Similar Documents at Maine Yankee |
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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20206H1521999-05-0505 May 1999 Amend 164 to License DPR-36,deleting License Conditions 2.B.6.c,2.B.6.e,2.B.6.f,2.B.6.g,2.B.7(a) & 2.B.7(b) Which Are No Longer Applicable Due to Permanently Shutdown & Defueled Condition of Plant ML20206G5681999-05-0303 May 1999 Amend 163 to License DPR-36,revising Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20204C4561999-03-16016 March 1999 Amend 162 to License DPR-36,revising App a TS of License DPR-36 to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet ML20217H4991998-03-30030 March 1998 Amend 161 to License DPR-36,replacing App A,Ts to License DPR-36 in Entirety ML20202D3121997-11-26026 November 1997 Amend 160 to License DPR-36,revising Selected Portions of Plant TS 5.0 to Define Facility Staffing & Training Requirements for Permanently Shutdown & Defueled Facility ML20216F1291997-08-0808 August 1997 Amend 159 to License DPR-36,revising TS 5.5.B to Designate President of Maine Yankee as Responsible Official for Matters Re Nuclear Safety Audit & Review Committee ML20141G6301997-05-19019 May 1997 Amend 158 to License DPR-36,revising TS to Permit Use of 10CFR50,App J,Option B,performance-based Containment Leakage Rate Testing ML20138G3401997-05-0202 May 1997 Amend 157 to License DPR-36,revising TS 3.12, Station Svc Power, to Require Both 115 Kv Power Circuits to Be Operable When Reactor Critical ML20058E2561993-11-0505 November 1993 Amend 143 to License DPR-36,modifying TS 4.6.A Re Safety Injection & Containment Spray Sys,To Require Quarterly,Vice Monthly,Testing of Automatic Core Flooding & Containment Spray Valves ML20056G9321993-09-0101 September 1993 Corrected TS Page 4.5-1 to Amend 140 to License DPR-36 ML20056F7821993-08-23023 August 1993 Amend 142 to License DPR-36,deleting Surveillance Requirements for Environ Monitors from TS ML20127D4881993-01-11011 January 1993 Amend 136 to License DPR-36,modifying Remedial Action Requirements of TS 3.6.B & 3.6.C,by Deleting Alternate Train Testing Requirements ML20126H6071992-12-29029 December 1992 Amend 135 to License DPR-36,making Two Corrections to Core Operating Limits Presented in TS 5.14.1 ML20126C0981992-12-0909 December 1992 Errata to Amend 134 for License DPR-36,correcting Item 2 to Page One ML20059D0381990-08-30030 August 1990 Amend 117 to License DPR-36,modifying Tech Spec 3.14, Primary Sys Leakage, by Deleting Current Limit of 1.0 Gpm from All Steam Generator Tubes & Establishing 0.15 Gpm from Any One Steam Generator ML20246L4291989-07-14014 July 1989 Revised Pages 3.10-16 & 3.10-17 to Amend 107 to License DPR-36,correcting Typos ML20246F6231989-07-10010 July 1989 Amend 113 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Operation ML20245D4341989-04-24024 April 1989 Amend 112 to License DPR-36,modifying Tech Spec Table 3.9-3, Accident Monitoring Instrumentation & Table 4.1-3 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouple Channel Operability ML20245D4451989-04-24024 April 1989 Amend 111 to License DPR-36,changing Moderator Temp Coefficient Limit in Tech Specs Between 0% & 30% Power Levels ML20207L6021988-10-11011 October 1988 Correction to Amend 106 to License DPR-36,replacing Tech Spec Page 3.12-1 ML20155B4501988-09-27027 September 1988 Amend 107 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Reload Core ML20154A1311988-09-0707 September 1988 Amend 106 to License DPR-36,modifying Tech Spec 3.12 Re Station Svc Power by Prohibiting Reliance on 115 Kv Suroweic Line Unless Addl Justification Provided to NRC ML20196G6801988-06-23023 June 1988 Amend 105 to License DPR-36,changing Max Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core for Operating Cycle 11 & Beyond from 3.5 to 3.7% Nominal Weight U-235 ML20151W5731988-04-26026 April 1988 Amend 104 to License DPR-36,revising Tech Spec Figures 5.2-1 & 5.2-2 to Reflect Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure ML20149H2691988-02-17017 February 1988 Amend 103 to License DPR-36,changing Tech Specs to Update Figures 5.2.