Letter Sequence Other |
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Results
Other: ML20072P134, ML20087E615, ML20112J098, ML20136F665, ML20149M290, ML20151B003, ML20154B806, ML20154B813, ML20155E842, ML20195B498, ML20195B548, ML20209F446, ML20210B061, ML20210S419, ML20211P829, ML20214P575, ML20235B009
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MONTHYEARML20072P1341983-07-11011 July 1983 Proposed Tech Spec Changes Assuring Operability of Plant Protective Sys Limiting Conditions for Operation Defining Trip Setpoint Operability Project stage: Other ML20087E6151984-02-17017 February 1984 Rev a to Work Spec WS-93-0004, Reevaluation of Plant Protection Sys Setpoints Project stage: Other ML20087E5941984-03-0909 March 1984 Forwards Rev a to Work Spec WS-93-0004, Reevaluation of Plant Protection Sys Setpoints, as Result of 831027 Agreement to Revise Previous Application for Amend to Tech Specs Project stage: Request ML20112J0981985-03-18018 March 1985 Advises That Setpoint Reevaluation Program & Tech Spec Update Program Adopted.Proposed Amend to License DPR-34 for Plant Protective Sys Setpoints Will Be Submitted on or Before 850501 Project stage: Other ML20209F4231985-06-21021 June 1985 Forwards Application for Amend to License DPR-34,revising Tech Specs Re Limiting Conditions for Operation of Protective Sys Instrument Setpoints & Allowable Values Project stage: Request ML20209F4401985-06-21021 June 1985 Application for Amend to License DPR-34,revising Tech Specs Re Limiting Conditions for Operation of Protective Sys Instrument Setpoints & Allowable Values.Fee Paid Project stage: Request ML20209F4461985-06-21021 June 1985 Proposed Tech Specs Re Limiting Conditions for Operation of Protective Sys Instrument Setpoints & Allowable Values Project stage: Other ML20127P1071985-06-21021 June 1985 Advises That Util 850607 Submittal Re Draft Tech Specs for Control Rod Operability Acceptable Provided That Listed Changes Made.Confirmatory Submittal by Licensee of Revised Draft Tech Specs Should Be Provided Prior to Restart Project stage: Request ML20136F6651985-12-31031 December 1985 Informs of Continuation of Reviews Re Allowable Value & Trip Setpoint.Tech Spec Changes Submitted in .After Acceptable Margin Established Analyses Will Be Performed. Tech Spec Change Request Will Be Submitted by 860401 Project stage: Other ML20137P8021986-01-24024 January 1986 Forwards Draft Safety Evaluation Re 850621 Request to Change Tech Specs on Plant Protection Sys Instrumentation Setpoints.Resubmittal of Proposed Tech Specs to Reflect Acceptable Setpoints Requested within 45 Days Project stage: Draft Approval ML20140F8271986-03-25025 March 1986 Ack Receipt of NRC Re Proposed Tech Spec Change Request for Plant Protective Sys Trip Setpoints.Reevaluation of Basis & Analyses for Setpoint Justification for Fixed Feedwater Flow Low Parameter in Progress Project stage: Request ML20155E8421986-04-14014 April 1986 Advises That Addl Time Required to Fully Integrate Tech Spec Changes Re Plant Protection Sys Setpoints Into Existing Format.Tech Spec Amend Request Will Be Submitted by 860516 Project stage: Other ML20210S3261986-05-15015 May 1986 Forwards Application for Amend to License DPR-34,changing Plant Protective Sys Trip Setpoints & Surveillance Requirements.Summary of Proposed Changes & Comments on Draft SER Also Encl.Fee Paid Project stage: Draft Request ML20210S3291986-05-15015 May 1986 Application for Amend to License DPR-34,changing Plant Protective Sys Trip Setpoints & Surveillance Requirements Project stage: Request ML20210S4191986-05-15015 May 1986 Proposed Tech Specs,Changing Plant Protective Sys Trip Setpoints & Surveillance Requirements Project stage: Other ML20211P8291986-07-18018 July 1986 Ack Receipt of Re Plant Protective Sys Setpoints. Item Under Review w/860930 Target Completion Date Project stage: