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MONTHYEARML20235B6411987-06-29029 June 1987 Proposed Tech Specs,Adding Requirements for Operability of Meteorological Monitoring Instrumentation Project stage: Other ML20235B6001987-06-29029 June 1987 Application for Amend 160 to License DPR-54,adding Tech Specs for Min Meteorological Instrumentation Required for Emergency Response Purposes Per Suppl 1 NUREG-0737 & Reg Guide 1.97.Fee Paid Project stage: Request ML20245C7541987-10-27027 October 1987 Forwards Amend 88 to License DPR-54 & Safety Evaluation. Amend Adds New Tech Spec 3.29, Meteorological Monitoring Instrumentation, Per 870629 Application Project stage: Approval 1987-10-27
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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
[Table view] |
Text
RANCHO SECO UNIT 1 -
TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)
Page Section Fire Hose Stations 3 57 3.14.5 3.14.6 Fire Barrier Penetration Fire Seals 3-58 3-60 53> 3.15 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-63 3.16 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3-70 3.17 LIQUID EFFLUENTS Concentration 3-70 3.17.1 3-71 9
3.17.2 Dose 3.17.3 Liquid Holdup Tanks 3-72 3-73 3.18 GASEOUS EFFLUENTS Dose Rate 3-73 3.18.1 Noble Gases 3-74 3.18.2
~
3.18.3 Iodine-131. Tritium'and Radionuclides in Particulate Form 3-75 3-78 3.19 GASEOUS RADWASTE TREATMENT 3-79 3.20 GAS STORAGE TANKS 3-80 3.21 SOLID RADI0 ACTIVE WASTES 3 81 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-87 3.23 LAND USE CENSUS 3.24 EXPLOSIVE GAS MIXTURE 3-89 3-90 3.25 FUEL CYCLE. DOSE 3-92
< 3.26 INTERLABORATORY COMPARISON PROGRAM
. 8707090133 870629 DR ADOCK 05000312 PDR Amendment No. 53 iv O n a.iunt TS.
- RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)
Section Page 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-83 4.27 LAND USE CENSUS 4-86 4.28 EXPLOSIVE GAS MIXTURE 4-87 4.29 FUEL CYCLE DOSE 4-89
- 4. 30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90 68> 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4-91
- VENTILATION AND AIR CONDITIONING 5 DESIGN FEATURES 5-1 5.1 SITE 5-1 5.2 CONTAINMENT 5-2 5.2.1 Reactor Building 5-2 5.2.2 Reactor Building Isolatien System 5-3 5.3 REACTOR 5-4 5.3.1 Reactor Core 5-4 5.3.2 Reactor Coolant System 5-4 5.4 -
NEW AND SPENT FUEL STORAGE FACILITIES 5-o 5.4.1 New Fuel Inspection and Temporary Storage Rack 5-6 5.4.2 New and Spent Fuel Storage Racks and Failec 5-6 Fuel Storage Container Rack 5.4.3 New and Spent Fuel Temporary Storage 5-6 5.4.4 Spent Fuel Pool and Storage Rack Design 5-6 l
Amendment No. 68 ,,
v11
() R I 6i u n t I. S.
- RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS 4
... LIST OF TABLES Page Table, 2.3-1. REACTOR PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 80 s '3.5.'5-1 ACCIDENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 3-38b 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b i 3.12-1 SAFETY RELATED HYDRAULIC SNUBBERS 3-51a-e 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 INSIDE BUILDING FIRE HOSE STATIONS 3-57a 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61
~
3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS 3-86 IN ENVIRONMENTAL SAMPLES 4.1-1 INSTRUMENT SURVEILLANCE REQUIREMENTS 4-3.
4.1-2 MINIMUM EQUI,PMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b 4.10-1 ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-42 4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a 4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY 4-47d,e TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT-PROGRAM .l 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56
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DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57
~
4.17-2B STEAMGENERATdRTUBEINSPECTION(SPECIALLIMITEDAREA) 4-57a 4.17-3 OTSG AUXILIARY FEEDWATER HEATER SURVEILLANCE 4-57b,c 4.19-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREMENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-66 E!RVEILLANCE REQUIREMENTS Amendment No. 80 IX Ow o m_ T S.
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e- ,
. RANCHO SECO UNIT 1 TECHNICAL SPECIFICATI0KS LIST OF TABLES Table .
Page 53> 4.21-1L RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 4-70 4.22-1 RADI0 ACTIVE GASEOUS WASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD) 4-84 4.28-1 EXPLOSIVE GAS MIXTURE INSTRUMENTATION SURVEILLANCE 4-88 REQUIREMENTS ,
4 6.2-1 SHIFT CREW PERSONNEL AND LICENSE REQUIREMENTS 6-2
\
Amendment No. 53 X
()R t LitJ A L b,
-.,- RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS.