-1 & 5.2-2 in Tech Spec 5.2 Organization Depicting Plant Offsite & Facility Organization, Respectively ML20196C4211988-02-0909 February 1988 Amend 102 to License DPR-36,revising Tech Spec 3.10.C.3.1.1 to Reflect Revised LOCA Monitoring Limits to Be Used When in-core Monitoring Sys Inoperable ML20235M4591987-09-29029 September 1987 Amend 101 to License DPR-36,requiring Written Administrative Controls for Implementation of Process Control Program ML20216J0161987-06-25025 June 1987 Amend 99 to License DPR-36,revising Tech Specs 5.9.1.6 & 5.9.1.7,allowing Addl Time for Filing Supplemental Dose & Meteorological Summary Repts & Ensuring Refs to Other Tech Specs Correct ML20234B1691987-06-25025 June 1987 Amend 100 to License DPR-36,revising Tech Specs to Conform W/Generic Ltr 83-37 Requirements Re RCS Vent Sys ML20215E9211987-06-15015 June 1987 Amend 98 to License DPR-36,modifying Tech Specs to Reflect Revised LOCA Limits Using Revised Delta P Injection Penalty Factor During Reflood Phase of LOCA & Limiting Axial Power Shapes ML20214J5961987-05-20020 May 1987 Amend 97 to License DPR-36,deleting Requirement for Emergency Diesel Generator Testing in Event That Any Component of One Train of ECCS Becomes Inoperable ML20206U9001987-04-0909 April 1987 Amend 96 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 10 Reload Core by Modifying steady-state Peak Linear Heat Rate to Reflect Acceptable Fuel Design Limits for Prevention of Centerline Melting ML20197D4181987-03-26026 March 1987 Amend 94 to License DPR-36,revising Tech Specs Re Operability & Surveillance for New Noble Gas Effluent monitors,high-range Monitors & Water Level Monitors in Containment ML20212N6911987-03-0404 March 1987 Amend 93 to License DPR-36,adding Administrative Controls to Limit Overtime of Staff Personnel & Allow Dual Role of Senior Reactor Operator & Shift Technical Advisor ML20210V1531987-02-0909 February 1987 Amend 92 to License DPR-36,revising Tech Specs to Increase Fuel Enrichment Limit to 3.5 Weight Percent U-255 for Cycle 10 & Beyond ML20207M8151987-01-0606 January 1987 Errata to Amend 91 to License DPR-36,including Revised Table 4.2-2, Min Frequencies for Equipment Tests ML20215E7851986-12-11011 December 1986 Amend 91 to License DPR-36,revising Tech Specs,Including Restating Spec 3.14B for Clarity & Deleting Ref to Cycle 7 & Dividing Section 3.15 Re Reactor Power Anomalies Into Spec & Remedial Action ML20197B6001986-10-27027 October 1986 Amend 90 to License DPR-36,revising Tech Specs to Incorporate Specific Requirements for Iodine Spiking Into Annual Rept Per Generic Ltr 85-19 & to Delete Primary Coolant Iodine Activity Rept ML20195D3931986-05-27027 May 1986 Amend 89 to License DPR-36,adding Addl Manual Containment Isolation Valves & Blowdown & Body Vent Valves on Instrument Lines to List of Manual Containment Isolation Valves That May Be Repositioned ML20140C8821986-03-17017 March 1986 Amend 88 to License DPR-36,requiring Operability of Three Independent Steam Generator Auxiliary or Emergency Feedwater Pumps to Supply Emergency Feedwater to All Three Steam Generators ML20137Y7231986-03-0404 March 1986 Amend 87 to License DPR-36,changing Tech Specs to Require Monthly Operability Testing of turbine-driven Auxiliary Feedwater Pump ML20137A0391985-12-31031 December 1985 Amend 86 to License DPR-36,modifying Tech Specs to Assure Compliance W/App I,10CFR50,50.36 & 50.34a to Ensure Releases of Radioactive Matl to Unrestricted Areas During Normal Operation Remain ALARA ML20137Y8421985-09-30030 September 1985 Amend 85 to License DPR-36,modifying Tech Specs to Reflect Cycle 9 Power Distributions,Insertion Limits & Peaking Factors & Describe Max Reactor Inlet Temp Used in Modified Safety Analyses ML20134K8651985-08-20020 August 1985 Amend 84 to License DPR-36,changing Tech Specs to Require More Extensive Insp of Steam Generator Tubes in Critical Areas ML20062E2511982-07-21021 July 1982 Tech Spec Page 5.2-3 Figure 5.2-2) Establishing Separate Training Dept & Other Organization Changes.Page Inadvertently Omitted from Original Transmittal ML20062A0961982-07-14014 July 1982 Amend 61 to License DPR-36,increasing Required Number of Operable Safety Injection Actuation Signal Sensors & Establishing Training Dept & Other Organizational Changes ML20148Q1241978-11-0808 November 1978 Amend 42 to Facil Oper Lic DPR-36 Rev Tech Specs Re Radiological & Thermal Effluent Monitoring.Changes Involve Environ Surveillance Prog,Air Particulate Charcoal Gamma Monitoring & Estuary Water Temp Monitoring 1999-05-05