Other ML20211E0111986-10-16016 October 1986 Forwards Request for Addl Info Re NRC Review of Util Info on Plant Protective Sys Trip Setpoints & Surveillance Requirements Against Draft Safety Evaluation Forwarded on 860124 Project stage: Draft Approval ML20214P5751986-11-26026 November 1986 Recommends That Util Propose Tech Specs Based on Annual Allowable Values Re Plant Protective Sys Trip Setpoints. Response Requested within 60 Days of Ltr Date Project stage: Other ML20210B0611987-04-27027 April 1987 Requests That Submittal of Plant Protective Sys Setpoint Info Be Deferred Until 870831,in Response to NRC . Delay Due to Recent Efforts Focusing on Plant Restart Issues Project stage: Other ML20235A9971987-08-28028 August 1987 Forwards Response to NRC 861016 Request for Addl Info on Util 850621 & 860515 Requests for Amend to Tech Specs Re Trip Setpoints & Operating Requirements.Proposed Tech Specs Also Encl Project stage: Request ML20235B0091987-08-28028 August 1987 Proposed Tech Specs Re Trip Setpoints & Operating Requirements Project stage: Other ML20236V3191987-10-31031 October 1987 Draft Plant Protective Sys Trip Setpoints for Fort St Vrain Nuclear Generating Station, Technical Evaluation Rept Project stage: Draft Other ML20235V8871987-10-31031 October 1987 Draft Plant Protective Sys Trip Setpoints for Fort St Vrain Nuclear Generating Station, Technical Evaluation Rept Project stage: Draft Other ML20235R4161987-10-31031 October 1987 Draft Eg&G Technical Evaluation Rept for Plant Protective Sys Trip Setpoints for Fort St Vrain Nuclear Generating Station Project stage: Draft Other ML20236V2941987-11-25025 November 1987 Forwards Draft EGG-NTA-7289, Plant Protective Sys Trip Setpoints for Fort St Vrain Nuclear Generating Station, Technical Evaluation Rept.Discussion of Encl Draft W/Nrc at 871202 Meeting Proposed ML20237D6921987-12-15015 December 1987 Summary of 871203 Meeting W/Util & Inel Re Protective Sys Setpoints in Tech Specs.List of Meeting Attendees Encl Project stage: Meeting ML20149M2731988-02-0808 February 1988 Forwards Application for Amend to License DPR-34,revising Tech Specs on Plant Protective Sys Trip Setpoints & Operating Requirements Project stage: Request ML20149M2851988-02-0808 February 1988 Application for Amend to License DPR-34,revising Tech Specs Re Plant Protective Sys Trip Setpoints & Operating Requirements Project stage: Request ML20149M2901988-02-0808 February 1988 Proposed Tech Spec Re Plant Protective Sys Trip Setpoint & Operating Requirements Project stage: Other ML20151B0031988-03-31031 March 1988 Technical Evaluation Rept for Plant Protective Sys Trip Setpoints for Fort St Vrain Nuclear Generating Station, Informal Rept Project stage: Other ML20154B8061988-04-28028 April 1988 Forwards Notice of Consideration of Issuance of Amend to License DPR-34 & Opportunity for Hearing Re 880208 Application Concerning Setpoints for Plant Protective Sys Project stage: Other ML20154B8131988-04-28028 April 1988 Notice of Consideration of Issuance of Amend to License DPR-34 & Opportunity for Hearing.Amend Modifies Setpoints Used in Plant Protective Sys Project stage: Other ML20195B4981988-06-0303 June 1988 Forwards Notice of Environ Assessment & Finding of No Significant Impact Re Util 880208 Application Concerning Setpoints for Plant Protective Sys Project stage: Other ML20195B5481988-06-0303 June 1988 Notice of Environ Assessment & Finding of No Significant Impact Re Util 880208 Proposed Revised Setpoints for Plant Protective Sys to Allow for Administrative Errors.Commission Has Decided Not to Prepare EIS Project stage: Other ML20151A9881988-06-20020 June 1988 Forwards Amend 60 to License DPR-34,safety Evaluation & Technical Evaluation Rept EGG-NTA-7289.Amend Revises Setpoints for Plant Protective Sys to Allow for Instrumentation Error Project stage: Approval 1986-05-15
