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MONTHYEARML20151Z2871986-01-29029 January 1986 Proposed Tech Spec Changes,Correcting Typos,Inadvertent Omissions & Grammatical Inconsistencies Originating from Previous Amends Project stage: Other ML20151Z2761986-01-29029 January 1986 Application for Proposed Amend 139 to License DPR-54, Changing Tech Specs to Correct Typos,Inadvertent Omissions & Grammatical Inconsistencies Originating from Previous Amends.Fee Paid Project stage: Request ML20153E0591986-02-14014 February 1986 Proposed Tech Specs,Correcting Misleading Work in Section 6.17.2 Re Administrative Controls Project stage: Other ML20153E0521986-02-14014 February 1986 Application for Amend to License DPR-54,changing Tech Specs to Correct Misleading Word in Section 6.17.2 Re Administrative Controls.Fee Paid Project stage: Request ML20154R9301986-03-20020 March 1986 Proposed Editorial Changes to Tech Spec Section 1.9 Re Time Period for Surveillance Tests Project stage: Other ML20154R9221986-03-20020 March 1986 Application for Proposed Amend 136 to License DPR-54, Correcting Tech Spec Section 1.9 Re Time Interval for Surveillance Tests Due to Editorial Errors.Fee Paid Project stage: Request ML20199B8671986-06-13013 June 1986 Proposed Tech Spec Pages 3-22,3-41 & 3-42,changing Wording & Identifying Specific Batteries Required for Nuclear Svc Project stage: Other ML20199B3341986-06-13013 June 1986 Application for Proposed Amend 135 to License DPR-54, Changing Wording in Tech Spec 3.3 & Identifying Specific Batteries in Tech Specs 3.7.1E,F,G & 3.7.2F.Safety Analysis & NSHC Also Encl.Fee Paid Project stage: Request ML20214A3081986-11-10010 November 1986 Informs of Util Decision to Abandon Proposed Amend 133. Proposed Amend 135 Changes to Specs 3.3,3.3.3 & 3.7.1E Still Required.Administrative Work on Second Part of Proposed Amend 135 May Be Abandoned Project stage: Other ML20245C6901987-10-27027 October 1987 Forwards Amend 87 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Make Numerous Administrative Changes to Tech Specs & Bases Project stage: Approval 1986-02-14
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20059C1861993-12-22022 December 1993 Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes ML20058L4371993-12-0909 December 1993 Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20246F1241989-07-0505 July 1989 Proposed Tech Specs,Deleting App B in Entirety ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 ML20245L0461989-04-27027 April 1989 Proposed Tech Specs for Proposed Suppl 1 to Amend 134 Re Application for Amend to License DPR-54,clarifying Unacceptability of Analysis Allowing Imperfections Greater than 40% of Nominal Tube or Sleeve Wall Thickness ML20235Y6071989-03-0606 March 1989 Proposed Tech Spec Page 4-17,including one-time Extension for Certain Surveillances Required to Be Performed by 890329 ML20245H8911989-02-28028 February 1989 Revised Proposed Tech Specs,Including Pages 3-30a,3-30b, 3-40a,3-45,3-46,4-18a & 4-75 Re Addition of Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations ML20195F7701988-11-18018 November 1988 Proposed Tech Spec Section 3.4, Steam & Power Conversion Sys ML20206F2881988-11-15015 November 1988 Proposed Tech Specs 4.6.4.f (Page 4-34i) Re Surveillance of Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8681988-11-0404 November 1988 Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity ML20205M8971988-10-28028 October 1988 Proposed Tech Specs Re Nuclear Svc Battery Operability & Surveillance Requirements ML20205L2661988-10-25025 October 1988 Proposed Tech Spec Table 3.14-3, Carbon Dioxide Suppression Zones ML20155G2201988-10-0707 October 1988 Proposed Tech Specs Clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train ML20155B4591988-09-30030 September 1988 Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes ML20155B8481988-09-30030 September 1988 Proposed Tech Specs Re Reactor Protection Sys Trip Setting Limits,Rcs High Point Vents,Leakage & Leak Detection,Reactor Coolant Inventory & Auxiliary Electric Sys ML20154J5611988-09-19019 September 1988 Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations ML20154D7591988-09-0808 September 1988 Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff ML20153E6481988-08-31031 August 1988 Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves