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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 ML20044F1091993-05-14014 May 1993 Proposed Permanently Defueled TS Section D6.0 Re Administrative Controls ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20042F5091990-04-30030 April 1990 Proposed Tech Specs Re long-term Defueling ML20034A2741990-04-12012 April 1990 Proposed Tech Specs Re Hpi,Chemical Addition & Low Temp Overpressure Protection Sys 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 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 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 ML20236U0821987-11-25025 November 1987 Proposed Tech Specs,Consisting of Suppl 1 to Rev 0 to Proposed Amend 164 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 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 1993-05-14
[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 ML20044F1091993-05-14014 May 1993 Proposed Permanently Defueled TS Section D6.0 Re Administrative Controls ML20127N3671993-01-19019 January 1993 Proposed Tech Specs Section D6.0,administrative Controls for Proposed Amend 186 ML20012G6061992-12-31031 December 1992 Rev 3 to Odcm ML20059E0191990-08-0303 August 1990 Rev 0 to CAP-0002, Odcm ML20043A0881990-04-30030 April 1990 Rev 1 to CAP-0002, Odcm ML20042F5091990-04-30030 April 1990 Proposed Tech Specs Re long-term Defueling ML20043B2551990-04-26026 April 1990 Rev 0 to Technical Svcs Administrative Procedure TSAP-4400, Environ Qualification Program ML20034A2741990-04-12012 April 1990 Proposed Tech Specs Re Hpi,Chemical Addition & Low Temp Overpressure Protection Sys ML20059E0141990-01-31031 January 1990 Rev 0,App a to CAP-0002, Odcm ML20011E1741990-01-29029 January 1990 Rev 1 to Technical Svcs Administrative Procedure TSAP-4124, Sys Layup Program ML20011E1731990-01-11011 January 1990 Rev 0 to Procedure NDP-039, Sys Required to Support Defueled Mode ML20005E8781989-12-31031 December 1989 Revised Rancho Seco Physical Security Plan,Training Program & Emergency Plan ML20005E3641989-12-28028 December 1989 Rev 1 to CAP-0002, Odcm ML20005E3651989-12-27027 December 1989 Process Control Program ML20005E3621989-12-21021 December 1989 Rev 4 to Radiological Environ Monitoring Program, Incorporating Provisions of Generic Ltr 89-01 in Support of Submittal of Tech Spec Proposed Amend 182 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 ML20005G5121989-06-0707 June 1989 Mgt Rancho Seco Contingency Plan 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 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 ML20245G1941989-02-28028 February 1989 Procurement Engineering Assessment Plan Final Rept 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 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 1997-08-19
[Table view] |
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RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS TABLE OF CONTENTS (Continued)
Section Page I
3.1.6 Leakage 3-12 3.1.7 Moderator Temperatt e Coefficient of Reactivity 3-15 3.1.8 Low Power Physics Testing Restrictions 3-15b 3.1.9 Control Rod Operation 3-16 3.2 HIGH PRESSURE INJECTION, CHEMICAL ADDITION, AND LOW TEMPLRAIURE OVERPRL55URL PROILGi10N (L10P) 5Y51LM5 3-17 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING EMERGENCY COOLING, AND REACTOR BUILDING SPRAY SYSTEMS 3-19 3.4 STEAM AND POWER CONVERSION SYSTEM 3-23 3.5 INSTRUMENTATION SYSTEMS 3-25 3.5.1 Operational Safety Instrumentation 3-25 3.5.2 Control Rod Group and Power Distribution Limits 3-31 3.5.3 Safety Features Actuation System Setpoints 3-34 3.5.4 Incore Instrumentation 3-36
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3.5.5 Accident Monitoring Instrumentation 3-38d 3.6 REACTOR BUILDING 3-39 3.7 AUXILIARY ELECTRICAL SYSTEMS 3-41 3.8 FUEL LOADING AND REFUELING 3-44 84><
3.9 SPENT FUEL POOL 3-46a 3.10 SECONDARY SYSTEM ACTIVITY 3-47 3.11 REACTOR BUILDING POLAR CRANE AND AUXILIARY HOIST 3-49 3.12 SH0CK SUPPRESSORS (SNUBBERS) 3-b1 3.13 AIR FILTER SYSTEMS 3-52 3.14 FIRE SUPPRESSION 3-53 3.14.1 Instrumentation 3-53 3.14.2 Water Systen 3-53 3.14.3 Spray and Sprinkler Systens 3-56
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3.14.4 C0p System 3-56 Anendment No. 22, 64 iii 8712230057 871215 PDR ADDCK 05000312 P
PDR i
I 1
~ RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS l
Limiting Conditions for Operation 80>
3.5.5 ACCIDENT MONITORING INSTRUMENTATION Accident monitoring instrumentation channels shown in table 3.5.5-1
.shall be OPERABLE with their alarm / trip setpoints as shown.
