Letter Sequence Other |
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MONTHYEARML20134D5231985-08-0101 August 1985 Proposed Tech Spec Changes Re Operability of Fire Detection Instrumentation Project stage: Other ML20134D5191985-08-0101 August 1985 Application to Amend License DPR-54,upgrading Existing Tech Specs for Compliance W/App R Requirements & Providing Addl Tech Specs Re Fire Protection Features.Safety Analysis & NSHC Determination Encl Project stage: Request ML20137L2221985-11-25025 November 1985 Rev 1 to Proposed Amend 137,changing Tech Specs to Add Water Deluge Sys in Area of Auxiliary Feedwater Pumps Project stage: Other ML20137L1991985-11-25025 November 1985 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 137,adding Water Deluge Sys in Area of Auxiliary Feedwater Pumps,Per Discussion at 850206 Meeting on Fire Protection Project stage: Meeting ML20153E5241986-02-20020 February 1986 Proposed Tech Spec Table 3.14-2,adding Water Suppression Zone 110 to Auxiliary Feedwater Pump Project stage: Other ML20153E5171986-02-20020 February 1986 Application for Amend to License DPR-54,consisting of Suppl 1 to 850801 & 1125 Proposed Amend 137,Rev 1.Suppl Revises Tech Specs to Include Addl Water Suppression Zone 110 to Table 3.14-2 Per 10CFR50,App R.Safety Analysis Encl Project stage: Request ML20207Q6381986-12-24024 December 1986 Proposed Tech Specs Adding Water Suppression Zone 104 to Table 3.14-2 Per 10CFR50,App R Project stage: Other ML20207Q6281986-12-24024 December 1986 Rev 1,Supplement 2 to Application for Amend 137 to License DPR-54,revising Tech Specs to Include Water Suppression Zone 104 on Table 3.14-2 Per 10CFR50,App R.Safety Analysis & No Significant Hazards Evaluation Encl Project stage: Supplement ML20238B0441987-08-27027 August 1987 Forwards Amend 85 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Include Fire Protection Components in Auxiliary,Turbine & Svc Nuclear Electrical Bldgs & Clarifies Requirements on Fire Barriers Project stage: Approval 1986-12-24
[Table View] |
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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 !
l
' TABLE OF-CONTENTS (Continued) I 2'Section Page 137> 3.14.5 Fire Hose Stations 3-56a
-- < 3.14.6 Fire Rated Assemblies 3-58
'3.15 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION 3-60 3.16 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 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 RADI0 ACTIVE WASTES 3-80 3.22 RADIOLOGICAL ENVIRONMENTAL MONITORING 3-81 3.23 LAND USE CENSUS- 3-87 3.24' EXPLOSIVE GAS MIXTURE 3-89 l l
3.25 FUEL CYCLE DOSE 3-90 3.26 INTERLABORATORY COMPARIS0N PROGRAM 3-92 '
l-L-
[.- I 1
I Proposed Amendment No. 137, Rev. 1 iv "8512030387'851125 i PDR ADOCK 05000312 PDR l P_ -
+ -
- - , . - g- y m -
n,- v n p- aee---a
.. ~
RANCHO SECO UNIT 1 i F TECHNICAL SPECIFICATIONS LIST OF TABLES Table Page l 2.3-1 -REACTOR' PROTECTION SYSTEM TRIP SETTING LIMITS 2-9 3.5.1-1 ' INSTRUMENTS OPERATING CONDITIONS 3-27
^
3.6-1 . SAFETY FEATURES CONTAINMENT ISOLATION VALVES 3-40 l
- 3. 7-l' YOLTAGE PROTECTION SYSTEM RELAY TRIP VALUES 3-41a 3.7 ' VOLTAGE PROTECTION SYSTEM LIMITING CONDITIONS 3-41b 4
3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS 3-55 137V .3.14-2 WATER SUPPRESSION ZONES ~ 3-56b,c 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES 3-56d,e
< . 3.14-4 FIRE HOSE STATIONS 3-57a,b 3.15-1 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 3-61
-3.16-1 RADI0 ACTIVE GASES EFFLUENT MONITORING INSTRUMENTATION 3 3.22-1: RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 3-83 3.22-2 REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS 3-86
. IN ENVIRONMENTAL SAMPLES'
- 4.1-1 INSTRUMENT SURVEILLANCE 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 WITHDRAWAL SCHEDULE AT DAVIS-BESSE 1 4-12b
'4.14-1 SNUBBERS ACCESSIBLE DURING POWER OPERATIONS 4-47c 4.17-1 MINIMUM NUMBER OF STEAM GENERATORS TO BEL 4-56 INSPECTED DURING INSERVICE-INSPECTION
- 4.17-2A STEAM GENERATOR ~ TUBE INSPECTION- 4-57
[ 4.17-28 ' STEAM GENERATOR TUBE INSPECTION (SPECIFIC LIMITED AREA) 4-57a U
. 4.17-3. OTSG AUXILIARY FEEDWATER. HEADER SURVEILLANCE 4-57b, !