ML20207C0831988-07-27027 July 1988 Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B ML20196A2281988-06-21021 June 1988 Proposed Tech Specs Providing Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation & Modifying Existing Purge Sys Operation Requirement ML20155K0971988-06-14014 June 1988 Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4921988-06-10010 June 1988 Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis ML20150D1861988-03-17017 March 1988 Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129 ML20196G5131988-03-0101 March 1988 Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite ML20149K8621988-02-12012 February 1988 Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review ML20196D9091988-02-11011 February 1988 Proposed Tech Specs,Adding Term Dewatering to Process Control Program ML20149G1781988-02-0808 February 1988 Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart ML20148J3531988-01-13013 January 1988 Proposed Tech Specs,Consisting of Proposed Amend 165,adding Ventilation Radiation Monitor to Interim Onsite Storage Bldg.Related Info Encl ML20149E5971988-01-0606 January 1988 Proposed Tech Spec 3.6,consolidating Applicability Requirement for Containment Integrity in Applicability Statement ML20149E1591987-12-23023 December 1987 Proposed Tech Specs Incorporating Accident Monitoring Instrumentation Recently Installed or Upgraded ML20149E8591987-12-22022 December 1987 Proposed Tech Specs,Establishing New Set Lower Limits of Detection for Prebatch Release & Composite post-release Analyses ML20237D1171987-12-15015 December 1987 Proposed Tech Spec Section 3.5.5, Accident Monitoring Instrumentation & Table 3.5.5-1, Accident Monitoring Instrumentation Operability Requirements, Changing Page Ref & Wording,Respectively ML20236W8671987-12-0303 December 1987 Proposed Tech Spec,Combining Tech Specs 3.3.1.E & 3.3.1.F for Nuclear Svc Cooling & Raw Water ML20236V7961987-11-25025 November 1987 Proposed Tech Spec Figures 6.2-1 & 6.2-2,reflecting Util Corporate Support of Nuclear Safety & Nuclear Organization Chart,Respectively ML20236U3361987-11-25025 November 1987 Proposed Tech Specs Page 1-2b,adding Words to Effect That 3.25 Factor Applicable to Three Consecutive Time Intervals Will Be Reset to Begin After Next Surveillance ML20236U0821987-11-25025 November 1987 Proposed Tech Specs,Consisting of Suppl 1 to Rev 0 to Proposed Amend 164 ML20236S0881987-11-17017 November 1987 Proposed Tech Specs,Consisting of Suppl 2 to Rev 2 to Proposed Amend 147,concerning Diesel Generators ML20236P3511987-11-0606 November 1987 Proposed Tech Specs Re Limiting Condition for Operation of Instrumentation Sys ML20236K3921987-11-0202 November 1987 Proposed Tech Spec Table 6.2-1, Shift Crew Personnel & License Requirements & Pages 6-7 & 6-8,adding non-licensed Personnel,Statement Re Limiting Representation to Minority of Quorom & Lers,Respectively ML20236D6601987-10-23023 October 1987 Proposed Tech Specs,Providing Exception to Requirement That key-operated Shutdown Bypass Switch Not Be Used During Reactor Power Operation ML20235R4261987-10-0303 October 1987 Proposed Radiological Effluent Tech Specs,Incorporating Clarifications & Correcting Editorial Errors ML20235Q5111987-10-0101 October 1987 Proposed Tech Specs Re Comparison of Plant Tech Specs to STS ML20235F5301987-09-22022 September 1987 Proposed Tech Specs Consisting of Supplemental Info to Proposed Amend 147,Rev 2 Re Diesel Generator Outages ML20235F4641987-09-21021 September 1987 Proposed Tech Specs Changing Requirements Re Concentration of Oxygen in Waste Gas Holdup Sys to Provide for When Sys Free of Potentially Explosive Gases,For Example,During Maint ML20234D6591987-09-16016 September 1987 Proposed Tech Specs,Reflecting Addl Organizational Changes Due to Need for Addl Mgt Staffing for Present Outage & from Expansion of long-term Mgt Function ML20238E8351987-09-0808 September 1987 Corrected Tech Spec Page 4-47c to Proposed Amend 151 to License DPR-54,adding ...Will Be Exceeded Prior to Next Scheduled Snubber Svc Life... to Last Paragraph of Tech Spec 4.14f ML20236M3531987-07-31031 July 1987 Proposed Tech Specs,Clarifying Proposed Limiting Conditions of Operation & Addl Surveillance Requirements for Emergency Feedwater Initiation & Control Sys 1993-12-09
