|
---|
Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20211H7881999-08-13013 August 1999 Amend 126 to License DPR-54,changing Permanently Defueled TS (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP (Sfp)Level Alarm Switches with Generic Ref to SFP Level Instrumentation ML20198G8211997-08-22022 August 1997 Amend 125 to License DPR-54,revising TS to Incorporate Revised 10CFR20, Stds for Protection Against Radiation & Amending Refs from NRC Region V to Region IV ML20059G9521990-09-10010 September 1990 Amend 115 to License DPR-54,revising License Condition Re Fire Protection Plan,Adding Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocating Fire Protection Requirements to Fire Protection Plan ML20247B6821989-07-19019 July 1989 Errata to Amends 109,110 & 111 to License DPR-54,correcting Omission of Language ML20247B3461989-07-17017 July 1989 Amend 112 to License DPR-54,revising Tech Specs to Increase Max Closure Time for Selected Containment Isolation Valves & Add 12 Valves to Table 3.6-1 ML20245E1101989-06-20020 June 1989 Amend 111 to License DPR-54,revising Section 2.C.(4) to Remove Requirements for Certain Fire Doors & Dampers ML20245A1901989-06-0909 June 1989 Amend 110 to License DPR-54,revising Tech Specs by Removing Tabular Listing of Snubbers as Suggested by Generic Ltr 84-13 ML20248B6171989-06-0505 June 1989 Amend 108 to License DPR-54,modifying Paragraph 2.C.(3) of License to Require Compliance W/Amended Physical Security Plan ML20248B9311989-06-0505 June 1989 Amend 107 to License DPR-54,removing Requirements for Fire Suppression Sys in Fire Zones 75-80 from Tech Spec 3.14 ML20248B9531989-06-0505 June 1989 Amend 109 to License DPR-54,revising Tech Spec 4.17 Steam Generators & Associated Bases & Tables 4.17-2A & 4.17-2B to Permit Repairs of Steam Generator Tubes by Means of Tube Sleeves ML20247K7121989-05-23023 May 1989 Amend 105 to License DPR-54,clarifying Operational Mode of Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Train & Revising Surveillance Requirements & Frequency of Verifying Auxiliary Feedwater Sys Flow Path ML20247M9071989-05-23023 May 1989 Amend 106 to License DPR-54,revising Tech Spec 4.17, Steam Generators, to Provide for More Extensive Insp of Steam Generator Tubes by Defining Special Tube Areas to Complete 100% Insp Where Degradation Expected ML20247K6811989-05-16016 May 1989 Amend 104 to License DPR-54,deleting Tech Specs Re Reactor Vessel Matl Surveillance ML20245F8931989-04-18018 April 1989 Amend 103 to License DPR-54,revising Tech Specs by Changing Air Flow Rate Through Reactor Bldg Purge Valves,Adding Requirement to Test Reactor Bldg Purge Exhaust HEPA Filters ML20248E9221989-03-29029 March 1989 Amend 102 to License DPR-54,changing Tech Specs to Permit one-time Extension for Certain Local Leak Rate Tests to Cycle 8 Refueling Outage & Revising Surveillance Period for Local Leak Rate Tests on DHR Suction Piping ML20155D3051988-09-28028 September 1988 Amend 100 to License DPR-54,deleting Organizational Charts from Tech Spec Administrative Section ML20151L5331988-07-14014 July 1988 Redistributed Amend 99 to License DPR-54,adding Limiting Conditions of Operation & Surveillance Requirements Re Shunt Trip Attachment Installed at Facility in Response to Generic Ltr 83-28 ML20151B3231988-03-30030 March 1988 Errata to Amends 97 & 98 to License DPR-54,correcting Inadvertent Errors in Tech Specs ML20148J8461988-03-17017 March 1988 Amend 98 to License DPR-54,revising Tech Specs by Reducing Limits of Detection for Liquid Radioactive Effluents & Changing Requirements to Address Hardware Changes in Effluent Sys ML20153B2851988-03-15015 March 1988 Amend 97 to License DPR-54,modifying Various Sections of Tech Specs to More Closely Resemble B&W STS ML20149M8541988-02-19019 February 1988 Amend 96 to License DPR-54,revising Administrative Controls Section of Tech Specs to Reflect Changes in Plant Mgt & Organization ML20149L6911988-02-12012 February 1988 Amend 95 to License DPR-54,revising Tech Specs to Reflect Hardware Mods Associated W/Reactor Bldg Combustible Gas Control.Hydrogen Purge Sys Replaced W/Incontainment Hydrogen Recombiner Sys ML20149L2601988-02-0909 February 1988 Amend 94 to License DPR-54,adding Criteria to Tech Specs to Reflect Addition of Two Diesel Generators & Associated Mods to Facility Emergency Electrical Distribution Sys ML20148C7031988-01-0505 January 1988 Amend 93 to License DPR-54,revising Criteria Re Auxiliary Feedwater Sys & Adding Specific Requirements Associated W/ Emergency Feedwater Instrumentation & Control Sys ML20237B4051987-12-0707 December 1987 Amend 92 to License DPR-54,changing Tech Specs to Redefine Refueling Interval to Make Definition Consistent W/Sts & to Extend Surveillance Interval of Internal Vent Valves to Cycle 8 Refueling ML20236X1761987-12-0202 December 1987 Amend 91 to License DPR-54,revising Operating Criteria for Control Room & Technical Support Ctr HVAC Sys ML20236X1081987-11-13013 November 1987 Amend 90 to License DPR-54,changing Tech Specs 3.2.2 on Low Temp Overpressure Protection & 4.3.1 on Surveillance Requirements for Ventilation Sys in Nuclear Svc Electric Bldg ML20236J2571987-11-0303 November 1987 Amend 89 to License DPR-54,deleting Surveillance Requirements Associated W/Upper Dome Air Circulators in Tech Spec 4.5.2, Reactor Bldg Cooling Sys ML20245C7781987-10-27027 October 1987 Amend 88 to License DPR-54,adding New Tech Spec 3.29, Meteorological Monitoring Instrumentation ML20245C7141987-10-27027 October 1987 Amend 87 to License DPR-54,revising Tech Specs to Make Numerous Administrative Changes to Tech Specs & Bases ML20236G8611987-10-23023 October 1987 Amend 86 to License DPR-54,revising Tech Specs 3.1.6, Leakage & 3.8, Fuel Loading & Refueling Re Requirements for Monitoring Airborne Radioactivity Inside Containment ML20238B0991987-08-27027 August 1987 Amend 85 to License DPR-54,revising Tech Specs to Include Fire Protection Components in Auxiliary,Turbine & Nuclear Svc Electrical Bldgs & Clarifing Requirements on Fire Barriers ML20205T2791987-03-31031 March 1987 Amend 84 to License DPR-54,establishing Limiting Conditions for Operation Based on Spent Fuel Pool (SFP) Water Temp Including Requirements for Use of DHR Sys as Alternate/ Supplemental SFP Cooling Means When SFP Limits Reached ML20210D0851987-02-0303 February 1987 Amend 83 to License DPR-54,revising Tech Specs to Increase Setpoint for Reactor Trip on High Pressure from 2,300 to 2,355 Psig & Arming Threshold for Anticipatory Reactor Trip on Turbine Trip from 20% to 45% Full Power ML20212N4281986-08-13013 August 1986 Amend 82 to License DPR-54,revising Tech Specs to Add Limiting Conditions for Operation & Surveillance Requirements for Low Temp Overpressure Protection Sys ML20211J0781986-04-17017 April 1986 Amend 81 to License DPR-54,changing Tech Specs to Revise Periodic Testing Requirements of Diesel Generators ML20203N5861986-04-14014 April 1986 Amend 80 to License DPR-54,incorporating Tech Spec Changes Per Recommendations Outlined in Generic Ltr 83-37 ML20203N7821986-04-0808 April 1986 Amend 79 to License DPR-54,revising Min Required Boron Concentration in Primary Sys While Loading & Unloading Fuel from Reactor ML20136C5281985-12-24024 December 1985 Amend 77 to License DPR-54,revising Tech Specs to Define Surveillance Requirements for Installed Snubbers ML20136A7271985-12-24024 December 1985 Amend 78 to License DPR-54,revising Tech Specs to Define Requirements for Calibr of power-range Neutron Instrumentation ML20133D1151985-09-30030 September 1985 Amend 76 to License DPR-54,revising Tech Specs to Provide Conformance W/Regulations Governing Inservice Insp & Insp of Steam Generator Tubes Set Forth in 10CFR50.55a(g) ML20135E8671985-09-0909 September 1985 Amend 74 to License