4-57c i- 4'.19-1 , RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 4-64 1 SURVEILLANCE REQUIREMENTS ~
!~ 4.20-1 RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 4-66
-SURVEILLANCE REQUIREMENTS
, Proposed Amendment No. 137, Rev. l' iX
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation ,
3.14.2.1 (Continued) )
I
- b. Two separate water supplies containing a minimum of 2,000,000 l gallons each.
- c. An OPERABLE flow path capable of taking suction from the circulating water system and the Site Reservoir or the Folsom South P.nal and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation ,
valves to the yard hydrant curb valves, the last valve ahead '
of the water flow alarm hvice on each sprinkler or hose standpipe, and the last valve ahead of the deluge valve on each deluge or spray system required to be OPERABLE per Specifications 3.14.3.1 and 3.14.5.
3.14.2.2 With one pump and/or one water supply inoperable, restore the inoperable equipment to OPERABLE status within 7 days or, in lieu 137>< of any other report required by Specification 6.9, prepare and .
submit a Special Report to the Commission pursuant to 137>< Specification 6.9.5.E within the next 30 days outlining the plans and procedures to be used to restore the inoperable equipment to OPERABLE status or to provide an alternate backup pump of supply.
3.14.2.3 With no fire suppression water system OPERABLE:
- a. Establish a backup fire suppression water system equivalent to Specification 3.14.2.1 within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
- b. In lieu of any other report required by Specification 6.9, submit a Special Report in accordance with Specification 6.9.5.E:
- 1) By telephone within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- 2) Confinned by telegraph, mailgram of facsimile transmission no later than the first working day following the event, and c.
~
In writing within 14 days following the event, outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
d.. If a. above cannot be fulfilled, place the reactor in Hot Standby within the next six (6) hours and cold shutdown within the following thirty (30) hours.
I l
l Propc:cd Ame@nt No.137, Rev. 1 3-54
, n.. , ,, , , , - - . , , , . . _ - - .
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS ~
Limiting Conditions for Operation TABLE 3.14-1 FIRE DETECTION INSTRUMENTS FOR SAFETY SYSTEMS. (Continued).
Detection Number of detectors in zones-Zone' Instrument Location All Required to be OPERABLE
- Heat Flame Smoke l
87 NSEB Computer Room B 0 0 5 89 NSEB Computer Room A 0 0 5 104 . Technical Support Center. 0 0 15 109 Chemical Lab Area - 0 0 19 Auxiliary Building 4
- 137>< 110-- Auxiliary Feedwater Pump Area 0 4 ,
0 l
l l
4 t
l Propo' sed Amendment No. 137, Rev. 1 3-55c l
'^
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
' Limiting Conditions for Operation l
- 137>< -Table 3.14-2
, WATER SUPPRESSION ZONES ZONES AREAS
- 137> .3 Control Room - Turbine Deck, Auxiliary Building 5 South East Uncontaminated Area - Turbine Deck, Auxiliary Building 6 North West' Uncontaminated Area - Turbine Deck, Auxiliary Building 7- ~ Contaminated Area - Turbine Deck, Auxiliary Building ,
10 Mezzanine Level - Turbine Building 18 Air Condition Equipment Room - Mezzanine Levels ;
Auxiliary Building 19 Communication Room - Mezzanine Level, Auxiliary Building l 20 Electrical Penetration Room - Mezzanine Level, Auxiliary
- Building
- - 31 Auxiliary Lube Oil Area - Grade Level, Turbine Building 32 Main Lube Oil - Grade Level, Turbine Building 33 Hydrogen Seal Oil Unit j ,
~34 Heater !iater Pump Area - Grade Level, Turbine Building
.35 Main. Feed Pump Area 1
< 40 North Diesel Generator Room - Grade Level, Auxiliary
< Building l
l Proposed Amendment No.137, 'Rev.1 ~
3-56b
, . a..-.._-.-.--- . . = . - - .