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7811989-09-14014 September 1989 Proposed Tech Specs,Documenting Design Features for Defueling Phase of Operation ML20247L1721989-09-14014 September 1989 Proposed Tech Specs Re Reactivity Control ML20247J2371989-09-14014 September 1989 Proposed Tech Specs Re Fuel Handling & Storage ML20247G7341989-09-14014 September 1989 Proposed Tech Specs Deleting Fire Protection Limiting Condition of Operation & Surveillance Requirements from Tech Specs ML20246K9921989-07-14014 July 1989 Proposed Tech Specs Documenting Improvements to Battery Surveillance Procedures ML20246L0231989-07-14014 July 1989 Proposed Tech Specs,Rewording Basis for Limiting Condition for Operation 4.2.2 Re Operable Circulator ML20244B3771989-06-0909 June 1989 Proposed Tech Specs Re Early Shutdown of Plant ML20245B3211989-04-14014 April 1989 Proposed Tech Specs Re Radiation Monitors & Noble Gas Monitors ML20155J6281988-10-14014 October 1988 Proposed Tech Specs Concerning Administrative Controls ML20155J6111988-10-14014 October 1988 Proposed Tech Specs Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E8171988-10-13013 October 1988 Proposed Tech Specs Re Linear channel-high Neutron Flux Trip Setpoints ML20207E1591988-08-0505 August 1988 Proposed Tech Specs Re Auxiliary Electric Sys Involving Proposed Change of Dc Batteries ML20155J7181988-06-14014 June 1988 Revised Draft Tech Specs 3/4.6.5.2,deleting Charcoal Filter Test Exceptions After Painting W/Low Solvent paints,6.5.1.2 & 6.2.3.3,reflecting Recent Util Reorganization & 3/4.7.1.5 & 3/4.7.1.6,requiring One Operable Valve Per Loop ML20151R8191988-04-20020 April 1988 Proposed Tech Specs,Deleting 10CFR51.5(b)2 ML20151S2471988-04-20020 April 1988 Proposed Tech Spec Pages 4.6-4 & 4.6-8,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery ML20148N2751988-03-29029 March 1988 Proposed Tech Specs,Deleting Requirement to Monitor Ambient Temp in Instrument Penetrations Housing Flow Sensors for Dewpoint Moisture Monitoring Sys ML20149M2901988-02-0808 February 1988 Proposed Tech Spec Re Plant Protective Sys Trip Setpoint & Operating Requirements ML20149N0391988-02-0505 February 1988 Proposed Tech Specs Re Changes to Administrative Controls to Reflect Organizational Changes in Util & NRC ML20238C3481987-12-23023 December 1987 Proposed re-drafted Tech Specs,Upgrading Sections Re safety- Related Cooling Sys.Related Info Encl ML20236C6361987-10-15015 October 1987 Proposed Tech Specs,Deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements ML20235W8611987-10-0101 October 1987 Proposed Tech Specs,Clarifying Actions on Inoperable Halogen or Particulate Monitors & Conditions Requiring Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20235B0091987-08-28028 August 1987 Proposed Tech Specs Re Trip Setpoints & Operating Requirements ML20216H7301987-06-25025 June 1987 Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp ML20210B7081987-04-23023 April 1987 Proposed Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys Parameters ML20206P3931987-04-0808 April 1987 Proposed Tech Specs,Revising 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserve Shutdown Sys,Per Rev 4 to FSAR, Section 3.5.3.3 ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs ML20207D2421986-12-23023 December 1986 Proposed Tech Specs Deleting Snubber Tables & Correcting Typos ML20212A0661986-12-19019 December 1986 Proposed Tech Specs Re Steam Line Rupture Detection/ Isolation Sys 1996-02-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation. ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys 1997-06-17
[Table view] |
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, JUN 2 31983 4.4-1 4.4 INSTRUMENTATION AND CONTROL SYSTEMS - LIMITING CONDIT0NS FOR OPERATION Applicability Applies to the plant protective system and other critical instrumentation and controls.