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20203H7501997-08-19019 August 1997 Rev 10 to Radiological Environ Monitoring Program Manual ML20203H7351997-02-10010 February 1997 Rev 9 to CAP-0002, Off-Site Dose Calculation Manual ML20203H7231997-01-21021 January 1997 Rev 9 to Radiological Environ Monitoring Program Manual ML20059C1861993-12-22022 December 1993 Proposed Tech Specs Amend 186,rev 1 Re Nuclear Organizational Changes ML20058L4371993-12-0909 December 1993 Proposed Tech Specs Amend 187 Including Changes Making PDTS Consistent W/New 10CFR20 Regulations ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20059E0241989-11-22022 November 1989 Rev 3 to Environ Monitoring & Emergency Preparedness ML20246A4081989-08-16016 August 1989 Rev 5 to Inservice Testing Program Plan ML20245L7281989-07-18018 July 1989 Rev 5 to Administrative Procedure RSAP-0101, Nuclear Organization Responsibilities & Authorities ML20246F1241989-07-0505 July 1989 Proposed Tech Specs,Deleting App B in Entirety ML20246A5221989-06-30030 June 1989 Closure Plan ML20245H5781989-06-22022 June 1989 Proposed Tech Specs for Amend 109 to License DPR-54 ML20246E8551989-04-30030 April 1989 Analysis of Capsule RS1-F Smud Reactor Vessel Matl Surveillance Program ML20245L0461989-04-27027 April 1989 Proposed Tech Specs for Proposed Suppl 1 to Amend 134 Re Application for Amend to License DPR-54,clarifying Unacceptability of Analysis Allowing Imperfections Greater than 40% of Nominal Tube or Sleeve Wall Thickness ML20235Y6071989-03-0606 March 1989 Proposed Tech Spec Page 4-17,including one-time Extension for Certain Surveillances Required to Be Performed by 890329 ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept ML20245H8911989-02-28028 February 1989 Revised Proposed Tech Specs,Including Pages 3-30a,3-30b, 3-40a,3-45,3-46,4-18a & 4-75 Re Addition of Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations ML20195F7701988-11-18018 November 1988 Proposed Tech Spec Section 3.4, Steam & Power Conversion Sys ML20206F2881988-11-15015 November 1988 Proposed Tech Specs 4.6.4.f (Page 4-34i) Re Surveillance of Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8681988-11-0404 November 1988 Proposed Tech Specs Re Local Leakage Rate Tests & Reactor Bldg Containment Integrity ML20205M8971988-10-28028 October 1988 Proposed Tech Specs Re Nuclear Svc Battery Operability & Surveillance Requirements ML20205L2661988-10-25025 October 1988 Proposed Tech Spec Table 3.14-3, Carbon Dioxide Suppression Zones ML20155G2201988-10-0707 October 1988 Proposed Tech Specs Clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train ML20155B8481988-09-30030 September 1988 Proposed Tech Specs Re Reactor Protection Sys Trip Setting Limits,Rcs High Point Vents,Leakage & Leak Detection,Reactor Coolant Inventory & Auxiliary Electric Sys ML20155B4591988-09-30030 September 1988 Proposed Tech Spec Sections 1,3,4,5 & 6,reflecting Numerous Editorial Corrections & Administrative Changes ML20206A8151988-09-28028 September 1988 Rev 0 to, Effluents & Water Mgt Project Action Plan ML20154J5611988-09-19019 September 1988 Proposed Tech Specs,Changing Local Leak Rate Test Requirements for Containment Penetrations ML20154D7591988-09-0808 September 1988 Proposed Tech Specs Re Administrative Controls,Onsite & Offsite Organizations & Facility Staff ML20153E6481988-08-31031 August 1988 Proposed Tech Specs on Limiting Condition for Operation Re Containment Isolation Valves ML20151K1041988-07-28028 July 1988 Rev 0 to Special Test Procedure STP.668, EFIC High/Medium Decay Heat Test ML20207C0831988-07-27027 July 1988 Revised Proposed Tech Specs,Consisting of Rev 1 to Proposed Amend 102,deleting App B ML20151H6131988-07-15015 July 1988 Rev 0 to Matl Control Dept Action Plan for Rancho Seco Nuclear Generating Station ML20196A2281988-06-21021 June 1988 Proposed Tech Specs Providing Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation & Modifying Existing Purge Sys Operation Requirement ML20155K0971988-06-14014 June 1988 Proposed Tech Specs Making Minor Corrections to Table 3.5.5-1, Accident Monitoring Instrumentation,Items 5 & 14 & Table 4.1-1 Items 65 & 92 & Adding Second Note to Table 4.1-1,Item 80 ML20195J4921988-06-10010 June 1988 Proposed Tech Spec Pages 4-69 Through 4-85a,modifying Radiological Effluent Tech Specs to Reduce Count Time Required for prebatch-release Sample Analysis ML20151R0641988-04-15015 April 1988 Rev 0 to STP.1154, Remote