Letter Sequence Other |
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Results
Other: 05000267/LER-1984-008, Forwards Addl Info Re Three CRDs & Orifice Assemblies That Failed to Scram During in-core back-EMF Testing,Per 850122 Telcon.Suppl to LER 84-008 Will Be Provided, ML20084C589, ML20084Q444, ML20092P626, ML20093K194, ML20094D774, ML20096C032, ML20098B305, ML20099K727, ML20100H112, ML20106B531, ML20106B533, ML20112G463, ML20117M059, ML20126B629, ML20127J822, ML20127K637, ML20127L885, ML20127N695, ML20132C948, ML20132E623, ML20132G502, ML20134E865, ML20138Q922, ML20206J841, ML20209E899
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MONTHYEARML20084C5891984-04-16016 April 1984 Provides Advance Notification of Intent to Propose Tech Spec Changes to Circulation speed-high Trip Setting Listed in Table 4.4-3 & Surveillance Requirement SR 5.3.7 for Secondary Coolant Monitoring Project stage: Other ML20084Q4361984-05-10010 May 1984 Application to Amend License DPR-34,revising Tech Specs to Change Circulator speed-high Steam Trip Setting.Change Would Increase Circulator Availability While Providing for Initiation of Protective Actions Project stage: Request ML20084Q4221984-05-10010 May 1984 Forwards Application to Amend License DPR-34,revising Tech Specs to Change Circulator speed-high Steam Trip Setting (Table 4.4-3).Change Would Increase Circulator Availability While Providing for Initiation of Protective Actions Project stage: Request ML20084Q4441984-05-10010 May 1984 Proposed Tech Spec Table 4.4-3, Instrument Operating Requirements for Plant Protective Sys,Circulator Trip. Significant Hazards Considerations Encl Project stage: Other ML20092P6261984-06-26026 June 1984 Confirms Util Commitment to Fully Investigate 840623 Event in Which Six Control Rod Pairs Failed to Insert Into Core Under Automatic Velocity Limited free-fall Sys.Nrc Approval of Resolutions Will Be Obtained Prior to Reactor Startup Project stage: Other ML20090C5261984-07-0606 July 1984 Responds to NRC Concerns Re Fire Protection Review,Bldg 10 Licensing Requirements,Control Rod Failure to Scram, Documentation of Disciplinary Actions,Clearance Tags & Radiological Emergency Exercise Scenario,Per 840625 Meeting Project stage: Meeting ML20094D7741984-07-18018 July 1984 Informs of Control Rod & CRD Insp & Testing in Response to NRC 840709 Insp.Major Power Consumption & Scram Verification of All 37 CRD & Orifice Assemblies Completed & Insp Underway.Plan for Further Action Described Project stage: Other ML20096C0321984-08-21021 August 1984 Provides Findings & Positions Re Investigation of 840623 Failure of Six Control Rods to Automatically Insert Upon Scram.Summary of Work on Four CRDs & Description of Tests Encl.Corrective Actions Listed Project stage: Other ML20098B3051984-09-0707 September 1984 Ro:On 840904,while Removing CRD & Orifice Assembly,Motor Overcurrent Condition on Auxiliary Transfer Cask Shutters Occurred,Preventing Full Closure.Caused by One Control Rod String Not Fully Retracted.Work Temporarily Discontinued Project stage: Other ML20093K1941984-09-24024 September 1984 Submits Info Re Status of Damaged Control Rod Removal on Fuel Deck.Related Info Encl.Possibly Caused by Absorber Strings Not Fully Retracted,Despite Full Retract Limit Switch Indication Project stage: Other ML20099K7271984-11-0808 November 1984 Provides Status of Control Rod Drive & Orificing Assembly (Crdoa) Refurbishing Efforts.Further Investigation of Crdoa Determined That Cause of Inability of Absorber String to Fully Retract Was Cable Failure Project stage: Other ML20112C0491984-12-27027 December 1984 Responds to NRC 841025 Request for Addl Info Re 840510 Application for Amend to License DPR-34,revising Tech Spec Re Helium Circulators Overspeed Trip Setpoint.Analysis Value Encl Project stage: Request ML20112G5061985-01-0404 January 1985 Forwards Status of Planned Audit Response to NRC July 1984 Audit of Plant Operations,Per Denton .Repts Covering Technical Details of Listed Subjs Will Be Provided by 850131,per 841128 & 29 Meetings Project stage: Meeting ML20106B5311985-01-25025 January 1985 Advises That Util Will Perform Turbine Load Rejection from Full Load Test at End of Cycle 4.Tech Spec Amend Will Be Submitted Project stage: Other 05000267/LER-1984-008, Forwards Addl Info Re Three CRDs & Orifice Assemblies That Failed to Scram During in-core back-EMF Testing,Per 850122 Telcon.Suppl to LER 84-008 Will Be Provided1985-01-28028 January 1985 Forwards Addl Info Re Three CRDs & Orifice Assemblies That Failed to Scram During in-core back-EMF Testing,Per 850122 Telcon.Suppl to LER 84-008 Will Be Provided Project stage: Other ML20106B5331985-01-31031 January 1985 Forwards Investigation Into Sources of Chloride in Fort St Vrain Primary Circuit. Rept Re Investigations of Effects of Chlorides on Major Components in Primary Circuit Will Be Sent