Objective To assure the operability of the plant protective system, and other critical instrumentation by defining the minimum operable instrument channels and trip settings.
Specification LC0 4/4/1 - Plant Protective System Instrumentation, Limiting Conditions for Operation The limiting conditions for the plant protective system instrumentation are shown on Tables 4.4-1 through 4,4-8.
The plant protection system instrumentation shown in Tables 4.4-1 through 4.4-4 shall be Operable with their trip setpoints set consistent with the values shown in the Trip Setpoint column. With a plant protection system instrument channel trip setpoint less conservative than the value of the Allowable Value column of Tables 4.4-1 through 4.4-4, declare the channel inoperable and apply the applicable Action requirement of Tables 4.4-5 through 4.4-8 until the channel is restored to operable status with the trip setpoint adjusted consistent with the Trip Setpoint value for that channel.
Compliance with the Limiting Conditions for Operation contained in the Tables 4.4-1 through 4.4-8 is required during the Operational Modes or other conditions specified therein; except that upon failure to meet the Limiting Conditions for Operation, the associated Action requirements shall be met.
Noncompliance with a Specification shall exist when the requirements of the Limiting Condition for Operation and associated Action requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the Action requirements is not required.
8307180276 830711 PDR ADOCK 05000267 P PDR
4.4-2 When a Limiting Condition for Operation is not met, except as provided in the associated Action requirements, within one hour action shall be initiated to place the unit in a Mode in which the Specification does not apply or by the following actions as applicable:
For Table 4.4-5, the reactor shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
For Table 4.4-6, the affected loop shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
For Table 4.4-7, the affected helium circulator shall be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
For Table 4.4-8, the reactor shall be shut down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Where corrective measures are completed that permit operation under the Action requirements, the Action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Speci fi cation s.
.This Specification is not applicable in Modes 4 or 5.
Entry into an Operational Mode or other specified condition shall not be made unless the conditions for the Limiting Condition for Operation are met without reliance on provisions contained in the Action requirements. This provision
~
shall not prevent passage through or to Operational Modes as required to comply with Action requirements. Exceptions to these requirements are stated in the individual Specifications.
-- m
r-- '
4.4-3 ~
~, .
TABLE 4.4-1 REACTOR SCRAM SYSTEM INSTRUMENTATION SYSTEM SETPOINTS No. Functional Unit Trip Setpoints Allowable Value la. Manual (Control Room) Not Applicable Not Applicable Ib. Manual (Emerency Board) Not Applicable Not Applicable 5 5
- 2. Startup Channel - High j[ (10 ) counts.per second j[ (1.3x10 ) counts per second 3a. Linear Channel - High -< (130) % Rated Thermal --< (132) % Rated Channels 3, 4, 5 Power Thermal Power 3b.. Linear Channel - High ;[ (130) % Rated Thermal j[ (132) % Rated Channels 6, 7, 8 Power Thermal Power
- 4. Primary Coolant Moisture High Level Monitor < (64) F Dewpoint j[(65) F Dewpoint Loop Monitor < (23) F Dewpoint j[ (24) *F Dewpoint
- 5. Reheat Steam Temperature j[(1059) F j[(1063) F
- High
- 6. -Programmed Coolant Pressure See figure 4.4-1 j[ (2) psig below
- Low Trip Setpoint
- 7. Programmed Coolant Pressure See figure 4.4-1 j[ (2) psig above
- High Trip Setpoint e
4.4-4.: ,
' TABLE 3.3.2 ,
REACTOR SCRAM SYSTEM,1NSTRUMENTATION SYSTEM SETPOINTS No.~ Functional Unit Trip Setpoints Allowable Value
- 8. Hot Reheat. Header > (35) psig > (30) psig
-Pressure - Low 9.- Main ~ Steam Pressure - > (1635) psig > (1610) psig Low-
- 10. Plant Electrical > (320) volts for > (310) volts for System - Loss T (28) seconds T (30) seconds
- 11. Two-Loop Trouble Not applicable Not applicable
- 12. High Reactor Building < (175)"F < (185) *F Temperature (Pipe Cavity) 13 Wide Range Channel - -< (4.5) decades / min -< (5) decades / min High Rate of Change Channels 3, 4, 5' 1
4.4-5 Figure-4.4-1 PROGRAMMED COOLANT PRESSURE TRIP SETP0INTS
- Define Programmed Trip Setpoints for Low and High primary coolant pressure as done -in figure 7.1-14 of FSAR.