DPR-54,revising Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources ML20135F7621985-09-0909 September 1985 Amend 75 to License DPR-54,revising Tech Specs to Define Fire Hose Acceptability & Correct Certain Inconsistencies in Reporting Requirements ML20135F3341985-08-30030 August 1985 Amend 73 to License DPR-54,revising Tech Specs to Change Name of Reactor & Auxiliary Bldg Stacks & Reactor & Radwaste Svc Area Vent to Particulate Samplers ML20133G4401985-07-30030 July 1985 Amend 72 to License DPR-54,revising Tech Specs to Change Closure Times of Several Containment Isolation Valves in Table 3.6-1 & Require Leak Rate Testing of Equipment Hatch & Fuel Transfer Tube Seals After Each Opening ML20126K8171985-07-0303 July 1985 Amend 71 to License DPR-54,revising Pages 3-1,3-2,3-44,3-45 & 3-46 Re Limiting Conditions for Operation to Incorporate Requirements for Redundant DHR Capability During All Modes of Facility Operation ML20127C9721985-06-0707 June 1985 Amend 70 to License DPR-54,changing Tech Specs to Incorporate Design Changes to Control Room/Technical Support Ctr Emergency Filtering & Air Supply Sys ML20126J8661985-06-0404 June 1985 Amend 68 to License DPR-54,defining Operability & Surveillance Requirements for Plant Essential Electrical Sys & Operability Requirements for Components of Fire Protection Sys ML20127B1711985-06-0404 June 1985 Amend 69 to License DPR-54,revising Operating Limits for Cycle 7 Operation ML20129E9771985-05-28028 May 1985 Amend 66 to License DPR-54,changing Tech Specs to Add Surveillance of Certain Special Interest Steam Generator Tubes & Visual Insps of Internal Auxiliary Feedwater Distributor,Attachment Welds & Thermal Sleeves 1999-08-13
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20211H7881999-08-13013 August 1999 Amend 126 to License DPR-54,changing Permanently Defueled TS (PDTS) D3/4.1, Spent Fuel Pool Level, to Replace Specific Reference to SFP (Sfp)Level Alarm Switches with Generic Ref to SFP Level Instrumentation ML20198G8211997-08-22022 August 1997 Amend 125 to License DPR-54,revising TS to Incorporate Revised 10CFR20, Stds for Protection Against Radiation & Amending Refs from NRC Region V to Region IV ML20129E3801996-10-14014 October 1996 Application for Amend to License DPR-54,representing Updated Licensing Basis for Operation of Shutdown Rancho Seco Nuclear Facility During Permanently Defueled Mode ML20058L4281993-12-0909 December 1993 Application for Proposed License Amend 187 to DPR-54 Re Changes Needed to Make PDTS Consistent W/New 10CFR20 Regulations.New 10CFR20 Effective 940101 ML20127N3291993-01-19019 January 1993 Application for Amend to License DPR-54,consisting of Proposed Amend 186,changing Organization & Requests Changes to Permanently Defueled Tech Specs Section D6.0 Administrative Controls Pages ML20059G9521990-09-10010 September 1990 Amend 115 to License DPR-54,revising License Condition Re Fire Protection Plan,Adding Administrative Controls to Tech Specs in Support of Fire Protection Plan & Relocating Fire Protection Requirements to Fire Protection Plan ML20247B6821989-07-19019 July 1989 Errata to Amends 109,110 & 111 to License DPR-54,correcting Omission of Language ML20247B3461989-07-17017 July 1989 Amend 112 to License DPR-54,revising Tech Specs to Increase Max Closure Time for Selected Containment Isolation Valves & Add 12 Valves to Table 3.6-1 ML20246F0991989-07-0505 July 1989 Application for Amend to License DPR-54,resubmitting Rev 1 to Proposed Amend 102,deleting Remaining Nonradiological Items Contained in App B of Tech Specs.Shutdown of Facility on 890607 Makes Submittal of Improved Specs Impractical ML20245E1101989-06-20020 June 1989 Amend 111 to License DPR-54,revising Section 2.C.(4) to Remove Requirements for Certain Fire Doors & Dampers ML20245A1901989-06-0909 June 1989 Amend 110 to License DPR-54,revising Tech Specs by Removing Tabular Listing of Snubbers as Suggested by Generic Ltr 84-13 ML20248B6171989-06-0505 June 1989 Amend 108 to License DPR-54,modifying Paragraph 2.C.