by 850228 Project stage: Other ML20132G5021985-03-12012 March 1985 Evaluation of CRD Mechanism & Reserve Shutdown Sys Failures & Pcrv Tendon Degradation Issues Prior to Fort St Vrain Restart Project stage: Other ML20112G4631985-03-18018 March 1985 Forwards Ga Technologies,Inc Rept 907838, Investigation Into Sources of Chloride in Fort St Vrain Primary Circuit, Re Effects of Chloride on Major Components in Primary Circuit.Final Review & Clearance to Be Forwarded by 850326 Project stage: Other ML20100H1121985-03-26026 March 1985 Forwards Evaluation of Fort St Vrain Metallic Components Exposed to Primary Coolant Chloride Contamination, Per 850318 Commitment Project stage: Other ML20117M0591985-04-26026 April 1985 Expresses Appreciation for Opportunity to Discuss Quality Aspects of CRD & Orifice Assembly (Crdoa) Refurbishment Program on 850424 in Arlington,Tx.Discusses 850418 Audit to Confirm 18 Crdoas Completed W/High Quality Project stage: Other ML20132C9781985-05-17017 May 1985 Safety Evaluation Re CRD Instrumentation Project stage: Approval ML20126B6291985-05-20020 May 1985 Responds to Commitment Log Item CL-1055 Re Verification of Operability of Surge Diodes on CRD Brake & Limit Switch Relays.Diodes & Functions Listed.Action Request DCAR-704 Initiated to Provide Relocation of Diodes Project stage: Other ML20127J8221985-06-0707 June 1985 Informs of Acceptability of Devcon 5-minute Epoxy for Use in Cementing Resistance Temp Detector Temp Sensors to CRD Cavity & Motor,Based on Test & Inservice Exposure of Epoxy to High Temps Project stage: Other ML20127K6371985-06-0707 June 1985 Forwards Interim Tech Specs for Control Rods for Use During Plant Startup.Specs Describe Program to Assure Control Rod & Reserve Shutdown Sys Reliability.Operating Limit of 250 F Max on Control Rod Motor Temp Anticipated Project stage: Other ML20127L8851985-06-13013 June 1985 Forwards Results of Engineering Evaluation of Design Changes Introduced in CRD & Orifice Assembly Bearings.Physical Comparison Testing of Original & Replacement Shim Motor Bearings Underway to Establish Operating/Design Margins Project stage: Other ML20127N6951985-06-14014 June 1985 Elaborates on Util Commitments to Listed Plant Activities, Including CRD Mechanism Temp Recording,Requalification, Surveillance & Preventative Maint,Backup Reactor Shutdown Procedure,Tendons & Pcrv Integrity & Electrical Sys Project stage: Other ML20209E8991985-06-25025 June 1985 Discusses Status of CRD & Orificing Assembly (Crdoa) Refurbishment Efforts.First 37 Crdoas Refurbished & Installed.Summary of Design Changes & Test Results Encl Project stage: Other ML20132C9481985-07-0101 July 1985 Evaluation of CRD Orifice Assembly Bearing Rept from Public Svc Co of Co Project stage: Other ML20132E6231985-07-0303 July 1985 Forwards Interim Tech Specs for Reactivity Control Sys.Tech Specs Will Provide Basis for Program to Assure CRD & Reserve Shutdown Sys Reliability.Specs Include Change to Criteria for Insertion of Reserve Shutdown Matl Project stage: Other ML20132C9391985-07-12012 July 1985 Forwards Eg&G 850701 Evaluation of CRD Orifice Assembly Bearing Rept from Public Svc Co of Co, Per Util 850613 Submittal.Installed Bearings Acceptable Replacements for Original Design.Review of 850607 Submittal Also Encl Project stage: Approval ML20134E8651985-07-17017 July 1985 Issue 1 to Procedure SR-TE-9-X, Inserted Rod Position Verification Project stage: Other ML20134E8601985-07-31031 July 1985 Forwards Issue 1 to Procedure SR-TE-9-X, Inserted Rod Position Verification, in Response to Concerns Discussed at 850221 Meeting & in Project stage: Meeting ML20138Q9221985-12-19019 December 1985 Informs of Inability to Meet 851230 Completion Date of High temp,300 F,Crd Mechanism Test & Preliminary Evaluation,Due to Difficulties,Including Orifice Valve on Mechanism.Final Rept Will Be Submitted by 860331 Project stage: Other ML20199D3411986-06-11011 June 1986 Forwards Evaluation of Util Response to 851003 Review of Performance Enhancement Program.Method Should Be Provided to Confirm Functional Acceptability of Equipment Prior to Return to Svc Project stage: Approval ML20206B3301987-04-0606 April 1987 Requests Fr Publication of Notice of Issuance of Amend 52 to License DPR-34,increasing Circular Speed High Steam Trip Setting Listed in Table 4.4-3 of Tech Specs Project stage: Approval ML20206J9331987-04-0606 April 1987 Safety Evaluation Supporting Amend 52 to License DPR-34 Project stage: Approval ML20206J8411987-04-0606 April 1987 Amend 52 to License DPR-34,increasing Circulator speed-high Steam Trip Setting Listed in Table 4.4-3 of Tech Specs Project stage: Other ML20206J7481987-04-0606 April 1987 Forwards Amend 52 to License DPR-34 & Safety Evaluation. Amend Increases Circulator speed-high Steam Trip Setting in Table 4.4-3 of Tech Specs Project stage: Approval 1985-03-12