l-i L- >
L-l _
o g' f 4.4-6 -
TABLE'4.4-2 LOOP SHUTDOWN SYSTEM INSTRUMENTATION SYSTEM SETPOINTS ,
N2 Functional Unit Trip Setpoints Allowable Value-
'la. Steam Pipe _ Rupture.Under -< (8.7) Volts dc -'< (8.9) Volts dc PCRV, Loop 1 lb. Steam Pipe Rupture Under .< (8.7) Volts dc
- -< (8.9) Volts dc PCRV, Loop 2 Ic.. Steam Pipe Rupture North -< (8.7) Volts dc -< (8.9) Volts dc Pipe Cavity, Loop 1
- Id Steam Pipe Rupture, South f (8.7) Volts dc f (8.9) Volts dc
. Pipe _ Cavity, Loop 1 lo. -Steam Pipe Rupture,. North I (8.7) Volts dc I (8.9) Volts dc Pipe Cavity, Loop 2 If. Steam Pipe Rupture, South -< (8.7) Volts dc -< (8.9) Volts dc Pipe Cavity, Loop 2 2a. High Pressure, Pipe 1 (1.5).in W.g. f (2.0) in W.g.
Cavity 2b. High Temperature, Pipe 1 (125) *F 1 (127) F Cavity 2c. High Pressure, Under < (1.5) in W.g. 1 (2.0) in W.g.
PCRV 2d . .- High Temperature, Under I (125) F 1 (127) *F PCRV 3a. (See Table 4.4-3)
. 3 b . _- (See Table 4.4-3)
4.4-7 TABLE 4.4-2 (continued)
LOOP SHUTDOWN SYSTEM INSTRUMENTATION SYSTEM SETPOINTS -
flot. Functional Unit Trip Setpoints Allowable Value 4a. . . Circulator 1A and IB Not Applicable Not Applicable Shutdown - Loop Shut-down Logic 4b. Circulator IC-and ID Not Applicable Not Applicable Shutdown -Loop Shut-down Logic Sa. Steam Generator Pene- j[ (757) psig < (762) psig tration Overpressure,.
Loop 1 Sb. Steam Generator Pene- j[ (757) psig ji(762) psig tration-Overpressure, Loop 2 6a. High Reheat Header j[ (4.5) mr/hr above j[ (5) mr/hr above Activity, Loop 1 background 0 100% background 0 100%
load load 6b. High Reheat' Header -< (4.5) mr/hr above -< (5) mr/hr above Activity, Loop 2 background 0 100% background 0 100%
load load 7a. Low Superheat Header > (815) *F 2,(810) *F .
Tenperature, Loop 1
] 7b. Low Superheat Header 2,(815) F 2,(810) F Temperature, Loop 2 7c. High Differential ;< (47) F j[ (50) *F Temperature Between Loop l and Loop 2
~
4.4-8
~
TABLE 4.4-3 CIRCULATOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS -
fio.. Functional Unit- Trip Setpoints Allowable Value
- 1. Circulator Speed - Low -See figure 4.4-2 j: 75 rpn below
, Trip Setpoint .