(3) of License to Require Compliance W/Amended Physical Security Plan ML20248B9311989-06-0505 June 1989 Amend 107 to License DPR-54,removing Requirements for Fire Suppression Sys in Fire Zones 75-80 from Tech Spec 3.14 ML20248B9531989-06-0505 June 1989 Amend 109 to License DPR-54,revising Tech Spec 4.17 Steam Generators & Associated Bases & Tables 4.17-2A & 4.17-2B to Permit Repairs of Steam Generator Tubes by Means of Tube Sleeves ML20247K7121989-05-23023 May 1989 Amend 105 to License DPR-54,clarifying Operational Mode of Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Train & Revising Surveillance Requirements & Frequency of Verifying Auxiliary Feedwater Sys Flow Path ML20247M9071989-05-23023 May 1989 Amend 106 to License DPR-54,revising Tech Spec 4.17, Steam Generators, to Provide for More Extensive Insp of Steam Generator Tubes by Defining Special Tube Areas to Complete 100% Insp Where Degradation Expected ML20247K6811989-05-16016 May 1989 Amend 104 to License DPR-54,deleting Tech Specs Re Reactor Vessel Matl Surveillance ML20245F8931989-04-18018 April 1989 Amend 103 to License DPR-54,revising Tech Specs by Changing Air Flow Rate Through Reactor Bldg Purge Valves,Adding Requirement to Test Reactor Bldg Purge Exhaust HEPA Filters ML20248E9221989-03-29029 March 1989 Amend 102 to License DPR-54,changing Tech Specs to Permit one-time Extension for Certain Local Leak Rate Tests to Cycle 8 Refueling Outage & Revising Surveillance Period for Local Leak Rate Tests on DHR Suction Piping ML20235Y6011989-03-0606 March 1989 Application for Amend to License DPR-54,consisting of Suppl 1 to Proposed Amend 175,Rev 0,for one-time Extension for Certain Surveillances Required by Tech Specs to Be Performed Beginning 890329 ML20245H8851989-02-28028 February 1989 Rev 1 to Proposed Amend 130 to License DPR-54,adding Operating Requirements to Tech Specs Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation ML20195F7641988-11-18018 November 1988 Rev 1 to 881007 Proposed Amend 170,defining Applicability Requirements of Tech Spec 3.4 W/Respect to Auxiliary Feedwater Sys Flow Paths.Rev Deletes Words to the Condenser from Spec 4.8.1 ML20206F2811988-11-15015 November 1988 Suppl 1 to 880930 Application for Amend 166,Rev 1 to License DPR-54 Revising Tech Spec 4.6.4.f to Ensure Equipment Required to Verify Vital 120 Volt Ac Bus Operability ML20205R8631988-11-0404 November 1988 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 172,withdrawing Request to Delete Reactor Bldg Spray Line Requirements & Justifying Removal of DHR Inlet Lines ML20205M8881988-10-28028 October 1988 Application for Amend 169 to License DPR-54,modifying Nuclear Svc Battery Surveillance Requirements.Fee Paid ML20205L2611988-10-25025 October 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 173,modifying Tech Spec 3.14 to Remove Requirements for Fire Suppression Sys in Fire Zones 75-80. Fee Paid ML20155G2161988-10-0707 October 1988 Application for Amend to License DPR-54,clarifying Operational Mode Applicability of Tech Spec 3.4 & Definition of Auxiliary Feedwater Sys Train.Fee Paid ML20155B8111988-09-30030 September 1988 Application for Rev 1 to Amend 166 to License DPR-54, Revising Tech Specs Re Reactor Protection Sys Trip Setting Limits by Making Editorial Corrections & Technical Changes ML20155B4251988-09-30030 September 1988 Application for Amend to License DPR-54,making Editorial Corrections & Administrative Changes.Fee Paid ML20155D3051988-09-28028 September 1988 Amend 100 to License DPR-54,deleting Organizational Charts from Tech Spec Administrative Section ML20154J5521988-09-19019 September 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 172,changing Local Leak Rate Test Requirements for Containment Penetrations.Fee Paid ML20154D7531988-09-0808 September 1988 Application