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20206H1521999-05-0505 May 1999 Amend 164 to License DPR-36,deleting License Conditions 2.B.6.c,2.B.6.e,2.B.6.f,2.B.6.g,2.B.7(a) & 2.B.7(b) Which Are No Longer Applicable Due to Permanently Shutdown & Defueled Condition of Plant ML20206G5681999-05-0303 May 1999 Amend 163 to License DPR-36,revising Liquid & Gaseous Release Rate Limits to Reflect Revs to 10CFR20, Stds for Protection Against Radiation ML20204C4561999-03-16016 March 1999 Amend 162 to License DPR-36,revising App a TS of License DPR-36 to Change Limiting Condition for Operation for Fuel Storage Pool Water Level from 23 Feet to 21 Feet ML20236T4711998-07-14014 July 1998 Application for Amend to License DPR-36,consisting of Proposed Change 209,amending TS to Revise Liquid & Gaseous Release Rate Limits to Reflect Replacement of Former 10CFR20.106 Requirements W/Existing Requirements ML20216F8831998-04-13013 April 1998 Application for Amend to License DPR-36,consisting of Proposed Change 208,revising TS to Base LCO for Fuel Storage Pool on Revised Analysis for Fuel Handling Accident & on New Analysis for Radiological Shielding During Movement of Fuel ML20217H4991998-03-30030 March 1998 Amend 161 to License DPR-36,replacing App A,Ts to License DPR-36 in Entirety ML20202D3121997-11-26026 November 1997 Amend 160 to License DPR-36,revising Selected Portions of Plant TS 5.0 to Define Facility Staffing & Training Requirements for Permanently Shutdown & Defueled Facility ML20212A6021997-10-20020 October 1997 Application for Amend to License DPR-36,consisting of Proposed TS Change 207,reflecting Permanently Defueled Status of Plant ML20211H6691997-09-30030 September 1997 Application for Amend to License DPR-36,eliminating Conditions,No Longer Appropriate in Permanently Defueled Condition ML20210M5801997-08-15015 August 1997 Application for Amend to License DPR-36,consisting of TS Change 206,revising TS Re Facility Staffing & Training ML20216F1291997-08-0808 August 1997 Amend 159 to License DPR-36,revising TS 5.5.B to Designate President of Maine Yankee as Responsible Official for Matters Re Nuclear Safety Audit & Review Committee ML20141G6301997-05-19019 May 1997 Amend 158 to License DPR-36,revising TS to Permit Use of 10CFR50,App J,Option B,performance-based Containment Leakage Rate Testing ML20138G3401997-05-0202 May 1997 Amend 157 to License DPR-36,revising TS 3.12, Station Svc Power, to Require Both 115 Kv Power Circuits to Be Operable When Reactor Critical ML20136B5161997-03-0505 March 1997 Application for Amend to License DPR-36,requesting Approval of Alternative Sleeving Repair Process for SG Tubes at Plant ML20134J6551997-02-0707 February 1997 Proposed TS Change 203 to License DPR-36,revising TS Pages 3.12-1,3.12-2 & 3.12-3 Re 115 Kv Offsite Power Requirements ML20134J6261997-02-0707 February 1997 Proposed TS Change 204 to License DPR-36,requesting one-time Extension of SG Tube Surveillance Interval as Specified in TS 4.10.C.2 ML20133A7011996-12-19019 December 1996 Application for Amend to License DPR-36,requesting Rev to Boronometer Operability Requirement & Reactor Coolant Boron Sampling ML20058E2561993-11-0505 November 1993 Amend 143 to License DPR-36,modifying TS 4.6.A Re Safety Injection & Containment Spray Sys,To Require Quarterly,Vice Monthly,Testing of Automatic Core Flooding & Containment Spray Valves ML20056G9321993-09-0101 September 1993 Corrected TS Page 4.5-1 to Amend 140 to License DPR-36 ML20056F7821993-08-23023 August 1993 Amend 142 to License DPR-36,deleting Surveillance Requirements for Environ Monitors from TS ML20127P2191993-01-25025 January 1993 Application for Amend to