ML19211A955
ML19211A955 | |
Person / Time | |
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Site: | Fort Saint Vrain |
Issue date: | 11/22/1979 |
From: | PUBLIC SERVICE CO. OF COLORADO |
To: | |
Shared Package | |
ML19211A954 | List: |
References | |
NUDOCS 7912210376 | |
Download: ML19211A955 (2) | |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997
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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 Category:TEST REPORT MONTHYEARML20114D6871992-09-0101 September 1992
[Table view]Tritium Leach Test on H-327 Graphite ML20064B2111989-11-0909 November 1989 Fort St Vrain Cycle 4 RT-500L Test Rept ML20245L5861989-07-31031 July 1989 CRD Partial Scram Test Results & Max Daily Temp Rept for Jul 1989 ML20246J2041989-05-0808 May 1989 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 51 for Period Ending 890505 ML20235N0611989-02-10010 February 1989 Interim Startup Rept 50 for Fort St Vrain Nuclear Generating Station,881106 - 890204.Informs That Reactor Did Not Operate Above 80% Power ML20154E9291988-08-0808 August 1988 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 48 for Period Ending 880808 ML20196E1591988-05-31031 May 1988 CRD Partial Scram Test Results & Max Daily Temp Rept ML20151D0021988-05-10010 May 1988 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 47 for Period Ending 880510 ML20148G9801988-03-21021 March 1988 CRD Partial Scram Test Results & Max Daily Temp for Feb 1988 ML20148A6391988-02-0909 February 1988 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 46 for Period Ending 880209 ML20196B7961988-01-31031 January 1988 CRD Partial Scram Test Results & Max Daily Temp Rept, 880117-31 ML20148G8301987-12-14014 December 1987 Metallurgical Analysis of Components from Helium Circulator C-2101 ML20237A9681987-12-11011 December 1987 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 45 for Period Ending 871111 ML20235G8571987-08-13013 August 1987 Fort St Vrain Initial Approach to Power (B-Series),Interim Rept 44 for Period Ending 870813 ML20236G3021987-07-30030 July 1987 CRD Partial Scram Test Results & Max Daily Temp Rept, 870703-30 ML20207T3391987-02-14014 February 1987 Fort St Vrain Initial Approach to Power (B-Series),Interim Rept 42,Rept for Period Ending 870214 ML20207D3361986-12-10010 December 1986 Fort St Vrain Initial Approach to Power (B Series):Interim Rept 41 ML20215K6991986-08-17017 August 1986 Fort St Vrain Initial Approach to Power (B-Series) Interim Rept 40,Rept for Period Ending Aug 1986 ML20204F1161986-07-31031 July 1986 CRD & Orifice Assembly Parameter Trending Test Program ML20207G8871986-07-11011 July 1986 Destructive Exam of Fort St Vrain Fuel Test Element FTE-2 ML20198D0681986-05-14014 May 1986 Final Rept - Fort St Vrain CRD & Orificing Assembly High Temp Functional Test ML20136D0401985-12-20020 December 1985 Fort St Vrain Initial Approach to Power (B-Series), Interim Rept 37,for Period of 850822-1120 ML20137L1141985-08-26026 August 1985 Test Rept for Analog Isolator P/N:1622-5 S/N:0001 ML20137L0971985-08-26026 August 1985 Test Rept for Analog Isolator P/N:1622-4 S/N:0004 ML20137L1871985-08-26026 August 1985 Test Rept for Analog Isolator P/N:1622-4 S/N:0003 ML20137L1631985-08-26026 August 1985 Test Rept for Analog Isolator P/N:1622-5 S/N:0002 ML20137L1441985-08-26026 August 1985 Test Rept for Singe Channel Analog Isolator P/N:993:34 S/N:0001 ML20135B4741985-08-21021 August 1985 Fort St Vrain Initial Approach to Power (B-Series), 36th Startup Rept for 850522-0821 ML20128F8301985-05-21021 May 1985 Fort St Vrain Initial Approach to Power (B-Series),Interim Rept 35,Rept for Period Ending 850521 ML20100E3541985-03-15015 March 1985 Fort St Vrain Initial