TABLE OF CONTENTS (Continued) ;
Section Page 3.14.5 Fire Hose Stations 3-57 3.14.6 . Fire Barrier Penetration Fire Seals 3-58 l 3.15 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-60 3.16 RADIDACTIYEGASEOUSEFFLUENTMONITORINGINSTRUMENTATION' 3-63 3.17 LIQUID EFFLUENTS 3-70 3.17.1 Concentration 3-70 3.17.2 Dose 3-71 3.17.3 Liquid Holdup Tanks 3-72 3.18 GASEOUS EFFLUENTS 3-73 3.18.1 Dose Rate 3-73 3.18.2 Noble Gases 3-74 3.18.3 Iodine-131, Tritium and Radionuclides in Particulate Form 3-75 3.19 GASEOUS RADWASTE TREATMENT 3-78 3.20 GAS STORAGE TANKS 3-79 3.21 SOLID RADIOACTIVE WASTES 3-80 3.22' RADIOLOGICAL ENVIRONMENTAL MONITORING ,
3-81 f 3.23 LAND USE CENSUS 3-87 3.24 EXPL0SIVE GAS MIXTURE 3-89 3.25 ,
FUEL CYCLE DOSE 3-90 1
3.26 INTERLABORATORY C011 PARIS 0N PROGRh4 3-92 i 160><3.29 HETEOROLOGICAL (10NITORING INSTRUMENTATION 3-94 Proposed Amendment No.160 iv
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)
Section Page 4.26 RADIOLOGICAL ENVIRONMENTAL MONITORING 4-83 4.27 LAND USE CENSUS 4-86 4.28 EXPLOSIVE GAS MIXTURE 4-87 4.29 FUEL CYCLE DOSE 4-89 4.30 INTERLABORATORY COMPARISON PROGRAM SURVEILLANCE REQUIREMENT 4-90 4.31 NUCLEAR SERVICE ELECTRICAL BUILDING EMERGENCY HEATING 4-91 VENTILATION AND AIR CONDITIONING 160><4.34 NETER0 LOGICAL MONITORING INSTRUHENTATION 4-93 ,
i 5 DESIGN FEATURES 5-1 5.1 SITE- 5-1 5.2 CONTAINMENT 5-2 1 5.2.1 Reactor Building 5-2 5.2.2 Reactor Building Isolation System 5-3 5.3 REACTOR 5-4 5.3.1 Reactor Core 5-4 5.3.2 Reactor Coolant System 5-4 5.4 NEW AND SPENT FUEL STORAGE FACILITIES 5-6 5.4.1 Nyw Fuel Inspection and Temporary Storage Rack 5-6 5.4.2 New and Spent Fuel Storage Racks and Failed 5-6 Fuel Storage Container Rack 5.4.3 New and Spent Fuel Temporary Storage 5-6 5.4.4 Spent Fuel Pool and Storage Rack Design 5-6 Proposed Amendment No.160 vii
l RANCHO SECO UNIT 1 i TECHNICAL SPECIFICATIONS {
LIST OF TABLES Table Page !