Shutdown Panel Test ML20151X3211988-04-0606 April 1988 Rev 1 to Procedure Development Project Action Plan for Temporary & Interim Procedure Change Incorporation as Procedure Rev ML20151V5871988-04-0202 April 1988 Rev 1 to Sys Engineering Action Plan SYSTEM-012, CRD Breaker Action Plan ML20151X2871988-03-31031 March 1988 Rev 0 to Sys Engineering Action Plan SYSTEM-009, Letdown Cooler Thermal & Hydraulic Shock Prevention ML20150D1861988-03-17017 March 1988 Proposed Tech Specs,Correcting Typos & Making Further Editorial Changes to Proposed Amend 139,dtd 860129 ML20196G5131988-03-0101 March 1988 Proposed Tech Specs,Revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 Re Total Quantity of Gaseous Chlorine in Restricted Area ML20147F0771988-02-25025 February 1988 Revised Proposed Tech Spec Table 4.1-1 & Tech Spec 4.10.1.E.2,requiring Performance of Surveillances Only When Gaseous Chlorine Onsite ML20147B1761988-02-15015 February 1988 Rev 0 to RECM-6878, Radiological Effluent Control Manual ML20148D9931988-02-12012 February 1988 Post-Trip Transient Investigation,Assessment & Reporting ML20149K8621988-02-12012 February 1988 Proposed Tech Spec 6.5.1.6.d,identifying Items Not Requiring Plant Review Committee Review ML20196D9091988-02-11011 February 1988 Proposed Tech Specs,Adding Term Dewatering to Process Control Program ML20149G1781988-02-0808 February 1988 Proposed Page 3-19 to Tech Spec 3.3, Emergency Core Cooling,Reactor Bldg Emergency Cooling & Reactor Bldg Spray Sys ML20196B8071988-02-0101 February 1988 Proposed Tech Spec Figure 6.2-2, Nuclear Organization Chart 1997-08-19
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Liniting Conditions for Operation
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The requirement that one BWST isolation valve shall be open assures a static l head to the injection pump not lined up to the makeup tank. l The post acci: lent Reactor Building cooling may be accomplished by two spray units or by a combination of two emergency cooling units and one spray unit.
The specified requirements assure that the required post accident components are available.
The spray system utilizes common suction lines with the decay heat removal system. If a single train of equipment is removed from either system, the other train must be assured to be operable in each system.
When the reactor is critical, maintenance is allowed per Specification 3.3.2 provided requirements in Specification 3.3.3 are met which assure operability of the duplicate components. Operability of the specified components shall be based on the results of testing as required by Technical Specification 4.5.
143>
In the event that the need for emergency core cooling should occur, functioning of one train (one high pressure injection pump, one decay heat removal pump and.both core flooding tanks) will protect the core and in the event of a main coolant loop severance, limit the peak clad temperature to less than 2,200*F and the metal-water reaction to less than 1 percent of the clad.
.The nuclear service cooling water system consists of two independent, full capacity (3sLOO percent redundant systems, to ensure continuous heat removal.
The requirements of Specification 3.3.4 assure that the decay heat removal system will not be overpressurized, resulting in a LOCA that bypasses containment. Two in-series check valves function as a pressure isolation barrier between the high pressure reactor coolant system and the lower pressure decay heat removal system extending beyond containment. Valve leakage limits provide assurance that the valves are performing their intended isolation function.
The requirements of Specification 3.3.5 assure that, should all trains of a Safety Features equipment or system specified in this section 3.3 become inoperable as defined in Specification 1.3, the reactor will be placed in a cold shutdown condition. It is necessary for a component or system to have available its normal and emergency sources of power. When a system or component is determined to be inoperable solely because its normal or emergency power source is inoperable, it may be considered OPERABLE for the purpose of satisfying the requirements of its applicable Limiting Conditions for Operation provided its redundant system or component is OPERABLE with an OPERABLE normal and emergency power source.