License DPR-36,consisting of Proposed TS Change 177 to Allow Increase in Number of Spent Fuel Assemblies Stored in Spent Fuel Pool from 1,476 to 2,019.Rev 0 to Licensing Rept... Encl ML20127D4881993-01-11011 January 1993 Amend 136 to License DPR-36,modifying Remedial Action Requirements of TS 3.6.B & 3.6.C,by Deleting Alternate Train Testing Requirements ML20126H6071992-12-29029 December 1992 Amend 135 to License DPR-36,making Two Corrections to Core Operating Limits Presented in TS 5.14.1 ML20126B6821992-12-15015 December 1992 Proposed TS Change 176 to License DPR-36,modifying TS 3.19 & 4.6 for Consistency W/Change in Normal Operating Position of LPSI motor-operated Isolation Valves from Closed to Open ML20126C0981992-12-0909 December 1992 Errata to Amend 134 for License DPR-36,correcting Item 2 to Page One ML20198D0701992-05-0808 May 1992 Proposed TS Change 166 to License DPR-36,revising Section 1.4 to Eliminate Ref to Containment Air Recirculation Sys from TS 1.4.D, Containment Purge Sys ML20141M1121992-03-24024 March 1992 Application for Amend to License DPR-36,consisting of TS Proposed Change 165,revising Fuel Enrichment Limit & Allowing Radial & Axial Zoning of Enrichment Up to 3.95 Weight Percent U-235 ML20062D2801990-11-0505 November 1990 Application for Amend to License DPR-36,consisting of Proposed Change 151 Re Removal of cycle-specific Limits in Response to Generic Ltr 88-16 ML20058B5941990-10-15015 October 1990 Proposed Change 156 Requesting Amend to License DPR-36, Modifying Tech Spec 3.22, Feedwater Trip Sys, by Adding Exception Specifically Addressing Operation of Emergency Feedwater Sys During Plant Startups & Shutdowns ML20059D0381990-08-30030 August 1990 Amend 117 to License DPR-36,modifying Tech Spec 3.14, Primary Sys Leakage, by Deleting Current Limit of 1.0 Gpm from All Steam Generator Tubes & Establishing 0.15 Gpm from Any One Steam Generator ML20058L9271990-07-30030 July 1990 Application for Amend to License DPR-36,consisting of Proposed Change 154,revising Page 5.2-2 Re Manager Qualification Requirements for Operations ML20055G3101990-07-10010 July 1990 Application for Amend to License DPR-36,consisting of Tech Spec Change 155 Re Safety Injection Actuation Sys ML20055E0951990-07-0505 July 1990 Application for Amend to License DPR-36,consisting of Proposed Change 154,modifying Tech Specs Re Qualification Requirements for Operations Manager ML20246L4291989-07-14014 July 1989 Revised Pages 3.10-16 & 3.10-17 to Amend 107 to License DPR-36,correcting Typos ML20246F6231989-07-10010 July 1989 Amend 113 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Operation ML20245D4451989-04-24024 April 1989 Amend 111 to License DPR-36,changing Moderator Temp Coefficient Limit in Tech Specs Between 0% & 30% Power Levels ML20245D4341989-04-24024 April 1989 Amend 112 to License DPR-36,modifying Tech Spec Table 3.9-3, Accident Monitoring Instrumentation & Table 4.1-3 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouple Channel Operability ML20235H5401989-02-15015 February 1989 Application for Amend to License DPR-36,consisting of Proposed Change 146,amending Tech Spec Sections 3.9 & 4.1 to Add Primary Inventory Trend Sys for Reactor Vessel Level Indication & Core Exit Thermocouples Channel Operability ML20196B5261988-11-22022 November 1988 Application for Amend to License DPR-34,consisting of Proposed Change 134 Re Main Steam Excess Flow Check Valve. Amend Modifies Tech Spec 4.6 Re Periodic Testing by Extending Specified Surveillance Testing Interval ML20206F2281988-11-0808 November 1988 Application for Amend to License DPR-36,modifying Tech Spec 1.1, Fuel Storage. Fee Paid ML20205T2091988-11-0202 November 1988 Application for Approval to Leave Inplace,Slightly Contaminated Soil Next to Reactor Water Storage Tank. Radiological Assessment Encl.Fee Paid ML20206C2571988-10-26026 October 1988 Application for Amend to License DPR-36,amending Tech Spec Section 5.2 to Delete Offsite & Facility Organization Charts,Per Generic Ltr 88-06.Fee Paid ML20205M9611988-10-18018 October 1988 Application for Amend to License DPR-36,consisting