2a. Feedwater Flow . Low 2,(10) % 2 (9.5) %
2b. Programmed Feedwater See figure 4.4-2 ~< (3) % below Flow -Low Trip Setpoint
- 3. Loss of Circulator ]L (485) psid 2,(475) psid Bearing Water
- 4. Circulator Penetration j[ (757) psig ;[ (762) psid Trouble 15 . Circulator Drain 2 (8) psid 2,(7) psig Mal function
'E
' 6. Circulator Speed - High j[ (10,700) rpm j( (10,830) rpn (Steam Drive)
- 7. Manual Not Applicable Not Applicable
- 8. Circulator ;[ (75) in H 20 j( (77) in H O2 Seal Malfunction
]; (-6) in H 2O 2, (-5) in H 2O
- 9. Circulator. Speed - j( (8,550) rpm j[ (8,610) rpm High (Water Drive)
4,4-9 1
Figure 4.4-2 PROGRAMMED LOW CIRCULATOR SPEED AND LOW FEEDWATER FL0d TRIP SETPOINTS
' Define Programmed Low Circulator Speed and Low Feedwater-Flow as done in figure 7.1-15 of FSAR.
i 4
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V: e l, , , .. . ,.
,-+ .. . . ~ . , , , . - - ,-,-,.4.-
. . ,, - . - . . , . - . - = , - - - - . _ , - , - , - . . _ - . - , . .
4.4-10
. TABLE 4.4-4 R0D WITHDRAWAL PR0HIBIT SYSTEM lhSTRUMENTATION-TRIP SETPOINTS flot. Functional Unit Trip Setpoints Allowable Value
- 1. Startup Channel - Low 2,(5) cps 2,(4) cps Count Rate 2a. ' Linear Channel - Low 1 (5) % Indicated 1 (7) % Indicated Power RWP, (Channel s Thermal Power Thermal Power 3, 4,'and 5) 2b. Linear Channel - Low < (5) % Indicated
~~ < (7) % Indicated Power RWP (Channels Thermal Power Thermal Power 6, 7, and 8) .
3a.- Linear Channel - High -< (30) % Indicated -< (32) % Indicated Power RWP (Channels Thermal Power Thermal Power 3,_4, and 5) 3b. Linear Channel -High I (30) % Indicated < (32) % Indicated Power RWP (Channels Thermal Power Thermal Power
' 6,.7, and 8) t
4.4-11 -
TABLE 4.4-5 INSTRUMENT OPERATING' REQUIREMENTS FOR PLANT PROTECTIVE SYSTEM, SCRAM ,
Minimum Total No- Channels ^hannels Applicable No ,
Functional' Unit of channels- To Trip Operable ** Modes
- Action la. - Manual (Control Room) ' -1 1 1 1,2,3 1 lb. Manual (Emergency 3 2 2 1,2,3 2 Board) 2.. Startup Channel - High 2 1 2 4, 5 3 3a. Linear Channel - High 3 2 2 1,2,3 4 Channels 3, 4, 5 3b. Linear-Channel - High 3 2 2 1,2,3 '4 Channels 6, 7, 8
- 4. Primary Coolant Moisture ***
High Level Monitor. 2 2 1 2, 3 5 Loop Monitor (Trip is 3 2 2 2, 3 4 coincident with 1 of 2 High Level Monitor) .
- 5. Reheat Steam Temperature 3 2 2 3 4
.High
- 6. Programmed Coolant 3 2 2 3 4 Pressure - Low
- 7. Programmed Coolant 3 2 2 2, 3 4 Pressure - High
- - - - - - - - - - - A
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4.4-12
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1 TABLE 4.4-5 (continued)
INSTRUMENT OPERATING REQUIREMENTS FOR PLANT PROTECTIVE SYSTEM, SCRAM J.