Applicability As shown in Table 3.5.5-1.
Action l
A.
With an accident nonitoring instrument channel less conservative than the setpoints provided in Table 3.5.5-1, declare the channel inoperable.
B.
With less than the minimum number of operable channels, take the ACTION shown in Table 3.5.5-1.
Bases Table 3.5.5-1 lists the operability requirements for the various types of accident monitoring instrumentation that were installed in response to NUREG f.
0737, items II.F.1 and II.F.2.
This new set of equipment meets or exceeds the amount of coverage outlined in Generic Letter No. 83-37, "NUREG-0737 Technical s
Specifications." Most of the instrument parameters in Table 3.5.5-1 are monitored by redundant equipment. However, a failure of any one of the radiation monitors described in items 1, 6, and 7 would place that item in an LCO position and would require action number I.
If the inoperable channel cannot be repaired within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, Action Statement Number I requires that a, pre-planned alternate method of monitoring be initiated.
Operating procedures will be used to control the use of backup radiation equipment.
Amendment No. 80 3-38 d
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS
+
Limiting Conditions for Operation TABLE 3.5.5-1 ACCIDENT HONITORING INSTRUMENTATION OPERABILITY REQUIREMENTS (l) 80>
Total Number Minimua Nuaber Al a rct/ T ri p of Channels of Channels Setpoint Ac ti on Instrument Operable 1.
Containment Area 2
2 12 rad /hr I
High Range Radiation Monitor 2.
Wide Range Con-2 1
N/A II tainment Water (Range Level 0-10 ft) 3.
Containment 2
1
<4 Percent II Ii Conc Hydrogen Analyzer 2
4.
Emergency Sump 2
1 54 Ft. (High III Level Alam on Computer) l 5.
Containment Wide 2
1 N/A II Range Pressure (Range -5 to Monitor / Recorder 180 psig)
)
6.
High Range Noble N/AI2)
I Gas Effluent Monitors (Rarige 10-7 a)
RB Exhaust Stack (3) 1 1
b)
Aux Building Stack 1
1 c)
Radwaste Venti 4}
1 1
7.
Main Steam Lines 2
2
-<10 mr/hr I
Radiation Monitors 8.
Subcooling Margin 2
1 No alarms.
II Monitor Procedural controls in place 9.
Incore Thermocouple 4/ core 2/ core (Range 200 -
III quadrant quadrant 2300 F)
(1)
This Table applies at all times except during cold shutdown or refueling.
(2)
Alarm limits are set according to the Offsite Dose Calculation Manual.
(3) Monitoring of the RB Exhaust Stack is not required when the purge and/or equalizing valves are closed.
I4) Monitoring of the Radwaste Vent is not required when the unit is not operatisig.
Amendment No. 80 3-38e
RANCHO SECO UNIT 1 TECHNICAL SPECIFICATIONS i
Ll' Limiting Conditions for Operation t
80>
Table 3.5.5-1 (Continued)-
Action I.
- With the number of OPERABLE channels less than the Minimum Channels
~ OPERABLE ' requirement, either restore the inoperable Channel ( s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:
1)
Initiate the pre-planned alternate method of monitoring, and 1
l 2)
Prepare and submit a Special Report to the Commission pursuant l
to Specification 6.9.5.0, within 30 days following the event, l
outlining the action taken, the cause of the inoperability, and the corrective action and schedule for implementation.
i II.
a.
With the number of OPERABLE accident monitoring instrumentation channels less than the Total Number of Channels, restore the inoperable channel (s) to OPERABLE status within 30 days, or be in at least HOT SliUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
With the number of OPERABLE accident monitoring instrumentation l
channels less than the Minimum Number of Channels Operable, restore the inoperable channel (s) to OPERABLE status within 7 l
days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
III.
With the number of OPERABLE accident monitoring instrumentation
(.
channels less than the Minimum Number of Channels Operable, restore the inoperable channel (s) to OPERABLE status within 30 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
1 I'
l l
l Amendment No. 80 3-38f I
c
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