RANCHO SECO UNIT 1 '
TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.14-2 WATER SUPPRESSION ZONES (Continued) l ZONES AREAS 137> 41 South Diesel Generator Room - Grade Level, Auxiliary Buf1 ding 42 Electrical Penetration Room, Grade Level, Auxiliary Building 1
43 Chemical Mix Area - Grade Level, Auxiliary Building 46 Hut Area:- Basement Level, Auxiliary Building
~
47 Pipe Penetration Area - Basement Level, Auxiliary Building 81 NSEB B Cable Shaft 82 NSEB A Cable Shaft 83 NSEB Corridor,1 foot Level 84 NSEB Corridor, 21 feet Level 85 .NSEB Corridor, 40 feet Level 37 NSEB Computer Room B
<- 89 NSEB Computer Room A fi Proposed Amendment No. 13i, Rev. 1 3-56c i T f
a _ .-- --. - ,- .m m., . -.,, r. . , -
, _ , . , r , . . . . _ - .- _ , . - . ~ - - . , . . , . _ ._.
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation !
Table 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES ZONES AREAS
-137 ' + 11 West Battery Room - Mezzanine Level, Auxiliary Building 12 West Battery Charger Room - Mezzanine Level, Auxiliary Building 13 West 480V Switchgear Room - Mezzanine Level, Auxiliary Building 14 West Cable ~ Shaft - Auxiliary Building 15 East Cable Shaft - Auxiliary Building i 16 East 480V Switchgear Room - Mezzanine Level, Auxiliary
- Building-17 East Battery Charger Room - Mezzanine Level, Auxiliary Building 19 Communication Room - Mezzanine Level, Auxiliary Building.
36 West Nuclear Battery Room -' Grade Level, Auxiliary Building 37 West 4160 Y Switchgear Room - Grade Level, Auxiliary Building 38 East 4160 Y Swit:hgear Room - Grade Level, Auxiliary Building 39 East Nuclear Battery Room - Grade Level, Auxiliary Building.
'40 ' North Diesel Generator Room - Grade Level, Auxiliary e Building J
l
[
Proposed Amendment No. 137, Rev. 1 l 3-56d i
. - . _ . ._ _ - .- ._, ~ . . _ . - - _ _ . . _ . _ . _ . _ _
- o. .e.
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Limiting Conditions for Operation Table 3.14-3 CARBON DIOXIDE SUPPRESSION ZONES, Continued ZONES AREAS
~
137- + 41 South Diesel Generator Room - Grade Level, Auxiliary Building 53-54 Turbine Area 75 NSEB Switchgear Room B 76 NSEB Switchgear Room A
^
77 NSEB B Electrical: Equipment 78 NSEB A Electrical Equipment l 79 NSEB Battery GB
+ 80 NSEB Battery GA Proposed Amendment No.137, Rev.1 3-56e
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Surveillance Standards
- a. Once per 31 days by visual inspection of the station to assure all equipment is available at the station.
- b. Once per 18 months inspect and replace all gaskets in the couplings that are degraded, and remove the hose for
, inspection and re-racking.
4
- c. Once per three (3) years, partially open hose station valves to verify valve operability and no valve blockage.
- d. Once per three (3) years by removing and replacing all hose with new hose that meets or exceeds NFPA guidelines or recommendations.
137>< 4.18.6 Fire Rated Assembifes' 4.18.6.1 Each of the fire rated assemblies specified in Section 3.14.6.1 shall be verified to be functional:
- a. At least once per 18 months by a visual inspection.
- b. Prior to returning a fire rated assembly to functional status following repairs or maintenance by performance of a visual inspection of the affected fire rated assembly (s).
Proposed Amendment No. 137, Rev. 1 4-62 0
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS Administrative Controls Special Reports 6.9.5 Special reports shall be submitted to the Director of the Regulatory Operations Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
A. A one-time only, " Narrative Summary of Operating Experience" will be submitted to cover the transition period (calendar year 1977).
B. A Reactor Building structural integrity report shall be submitted within ninety (90) days of completion of each of the following tests covered by Technical Specification 4.4.2 (the integrated leak rate test is covered in Technical
< Specification 4.4.1.1).
- 1. Annual Inspection
!~
- 2. Tendon Stress Surveillance
- 3. End Anchorage Concrete Surveillance
- 4. Liner Plate Surveillance C. In-Service Inspection Program x '
D. Reserved for Proposed Amendment No. 43 137k- E. Status of Inoperable Fire Protection Equipment 30 days (3.14.1.2, 3.14.2.2, 3.14.3.2, 3.14.2.3, 3.14.5.2, 3.14.4.2, i -4 3.14.6.2)
F. Reserved for Proposed Amendment 125 G. Radioactive Liquid Effluent Dose 30 days (3.17.2)
H. Noble Gas Limits 30 days (3.18.2)
, I. Radio-Iodine and Particulates 30 days (3.18.3)
I Proposed Amendment No.137
, 6-12f s