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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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r
Fort St. Vrain #1 Technical Specifications
. Amendment Page 4.4-6 Specification LC0 4.4-1 TABLE 4.4-3 INSTRUMENT OPERATING REQUIREMENTS FOR PLANT PROTECTIVE SYSTEM, CIRCULATOR TRIP MINIMUM MINIMUM PERMISSIBLE TRIP OPERABLE DEGREE OF BYPASS N0. FUNCTIONAL UNIT SETTING CHANNELS REDUNDANCY CONDITIONS
- 1. Circulator Speed-Low 1910 rpm Below 2 (f) 1 Less than 30%
- (r) Normal as Rated Power Programmed by FW Flow 2a. Loop 1, Fixed Feedwater 20% of Rated 2 (f) 1 Less than 30% ,
Flow-Low (Both Full Load Rated Power Circulators) 2b. Loop 2, Fixed Feedwater 20% of Rated 2 (f) 1 Less than 30%
Flow-Low (Both Full Load Rated Power Circulators)
- 3. Loss of Circulator ->475 psid 2 (f) 1 None Bearing Water (r)
~.
4 Circulator Penetration -<810 psig 2 (f) 1 Hone Trouble (r)
- 5. Circulator Drain ->5 psid 2 (f) 1 None Malfunction (r)
.6. Circulator Speed-High -<11,700 rpm 2 (f) 1 None Steam (r)
- 7. Manual ----------- 1 0 None
- 8. Circulator Seal >-10"H 2 0, or 2 (f) 1 Opposite loop Malfunction (r) 580" hod 2 shutdown or circulator seal malfuncticn trip or other circulats in same loop
- 9. Circulator Speed- -<8,800 rpm 2(f) 1* None High Water L
- Minimum operable channels and minimum degree of redundancy must be maintained on at least one helium circulator per loop. If the minimum number of channels and the minimum degree of redundancy are not maintained as required, reactor power shall be reduced to 50% of rated thermal power within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
8405210262 840510 PDR ADOCK 05000267 p PDR
7 G
G ATTACHMENT 2 SIGNIFICANT HAZARDS CONSIDERATIONS
r: -
SIGNIFICANT HAZARDS CONSIDERATIONS I. EVALUATION Table 4.4-3 As stated in FSAR Section 7.1.2.b, " Circulator overspeed is an indication of speed control or other failure necessitating rapid shutdown of the circulator. The speed sensing system response and trip setting are chosen so that under the maximum overspeed situation possible (loss of restraining torque) the circulator will remain within design capabilities." FSAR Section A.1.13.5 identifies the maximum " credible" overspeed condition as 135% of rated, resulting from a rupture of the reheat steam pipe downstream of the circulator, combined with failures of both the control system and the overspeed trip system. Therefore, the circulator trip setting should be conservative with respect to this maximum credible overspeed condition.
The proposed increase in maximum trip setting, from 11,000 rpm (115% of rated) to 11,700 rpm (123% of rated), would still provide the automatic protective actions conservatively prior to the credible overspeed condition (135%) 11 designed. Due to the almost instantaneous overspeed reaction m. der postualted control or piping failures, the proposed increase would be insignificant from a system sensing and time response standpoint.
In considering the impact on the design capabilities of the circulators, the postulated maximum credible overspeed accident assumes control and trip system failures resulting in 135% rated speed with no affect on circulator components or efficiency.
This conclusion is verified by FSAR Section A.1.13.5, which references the circulator disc and blade testing program that required actual individual testing and inspection of each component at 140% of design speed prior to assembly. This section also identified the tested blade shedding speed as 170%
of design, which would constitute the maximum design capability
. of the circulators.
O
The only event which could result in a damaging circulator speed (2 170%) would be an instantaneous depressurization of the primary loop at full load simultaneous with speed control and high speed trip failures (FSAR Section 5.10.2.2). This accident, although considered extremely unlikely, assumes rotor or disc failures without damage to the primary closure or penetration liner. Therefore, only circulator operability would be affected. This accident evaluation further justifies the ability of the new trip setting (123%) to perform its design function of maintaining the circulator within design capabilities (170%), while avoiding unnecessary trips caused by normal plant transients.
II. CONCLUSION Based on the above evaluation, it is concluded that operation of Fort St. Vrain in accordance with the proposed changes will not (1) involve a significant increase in the probability or consequences of an accident previously evaluated, (2) create the possibility of a new or different kind of accident from any accident previously evaluated, or (3) involve a significant reduction in any margin of safety.
Therefore, these changes will not increase the risk to the health and safety of the public nor to they involve any significant hazards considerations.
E