for Amend to License DPR-54,consisting of Rev 1 to Amend 168,replacing Organization Charts W/More General Administrative Controls CEO-88-024, Supplemental Application for Amend to License DPR-54, Consisting of Rev 1 to Proposed Amend 102,deleting App B of Tech Specs1988-07-27027 July 1988 Supplemental Application for Amend to License DPR-54, Consisting of Rev 1 to Proposed Amend 102,deleting App B of Tech Specs ML20151L5331988-07-14014 July 1988 Redistributed Amend 99 to License DPR-54,adding Limiting Conditions of Operation & Surveillance Requirements Re Shunt Trip Attachment Installed at Facility in Response to Generic Ltr 83-28 CEO-88-002, Application for Proposed Amend 130 to License DPR-54,adding Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation.Fee Paid1988-06-21021 June 1988 Application for Proposed Amend 130 to License DPR-54,adding Operating Requirements Designed to Provide Proper Limitations & Conditions on Reactor Bldg Pressure Equalization Operations During Power Operation.Fee Paid ML20155K0611988-06-14014 June 1988 Rev 0,Suppl 2 to Proposed Amend 159 to License DPR-54,making Minor Corrections to Tech Spec 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 ML20195J4561988-06-10010 June 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 67,reducing Count Time Required for prebatch- Release Sample Analysis.Ser & NSHC Analysis Encl.Fee Paid ML20151B3231988-03-30030 March 1988 Errata to Amends 97 & 98 to License DPR-54,correcting Inadvertent Errors in Tech Specs ML20148J8461988-03-17017 March 1988 Amend 98 to License DPR-54,revising Tech Specs by Reducing Limits of Detection for Liquid Radioactive Effluents & Changing Requirements to Address Hardware Changes in Effluent Sys ML20150D1791988-03-17017 March 1988 Application for Amend to License DPR-54,consisting of Proposed Amend 166,modifying Tech Specs to Correct Typos & Make Further Editorial Changes to Those Submitted in Proposed Amend 139.Fee Paid ML20153B2851988-03-15015 March 1988 Amend 97 to License DPR-54,modifying Various Sections of Tech Specs to More Closely Resemble B&W STS ML20196G5001988-03-0101 March 1988 Application for Amend to License DPR-54,consisting of Suppl 6 to Rev 0 to Amend 164,revising Tech Spec 4.1-1,Item 44.c & Tech Spec 4.10.1.E.2 to State Total Quantity of Gaseous Chlorine in Restricted Area ML20149M8541988-02-19019 February 1988 Amend 96 to License DPR-54,revising Administrative Controls Section of Tech Specs to Reflect Changes in Plant Mgt & Organization ML20149L6911988-02-12012 February 1988 Amend 95 to License DPR-54,revising Tech Specs to Reflect Hardware Mods Associated W/Reactor Bldg Combustible Gas Control.Hydrogen Purge Sys Replaced W/Incontainment Hydrogen Recombiner Sys ML20149K8521988-02-12012 February 1988 Suppl 4 to Rev 2 of Proposed Amend 138 to License DPR-54, Revising Tech Spec 6.5.1.6.d to Identify What Items Do Not Require Plant Review Committee Review ML20196D9001988-02-11011 February 1988 Suppl 1 to Rev 2 to Application for Amend 155 to License DPR-54,adding Term Dewatering to Process Control Program. Description of Changes Encl ML20149L2601988-02-0909 February 1988 Amend 94 to License DPR-54,adding Criteria to Tech Specs to Reflect Addition of Two Diesel Generators & Associated Mods to Facility Emergency Electrical Distribution Sys ML20149G1611988-02-0808 February 1988 Application for Amend to License DPR-54,consisting of Rev 0, Suppl 4 to Proposed Amend 164,adding Note to Tech Spec 3.3 to Eliminate Conflict W/Tech Spec 3.2.2.2 ML20196B7981988-02-0101 February 1988 Application for Proposed Amend 138 to License DPR-54.Amend Revises Nuclear Organization Chart,Figure 6.2-2 as Listed ML20148J3461988-01-13013 January 1988 Application to Amend License DPR-54,consisting of Proposed Amend 165,changing Tech Specs to Add Ventilation Radiation Monitor to Interim Onsite Storage Bldg.Fee Paid 1999-08-13
[Table view] |
Text
.