of Proposed Change 133,modifying Specified Surveillance Interval for Control Element Assembly Partial Movement Test from Once Every 2 Wks to Monthly.Fee Paid ML20207L6021988-10-11011 October 1988 Correction to Amend 106 to License DPR-36,replacing Tech Spec Page 3.12-1 ML20155B4501988-09-27027 September 1988 Amend 107 to License DPR-36,modifying Tech Specs to Reflect Operating Limits for Cycle 11 Reload Core ML20154A1311988-09-0707 September 1988 Amend 106 to License DPR-36,modifying Tech Spec 3.12 Re Station Svc Power by Prohibiting Reliance on 115 Kv Suroweic Line Unless Addl Justification Provided to NRC ML20150E8971988-06-30030 June 1988 Application for Amend to License DPR-36,consisting of Proposed Change 141,revising Tech Specs to Reflect Cycle 11 Operation.Cycle 11 Core Performance Analysis Rept Encl.Fee Paid ML20196G6801988-06-23023 June 1988 Amend 105 to License DPR-36,changing Max Nominal Enrichment of Fuel Allowed to Be Used in Reactor Core for Operating Cycle 11 & Beyond from 3.5 to 3.7% Nominal Weight U-235 ML20151W5731988-04-26026 April 1988 Amend 104 to License DPR-36,revising Tech Spec Figures 5.2-1 & 5.2-2 to Reflect Successional Change in Offsite Corporate Organization & Associated Changes in Functional Reporting Structure ML20150E4071988-03-24024 March 1988 Application for Amend to License DPR-36,increasing Max Nominal Fuel Enrichment from 3.5% to 3.7% U-235.Fee Paid 1999-05-05
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Uro g i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066 4 001
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MAINE YANKEE ATOMIC POWER COMPANY DOCKET N0. 50-309 MAINE YANKEE ATOMIC POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.157 License'No. DPR-36
- 1. The Nuclear Regulatory Commission (the Comission) has found that:
A. The application for amendment by Maine Yankee Atomic Power Company (the licensee) dated February 7, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in acccrdance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
P. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.B(6)(b) of Facility Operating License No. DPR-36 is hereby amended to read as follows:
j 9705060267 970502 PDR ADOCK 05000309 P PDR n I
b 4
(b) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.157, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of its date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
%o Patrick D. Milano, Acting Director Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 2, 1997 l
l l
1 I
I
I ATTACHMENT TO LICENSE AMENDMENT N0.157 FACILITY OPERATING LICENSE NO. DPR-36 DOCKET N0. 50-309 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages. The revised pages are identified by Amendment number and i contain vertical lines indicating the areas of change. '
Remove Insert 3.12-1 3.12-1 3.12-2 3.12-2 3.12-3 I
1 4
3.12 STATION SERVICE POWER Aoolicability: Applies to station service electrical power system.
Ob.iectives: To assure an adequate supply of electrical power during station operation.
Specification:
A. The following equipment must be operable.whenever the reactor coolant system temperature and pressure exceed 210*F and 400 psig.
- 1. One 115 kV incoming line in service.
- 2. Diesel generator DG-1A operable; 4160v emergency bus 5, 480v emergency bus 7, and d-c distribution cabinet 1 in service.
or j Diesel generator DG-1B operable; 4160v emergency bus 6, 480v emergency bus 8, and d-c distribution cabinet 3 in service.
1
- 3. 18,300 gallons of diesel fuel oil in the fuel oil tanks.
Remedial Action: Restore required power supply limiting condition within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
B. The following equipment must be operable whenever the reactor is critical.
- 1. Both 115 kV incoming lines in service. l
- 2. Diesel generator DG-1A operable; 4160v emergency bus 5, 480v emergency bus 7, and d-c distribution cabinet 1 in service.
- 3. Diesel generator DG-1B operable; 4160v emergency bus 6, 480v emergency bus 8, and d-c distribution cabinet 3 in service.
- 4. 28,800 gallons of diesel fuel oil in the fuel oil tanks.