REFERENCES (1) FSAR, paragraph 6.2.1 (2) FSAR, paragraph 9.5.2 (3) FSAR, paragraph 9.4.1 Proposed Amendment No. 143 3-22 8606170239 860613 PDR P
ADOCK 05000312 PDR
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RANCHO SECO UNIT 1
. TECHNICAL SPECIFICATIONS
...- Limiting Conditions for Operation 3.7 AUXILIARY ELECTRICAL SYSTEMS Applicability Applies to the availability of off-site and on-site electrical power for station operation and for operation of station auxiliaries.
Objective To define those conditions of electrical power availability necessary to provide for safe reactor operation and to provide for continuing availability of engineered safety features in an unrestricted manner.
Specification 3.7.1 The reactor shall not be brought critical unless the following conditions are met:
A. All nuclear service buses, nuclear service switchgear, and nuclear service load shedding systems are operable.
B. Two 220 KV lines are in service.
C. One 6900 volt reactor coolant pump motors bus is energized.
D. Emergency diesel generators A and B are operable and at least 35,000 gallons of fuel are in each storage tank.
135> E. Nuclear Service batteries BA, BB, BC, BD, BA2 and BB2, which
< supply vital 125 VDC buses SOA, SOB, SOC, S0D, SOA2 and S082, are charged and in service.
F. Two out of three battery chargers are operable for 125 volt DC 135>< buses SOA, SOB, SOC, and S0D.
G. One out of two battery chargers are operable for each 125 VDC bus 135>< S0A2 and SOB 2.
H. Three out of four inverters SIA, SIB, SIC, and S1D, and both inverters SIA2 and S182 are operable for 120 volt AC vital bus power.
I. Both startup transformers, No. 1 and No. 2, are in service.
J. The switchyard voltage is 215 KV or above.
K. The interconnections between 480 volt switchgear 3A and 3A2, and 2 3B and 382 are operable.
3.7.2 The reactor shall not remain critical unless all of the following requirements are satisfied:
A. One 220 KV line shall be fully operational and capable of carrying nuclear service and auxiliary power except as specified in D below.
Proposed Amendment No. 135 3-41
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- RANCHO SECO UNIT 1
.. TECHNICAL SPECIFICATIONS Limiting Conditions for Operation B. Both startup transformers shall be in service except that one will be sufficient if during the. time one startup transformer is inoperable, the associated diesel generator is started and run continuously.
C. Both diesel generators shall be operable except that from and after the date that one of the diesel generators is made or found to be inoperable for any reason, reactor operation is permissible for the succeeding 15 days provided that during such 15 days the operable diesel generator shall be load tested daily and both startup transformers are available. If the diesel is not returned to service at the end of 15 days, the other diesel will be started and run with at least minimum load continuously for an additional 15 days. If at the end of the second 15 days the diesel is not returned to service, the reactor shall be brought to the cold shutdown condition within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D. If the plant is separated from the system while carrying its own auxiliaries, or if all 220 KV lines are lost, continued reactor operation is permissible provided that one emergency diesel generator is started and run continously until a transmission line is restored.
E. The essential nuclear service electrical buses, switchgear, load shedding, and automatic diesel start systems shall be operable except as provided in C above and as required for surveillance testing.
135>< F. Nuclear service batteries identified in Section 3.7.1E are charged and in service except that one nuclear service battery may be removed from service for not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
G. Both sets of nuclear services buses 4A, 4A2 and 4B, 4B2 are operable except that one set of nuclear service buses (4A, 4A2 or 4B, 4B2) may be removed from service for not more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided that all equipment on the other set of nuclear service buses is operable.
i H. If the switchyard voltage goes below 219KY, positive actions, within the District's procedures, will be implemented in an attempt to return the voltage to 219KV. If the switchyard voltage goes below 217KY or remains below 219KV for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, one electrical division will be operated on its diesel generator independent of off-site power. The other electrical
, division will be operated on off-site power with its associated l diesel generator on standby status. The switchyard voltage must be returned to 219KY within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Switchyard j voltage above 219KV will allow unrestricted plant operation.
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l Proposed Amendment No. 135 l 3-42 l
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