, f Ce%9
+ ,\ UNITED STATES 8' :s.c 'h NUCLEAR REGULATORY COMMISSION 5
l W ASHING TON, D. C. 20555 k..v...f SACRAMENT 0 MUNICIPAL UTILITY DISTRICT DOCKET N0. 50-312 RANCHO SECO NUCLEAR GENERATING STATION
_ AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 99 License No. OPR-54
- 1. The Nuclear Regulatory Commission (tne Conynission) has found that:
A. The application for amendment by Sacramento Municipal Utility District (the licensee) dated November 8,1985, as supplemented December 9, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I;
- 8. The facility will operate in conformity with the application, the prnvisions of the Act, and the regulations of the Commission; C. i. nee is reasonable assurance (1) that the activities authorized by this amendment can be conducted witi1out endangering the health and safety of the public, and (11) that such activities will be conducted in compliance with the Comissicn's regulations; D. The issuance of this amendment will not be inimical to the conynon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requireraents have been satisfied.
8808040071 880725 DR ADOCK0500g2
~2-
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachmeat to this licence amendment, I and paragraph 2.C.(2) of Facility Operating License No. OPR-54 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No.99 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This Amendment to the Technical Specification shall become effective within 30 days of the issuance date. The implementation delay is provided to allow titre for modification of affected procedures and promulgation of these changes to personnel.
FOR THE NUCLEAR REGULATORY COMMISSION George W. Knighton, Director Project Directorate V Division of Reactor Projects - III, IV, Y and Special Projects Attachmerit: l Changes to the Technical Specifications Date of Issuance: July 14, 1988 l
l l
l
- _ . , , ,.7 , . .. --. _ - -
i ATTACHMENT TO LICENSE AMENDMENT N0.99 FACILITY OPERATING LICENSF NO. DPR-54 DOCKET N0. 50-312 Replace the following pages of the Appendix "A" Technical Specifications j with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 3-25a 3-25a )
l 3-26a 3-26a '
4-4 4-4
. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation 3.5.1.6 Hith one of the Reactor Trip Breaker diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the breaker in trip in the next hour.
3.5.1.7 In the event that both Reactor Trip Breaker diverse trip features fail in the untripped state, the Breaker will be declared inoperable, and the power supplied to the rod drive mechanisms through the failed trip device shall be manually removed within 30 minutes. The condition will be corrected and the remaining trip devices shall be tested within eight hours. If the condition is not corrected and the remaining trip devices are not tested within the eight-hour period, the reactor shall be placed in the hot shutdown condition within an additional four hours.
3.5.1.8 ~he SCR relays for the regulating rods duplicate the trip function of the DC breakers for the safety rods. With the number of OPERABLE SCR relays one less than the total number of SCR relays in a channel, restore the inoperable SCR relay to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the SCRs associated with the inoperable relay in trip in the next hour. With two or more SCR relays inoperable, place all SCR relays associated with that channel in trip in the next hour.
3.5.1.9 The inoperable channel in Sections 3.5.1.6, 3.5.1.7, and 3.5.1.8 may be bypassed for up to 30 minutes in any 24-hour period when necessary for surveillance testing per Specification 4.1.1.