Remedial Action:
- 1. If one 115 kV incoming line becomes inoperable, restore it to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
- 2. If both 115 kV incoming lines become inoperable, restore one to operable status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- 3. If either diesel generator or its associated emergency buses or d-c distribution cabinet becomes inoperable, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> determine the operable diesel generator is not inoperable due to common cause failure or within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test the operable diesel 3.12-1 Amendment No. 19,55,105,140,157
l generator in accordance with Specification 4.5.A.I. The -
inoperable equipment shall be restored to the operable status within seven days. l l
- 4. If one 115 kV incoming line and either diesel generator or its l 4
associated emergency buses or de distribution cabinet are not operable, restore the inoperable 115 kV line or the diesel g generator (or its associated emergency buses or de distribution 4 cabinet) within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
- 5. If both diesel generators or their associated emergency buses or i d-c distribution cabinets are not operable, restore one diesel generatur (or its associated emergency buses or d-c distribution !
cabinet) to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. l
- 6. If the diesel fuel oil level in the fuel oil tanks is less than l 28,800 gallons but greater than 24,700 gallons, restore the fuel
- oil level within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
C. Under accident conditions, the automatically connected load to either diesel generator shall not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating of 2850 KW.
Basis:
- )
Specification A assures that an emergency power source is operable whenever l the reactor coolant system is above the specified pressure and temperature limit. It recognizes the decreased consequences _of a loss of coolant accident 4
if the reactor is subcritical.
l The fuel requirement for Specification A of 18,300 gallons is made up as i
follows: 1 A. 16,637 gallons is the amount that will be required for the maximum I i expected engineered safeguards load for the maximum resupply time of '
4 days.
B. 10 percent of the above as a contingency for any non-engineered safeguard requirement during this period. ,
Specification B assures the operability of power to the engineered safeguards equipment that is necessary when the reactor is critical. If the loss of one of the 115 kV incoming lines occurs, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of operation is
, permitted while the situation is being assessed and full redundancy is being restored. If the loss of both 115 kV incoming lines occurs, a period of 24 '
hours of operation is permitted while the situation is being assessed and one of the 115 kV incoming lines is being restored. Following the restoration of this line, the remaining portion of the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> remedial action time is permitted to restore full redundance, as described above. If the loss of a diesel generator or its associated emergency buses or d-c distribution cabinet occurs, a period of seven days of operation is permitted while the situation is being assessed and full redundancy is being restored. These time periods are justified because adequate sources o' power remain available for the operation of the engineered safeguards ejuipment.
3.12-2 Amendment No. 55,105,140,157
)
The time period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for restoring either the inoperable 115 kV l incoming line or an inoperable diesel generator when both are inoperable takes into account the capacity and capability of the remaining AC sources, a i reasonable time for repairs, and the low probability of a design basis i accident occurring during this period. It recognizes that there are risks involved with performing a shutdown in a degraded condition that are balanced i against the risks.of remaining at power to perform repairs. Following the restoration of either the diesel generator or the 115 kV incoming line to
- operable status, the remaining portion of the respective remedial action time
- is permitted to restore full redundancy as described above.
4 With DG-1A and DG-1B inoperable, there are no remaining standby AC sources.
- Thus, with an assumed loss of offsite electrical power, insufficient standby l AC sources are available to power the minimum required ESF functions. Since i the offsite electrical power system is the only source of AC power for this -
level of degradation, the risk associated with continued operation for a short time could be less than that associated with an immediate controlled shutdown (the immediate shutdown could cause grid instability, which could result in a i
~
total loss of AC power). Since any inadvertent generator trip could also result in a total loss of offsite AC power, however, the time allowed for
- continued operation is restricted to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The intent is to avoid the risk i associated with an immediate controlled shutdown and to minimize the risk associated with this level of degradation.
3 The fuel requirement for Specification B of 28,800 gallons is made up as
- follows:
i A. 26,182 gallons is the amount that will be required for the maximum i expected engineered safeguards load for a period of seven days.
i B. 10 percent.of the above as a contingency for any non-engineered safeguard requirement during this period.
1 C. Fuel oil tank level is restricted to fuel oil level reductions that maintain at least a 6 day' supply. This restriction allows
- sufficient time for obtaining the requisite replacement volume and
! performing the fuel analyses required prior to addition of fuel oil
, to the tank. A period of 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> is considered sufficient to complete restoration of the required level prior to declaring DGs 3
inoperable. This period is acceptable based on the remaining capacity (greater than 6 days), the fact that procedures will be i- initiated to obtain replenishment, and the low probability of an event during this brief period.
I 3.12-3 Amendment No. 55,105, MO,157 l
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