Minimum Total No Channel s Channels Applicable NJ Functional Unit . of channels To Trip Operable ** Modes
- 8. Hot Reheat Header- 3 2 2 3 4 Pressure - Low
- 9. Main Steam Pressure 3 2 2 3 4
- Low
- 10. Plant' Electrical 3 2 2 1,2,3 4 System
. Loss
- 11. Two Loop Trouble 2 1 2 3 6
- 12. High Reactor Building 3 2 2 2, 3 4 Temperature (Pipe Cavity)
- 13. Wide Range Channel 3 2 2 1 3 High Rate of Change Channels 3, 4, 5 1
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4.4-13
-TABLE 4.4 INSTPUMENT OPERATING REQUIREMENTS FOR PLANT PROTECTIVE SYSTEM, LOOP SHUTDOWN -
- Minimum Total No Channel s Channel s Applicable N1 Functional Unit of channels To Trip Operable ** Modes
- Action la. Steam Pipe Rupture 3- 2 2 2, 3 4 Under PCRV, Loop 1-Steam' Pipe Rupture 3 2 2 2, 3 4
' 1b. . Under PCRV, Loop 2 Ic. Steam Pipe Rupture, North 3 2 2 2, 3 4 Pipe Cavity, Loop-1 Id. Steam Pipe Rupture, South 3 2 2 2, 3 4 Pipe Cavity, Loop 2 le. Steam Pipe Rupture, North 3 '2 2 2, 3 4 Pipe Cavity, Loop 2 If Steam Pipe Rupture, South 3 2 2 2, 3 4 Pipe Cavity, Loop 2 2a High Pressure, Pipe 3 2 2 2, 3 4 Cavity
- 2b. High Temperature, Pipe 3 2 2 2, 3 4 Cavity 2c. High Pressure, Under 3 2 -2 2, 3 4 PCRV 2d. High -Temperature, Under 3 2 2 2, 3 4 ,
PCRV m __
4.4-14 *-
TABLE 4.4-6 (continued)
INSTRUMENT OPERATING REQUIREhENTS FOR. PLANT PROTECTIVE SYSTEM, LOOP SHUTDOWN Minimum Total: No Channel s Channel s Applicable fijt- . Functional Unit of channels- To Trip Operable ** Modes
.. 4a . Circulator lA and 18- 2 1 2 2, 3 7 Shutdown - Loop Shut-down Logic 4b. Circulator 1C and 1D 2 1 2 2, 3 7 Shutdown - Loop Shut-down Logic-Sa. . Steam Generator.Pene- 3 2 2 2, 3 4 tration Overpressure, Loo, 1 Sb. Steam Generator Pene- 3 2 2 2, 3 4 tri. ion Overpressure, Loop 2.
6a. High Reheat Header 3 2 2 2, 3 4 Acitvity, Loop 1 6b. High Reheat Header 3 2 2 2, 3 4 Activity,. Loop 2
-7a. Low Superheat Header 3 2 2 3 4
. Temperature, Loop 1 7b. Low Superheat Header 3 2 2 3 4 Temperature, Loop 2 7c. . High Differential 3 2 2 3 4 Temperature Between Loop 1 and Loop 2
4.4-15
.. -1 TABLE 4.4 INSTRUMENT OPERATING REQUIREMENTS FOR PLANT PROTECTIVE SYSTEM, CIRCULATOR TRIP -
Minimum Total No . Channel s Channels Applicable
.No Functional Unit of channels To Trip. Operable ** Modes
- 1. -- -Circulator Speed - 3 2 2 3 4 Low
- 2. Feedwater Flow - 3 2 2 3 4 Low 2b.. Programmed Feed- 3 2 2 3 4 water Flow - Low
- 3. Loss of Circulator 3 2 2 1,2,3 4 Bearing Water
- 4. Circulator Penetration 3 2- 2 2, 3 4 Trouble
- 5. Circulator Drain 3 2 2 1,2,3 4 Mal function 6.- Circulator Speed - 3 2 2 1,2,3 4 High (Steam Drive)
, 7. Manual 1 1 1 1,2,3 4
- 8. Circulator Seal 3 2 2 4 4- Mal function
- 9. Circulator Speed.- 2 1 2 3 7 High (Water Drive)
- 10. Loop Shutdown Logic 2 1 2 3 7 9
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} o TABLE 4.4-8 INSTRUMENT OPERATING REQUIREMENTS FOR REACTOR PROTECTIVE SYSTEM,. ROD WITHDRAWAL' PR0HIBIT (RWP) .