2.3-1 REACTOR PROTECTION SYSTEN TRIP SETTING LIMITS 2-9 :
3.5.1-1 INSTRUMENTS OPERATING CONDITIONS 3-27 3.5.5-1 ACCIDENT MONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS 3-38b 3.6-1 SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 3.7-1 VOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7-2 VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 3.12-1 SAFETY RELATED HYORAULIC SNUBBERS 3-51a-e 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 3.14-2 INSIDE BUILDING FIRE HOSE STATIONS 3-57a 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61 3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3-64 3.22-1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86 IN ENVIRONMENTAL SAMPLES 160>< 3.29-1 METEOROLOGICAL MONITORING INSTRUMENTATION 3-95 4.1-1 INSTRUMENT S'URVEILLANCE REQUIREMENTS 4-3 4.1-2 MINIMUM EQUIPMENT TEST FREQUENCY 4-8 4.1-3 MINIMUM SAMPLING FREQUENCY 4-9 4.2-1 CAPSULE ASSEMBLY WITH0RAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b 4.10-1 ENVIRONMENTAL RADIATION N0 NIT 0' RING PROGRNi 4-42 4.10-2 OPERATIONAL ENVIRONMENTAL RADIATION MONITORING PROGRAM 4-22a 4.14-1 DESIGNATED SAFETY RELATED HYDRAULIC SNUBBERS FUNCTIONALLY 4-47d,e TESTED ONLY AS REQUIRED BY THE SNUBBER SEAL REPLACEMENT PROGRAM 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 4-56 DURING INSERVICE INSPECTION 4.17-2A STEAM GENERATOR TUBE INSPECTION 4-57 4.17-2B STEAM GENERATOR TUBE INSPECTION (SPECIAL LIMITED AREA) 4-57a 4.17-3 OTSG AUXILIARY FEE 0 WATER HEATER SURVEILLANCE 4-57b,c 4.19-1 RADI0 ACTIVE LIQUID EFFLUEWT MONITORING INSTRUMENTATION 4-64 SURVEILLANCE REQUIREHENTS 4.20-1 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 4-66 SURVEILLANCE REQUIREMENTS Proposed Amendment No. 160 ix
RANCHO SECO UNIT 1 ,
TECHNICAL SPECIFICATIONS LIST OF TABLES j Table Page i 4.21-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM 4-70 4.22-1 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM 4-75 4.26-1 MAXIMUMVALU5SFORTHELOWERLIMITSOFDETECTION(LLD) 4-84 4.28-1 EXPLOSIVE GAS MIXTURE INSTRUMENTATION SURVEILLANCE 4-88 REQUIREMENTS 160 x 4.34-1 METER 0 LOGICAL MONITORING INSTRUMENTATION 4-94 6.2-1 SHIFT CREW PERSONNEL AND LICENSE REQUIREMENTS 6 l i
Proposed Amendment No.160 x
4
,160> RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS !
l Limiting Condition for Operation-1 i
3.29 Meteorological Monitoring Instrumentation {
The meteorological monitoring instruaentation channels shown in Table 3.29-1 shall be OPERABLE.
Aoolicability At all times. I Action With one or more required meteorological monitoring channels inoperable !
for more than,7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.5 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status and include a description of the event in the next Semiannual Radioactive Effluent Report.
Bases
~"'
' Ths 0PERXB'ICITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the pJblic.
Delta Temperature is obtained from calculated differences between measured air temperaturas at 60 meters and 10 meters. With one or more air ;
temperature monitoring channels inoperable for determining delta temperature, the standard deviation of wind direction (sigma theta) can be used to detennine stability classifications.
Proposed Amendnent No. 160 3-94
160p RANCHO SECO UNIT 1 ;
TECHNICAL SPECIFICATIONS [
Limiting Condition for Operation TABLE 3.29-1 METEOROLOGICAL MONITORING INSTRM4ENTATION MINIMUM TOTAL NUMBER OF NG4BER OF OPERABLE
. INSTRUMENT CHANNELS CHANNELS
- 1. WIND SPEED
- a. Nominal Elev. 10 meters 1 1
- b. Nominal Elev. 60 meters 1 1
- 2. WIND DIRECTION
- a. Nominal Elev. 10 meters 1 1 l
- b. Nominal Elev. 60 meters 1 1
- 3. AIR TEMPERATURE
- a. Nominal Elev. 10 meters 1 1
- b. Nominal Elev. 60 meters 1 1 l
Proposed Amendment No. 160 3-95 7
L
, ., RANCHO SECO UNIT 1 TECitNICAL SPECIFICATION 160>
Surveillance Standards 1
4.34 Meterological Monitoring Instrumentation Surveillance Requirements Each of the above meteorological monitoring instrumentation cha.nnels shall be demonstrated OPERABLE by the performance of an INSTRUMENT CHANNEL CHECX and INSTRUMENT CHANNEL CALIBRATION at the frequencies shown in Table 4.34-1.
Bases:
The OPERABILITY of the meteorological instrumentation ensures that sufficient' '
meteorological data is available for estimating potential radiation doses to I the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
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Proposed Amendment No; 160 4-93
r 1 .- 4, ' ', .- RANCHO SECO UNIT l' TECHNICAL SPECIFICATIONS TABLE 4.34-1
- 160> Surveillance Standards f4ETEOR0 LOGICAL MONITORING INSTRUi4ENTATION
'INSTRUi4ENT -
CHANNEL CHANNEL
' INSTRUi1ENT - CHECK CALIBRATION
- 1. WIND SPEED
- a. Nominal Elev. 10 meters D SY
- b. . Nominal Elev. 60 meters D SY
- 2. WIND DIRECTION
- a. Nominal Eley; 10 meters -D SY
- b. Nominal Elev. 60 meters D SY
- 3. AIR TEl4PERATURE .
- a. Nominal Elev. 10 meters D SY.
- b. _ Neminal Elev. tR) meters D :SY
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Proposed Amendment No.160 4-94