ . _ _ _ _ . _ ___________u_ s
P-89264 Attachment 1 Page 1 of 2 Section Description of Change SR 5.6.1 Incorporate nomenclature changes for Standby and Basis Diesel Generator set (s).
SR 5.6.2 Repipce entire SR with new surveillance requirements and Basis for the three Batteries, IA, 18, and 1C based on Westinghouse Standard Technical Specifications, IEEE Standard 450-1987, Re3ulatory. Guide 1.129, TSUP, and vendor recommendations.
SR 5.6e2.a.2 Battery voltage on float charge has been revised from the TSUP-va'oe of 120.4 volts total to 2.15 volts
~
per cell to account for the size of Batteries IA and IB possibly varying between 58 and 60 cells. The value of 2.15 volts per cell is based on vendor recommendations.
SR 5.6.2.b Batte ry overcharge voltage criteria has been revised from TSUP value of 150 volts to 145 volts since the battery chsrgers are not capable of exceeding 145 volts.
SR 5.6.2.b.3 The . average electrolyte temperature of at least 20% of the cells for Station Batteries 1A and IB has been revised from a TSUP value of above 60 degrees F to above 70 degrees to accommodate the recent load profile analysis as documented in EE-92-0012, dated October 28, 1988 and EE-92-0013, dated November 4, 1988.
SR 5.6.2.c.4.c ihe required current for Battery Charger ID has been revised from a TSUP vilue of 310 amperes to 345 amperes since Charosr ID current limiter is set at 345 amperes SR 5.6.2.e.1 The performance discharge parameters for Batteries 1A and IB have been revised from the TSUP values.
The average discharge rate has been changed from 310 smperes to 340 ampere; and the possible test
+ermination points of 1.81 volts per cell and 3.2 t ours have been revised to 1.75 volts per cell and 7.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to accomodate the increase to 60 cells and the recent battery load profile analysis.
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P-89264 Attachment'l J Page 2'of 2
- SR 5.6.2Lf. The_ requirement for a Performance. Discharge Test
- every.18 months ha's been revised from the TSUP ano Westinghouse Standard. Technical' Specification values-of degradation for Batteries IA and ;1B.
The-'new~'value of 95% has been established to provide margin-above the 90% of. rated . capacity.
required to service the four hour load profile for Batteries 1A and 18.
TABLE 5.6.2 The pilot cell. specific gravity value in the TSUP
-and NOTES has been revised from 2 1~.205 to 2 2.210
'to accommodate a. change in electrolyte referenceslevel. ,
The new cells have a low electrolyte' level and a'high electrolyte level marx whereas the.old cells had only. N one level reference mark in the middle. The new value is twferenced to the low level mark.
Note ~ (6) was removed from the allowable value for-the average specific Lgravity. for all connected cells to accommodate the new cells. The charging current' on the Lead Antimony Batteries will increase with : age' and will, .therefore, be _
- monitored administratively..
3r SR 5.6.2 Basis The pilot cell specific gravity has been ' revised; from the TSUP value of- 0.010' below the.
); manufacturer's full charge-specific gravity to a specific value of 1.210. The l'.210 value is in accordance with the Load Profile Analysis documented in EE-92-0012, dated October 1M3, 1988 and EE-92-0013, dated November 4, 1988.
The allowable value for an individual cell's specific gravity ha; been changed from a TSUP value of 0.040 below the full charge specific gravity to 0.020 below average of all connected cells. This change was made to accommodate vendor recommendations and the load profile analysis.
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ATTACHMENT 2 To P-89264 PROPOSED CHANGES
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