Minimum Total No Channels Channel s ' Applicable No_ Functional Unit of channels To Trip Operable ** Modes *: Action 1.- Startup Channel-- Low- 2 1 2 1 1 Count Rate
' 2a.. Linear Channel - Low 3 2 2 3, 5 2 Power RWP (Channels
- 3. 4, and 5) 2b. Linear Channel - Low 3 2 2 3, 5 2 Po+er RWP ( Channel s 6 7, and 8) 3a. Linear Channel - High 3 2 2 3, 5 3 Power .RWP - (Channel s 3, 4, and 5) 3b. Linear Channel - High 3 2 2 3, 5 3 Power RSP (Channels .
6,.7, and 8)-
h_ "
f 4.4-17 TABLE NOTATION
- - Applicable Modes are defined with the Reactor Mode Switch in the run position and by the following positions of the Interlock Sequence Switch:
1 - STARTUP 2 - LOW POWER 3 - POWER OPERATION or the following positions of the Reactor Modes Switch 4 REFUELING 5 - 0FF 6 - RUN For programmed trip functions, a channel is inoperable when the channel which provides the programmed trip setpoint is inoper- .
able. Action statements apply when any part of the trip channel is inoperable, i
- For a primary coolant dew point moisture monitor to be considered operable, the following conditions shall be met.
- 1) Indicated Reactor Power Minimum sample flow Startup to 2% 1 scc /sec.
- . >2% - 5% 5 scc /sec.
>5% - 20% 15 scc /sec.
>20% - 35% 30 scc /sec.
>35% - 100% 50 scc /sec.
- 2) Min'imum flow of item 1) is alarmed in the control room and the alarm is set in accordance with the power ranges specified.
- 3) The ambient temperatures indicated by both temporary thermo-
, couples mounted on the flow sensors in penetrations 81 and 83 are less than 185*F.
- 4) Fixed alarms of l' scc /sec and 75 scc /sec are operable.
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- 4.4-18 ACTION STATEMENTS ACTION 1 - With the number of Operable channels one less than the Minimum Channels Operable requirement, restore the inoperable channel to Operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
ACTION 2 - With the number of Operable channels one less than the Total No.
of Channels restore the inoperable channel 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 place the inoperable channel in the tripped condition.
ACTION 3 - With the number of Operable channels one less than the Minimum Channels Operable requirement suspend all operations involving positive reactivity changes.
ACTION 4 - With the number of Operable channels one less than the Total No.
of Channels, Startup Low Power, and/or Power Operation may pro-ceed provided the following conditions are satisfied:
- a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />,
- b. The Minimum Channels Operable requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specifica-tion SR 5.4.1.
ACTION 5 - With'the number of Operable channels one less than the Total No.
of Channels, Startup, Low Power, and/or Power Operation may pro-ceed provided the inoperable channel is placed in the tripped conditition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
ACTION 6 - With the number of Operable channels one less than the Minimum Channels Operable requirement, restore the inoperable channel to Operable status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
ACTION 7 - With the number of Operable channels one less than the Minimum Channels Operable requirement, restore the inoperable channel to Operable status within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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The following statements should be added to Specification SR 5.4.1:
Surveillance Requirements shall be met during the Operational Modes or other conditions specified for individual Limiting Conditions for Operation in Tables 4.4-1 through 4.4-8 unless otherwise stated in an individual SLrveil-lance Requirement.
Each Surveillance Requirement shall be performed within the specified time interval with:
- a. A maximum allowable extension not to exceed 25% of the surveil-lance interval, but
- b. The combined time interval for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval.
Failure to perform a Surveillance Requirement within the specified time interval shall constitute a failure to meet the Operability requirements for a Limiting Condition for Operation. Exceptions to these requirements are stated in the individual Specifications. Surveillance Requirements do not have to be performed on inoperable equipment. -
Entry into Operational Mode or other specified condition shall not be made unless the Surveillance Requirement (s) associated with the Limiting Con-dition for Operation have been performed within the stated surveillance interval or as otherwise specified.
The Note 1 for Tables 5.4-1 through 5.4-4 should be changed to read:
D - Daily (i.e., delete "when in use"). This is more explicitly defined by the first paragraph above.
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