Bale.1 Every reasonable effort will be made to maintain all safety instrumentation in operation. A startup is not permitted unless three power range neutron instrument channels and two channels each of the following are operable:
four reactor coolant temperature instrument channels, four reactor coolant flow instrument channels, four reactor coolant pressure instrument channels, four pressure-temperature instrument channels, four flux-imbalance flow instrument channels, four power-number of pumps instrument channels, and four high reactor building pressure instrument channels. The safety features actuation system must have two analog channels functioning correctly prior to startup. EFIC system instrumentation as required by Table 3.5.1-1 must be operable.
Operation at rated power is. permitted as long as the systems have at least the redundancy requirements of Column B (Table 3.5.1-1). This is in agreement with redundancy and singlo failure criteria of IEEE 279 as described in FSAR section 7.
The four reactor protection channels were provided with key operated maintenance bypass switches interlocked to allow on-line test',ng or maintenance on only one channel at a time during power operation. Each channel is provided alarm and lights to indicate when that channel is bypassed.
Amendment No. 31,87,93, 99 3-25a
' l l
RANCHO SECO UNIT I TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Since the EFIC receives signals from the RPS it is important that only corresponding channels be placed in "maintenance bypass." If a channel of RPS is in maintenance bypass, only the corresponding channel of EFIC can be l bypassed. An interlock feature also prevents bypassing more than one EFIC channel at a time. These interlocking features allow the EFIC system to take a single failure in addition to having one channel in maintenance bypass. ;
Various RPS test features can inhibit initiate signals to the EFIC system and l degrade thb EFIC system below acceptable limits if the RPS channel is not in l bypass. Therefore, no testing should be performed on a RPS instrument string which supplies an output to EFIC without placing that RPS channel in bypass.
The EFIC system is designed to allow testing during power operation. The EFIC system can be tested from its input terminals to the actuated device controllers without placing the channel in key locked "maintenance bypass."
A test of the EFIC trip logic will actuate one of two relays in the ,
controllers. The two relays are tested individually to prevent automatic l actuation of the component. I Each EFIC channel key operated maintenance bypass switch is provided with alarm and lights to indicate when the maintenance bypass switch is being used.
The source range and intermediate range nuclear flux instrumentation scales i overlap by one decade. This decade overlap will be achieved at 10-10 amps j on the intermediate range scale.
Power is normally supplied to the control red drive mechanisms from two separate parallel 480 volt sources. Redundant trip devices are employed in each of these sources. If any one of these trip devices fails in the untripped state, on-line repairs to the failed device, when practical, will !
be made, and the remaining trip devices will be tested. Eight hours is ample I time to test the remaining trip devices and in many cases make on-line repairs. If on-line repairs are not practical, the device will be replaced with a spare or placed in tripped condition in a timely manner.
l Amendment No. 31,93, 99 3-26a
Im RANCHO SECO UNIT 1
~
o TECHNICAL SPECIFICATIONS
@ Surveillance Standards e Table 4.1-1 (Continued)
.D INSTRfmENT SURVEILLANCE REQUIRDENTS Channel Description Check Test Calfbrate Remarks l D
- 8. Reactor coolant pressure /
temperature comparator S M R e
- 9. Power /febalance/ flow comparator 5 M R
, 10. Pump / flux comparator 5 M R
- 11. High Reactor Building Pressure Channels D M R 12a. Protection channel cof ncidence logic NA M MA
- b. ARTS Turbine Trip 5 M R Monf tor Channels i
- e c. ARTS Loss of WW Pumps S M R
'
13a. CRD Trfp Breaker RPS Undervoltage trfp NA M.P NA
- b. RPS Shunt Trfp NA M.P NA
- c. SCR Relays NA M NA i Safety Features Systee
- 14. Emergency core cooling fnjection, emergency butiding cooling and 4 butiding isolation analog channels
- a. Reactor coolant pressure channel S M R i b. Reactor Building
- 4 pstg channel S M R
^
44 l
1
_ . _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ___ _ _ _ _