Approach to Power (B Series), Interim Rept 34 for Period Ending 850220 ML20112H4731985-01-24024 January 1985 NDE of 62 Fuel & Reflector Elements from Fort St Vrain Core Segment 3 ML20101L5031984-12-12012 December 1984 Fort St Vrain Initial Approach to Power (B Series), Interim Rept 33 for Period Ending 841122 ML20098F6581984-08-20020 August 1984 Initial Approach to Power (B-Series) Startup Test Rept, for Period Ending 840820 ML20092K6261984-06-19019 June 1984 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Rept 31 for Period Ending 840522 ML20084R2711984-05-10010 May 1984 Moisture Monitor Injection Tests in Compliance W/Fort St Vrain Tech Spec Limiting Condition for Operation 4.9.2 ML20087M8931984-02-22022 February 1984 Initial Approach to Power Tests (B-Series), Interim Rept 30 for Period Ending 840222 ML20083P5551983-12-16016 December 1983 Test Rept:Thermal Properties of Facility Fuel Element 1-2415 ML20083B4981983-11-22022 November 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), for 830923-1122 ML20083P5351983-09-23023 September 1983 Test Rept:Tensile Properties of Facility Fuel Element 1-2415 ML20080J2381983-08-22022 August 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Rept 28 for Period 830623-0822 ML20024B0411983-05-22022 May 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Startup Rept 27 for 830223-0522 ML20073J1811983-04-0808 April 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Rept 26 for Period Ending 830222 ML20076H3961983-04-0404 April 1983 Visual Exam Results of Segment 2,Fort St Vrain Fuel Elements 1-2415,1-0172,2-2693,1-0108 & 5-0801 ML20073S3251983-02-22022 February 1983 Initial Approach to Power Tests (B-Series), Interim Rept 26 for Period Ending 830222 ML20028E7291983-01-11011 January 1983 Fort St Vrain Initial Approach to Power Tests (B-Series), Interim Rept 25 for 820923-1222 ML20023E0531982-10-21021 October 1982 Results of Pgx Graphite Surveillance,Fort St Vrain. ML20066A3811982-10-0707 October 1982 Initial Approach to Power Tests, Interim Rept 24 for Period Ending 820822 ML20064M7411982-09-20020 September 1982 Test Rept:Nondestructive Exam of Fsv Fuel Test Element FTE-1 ML20055B9861982-07-22022 July 1982 Initial Approach to Power Tests (B-Series),Interim Rept 23 for Period Ending 820522 A16764, Radiochemical Analysis of First Plateout Probe from Fort St Vrain High-Temp Gas-Cooled Reactor1982-06-30030 June 1982 Radiochemical Analysis of First Plateout Probe from Fort St Vrain High-Temp Gas-Cooled Reactor 1992-09-01 |
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THE FORT ST. VRAIN INITIAL APPROACH TO POWER TESTS (B-SERIES)
INTERIM REPORT 13 Report for Period Ending November 22, 1979 1637 123 7912210 3 76
Inr.erim Report 8 covering the 90 day period ending August 22, 1978, re-ported the completion of all tests up to 70% of plant load. Since the Nuclear Regulatory Commission did not release the plant for operation at power levels in excess of 70%, no further Initial Approach to Power Tests were performed during the 90 days ending Novecher 22, 1979.
The Fort S t. Vrain Nuclear Generating Station was accepted for commercial operation at 70% power by Public Service Company of Colorado on July 1,1979.
Future interim reports will report the results of any startup tests at power levels above 70%.
'GE FORT ST. VPE N INITIAL APPROACH TO POWER TESTS (B-SERIES)
INTERIM REPORT 13 Report for Period Ending November 22, 1979 s
9 1637 125
A Interim Report 8 covering the 90 day period ending August 22, 1978, re-ported the completion of all tests up to 70% of plant load. Since the Nuclear Regulatory Commission did not release the plant for operation at power levels in excess of 70%, no further Initial Approach to Power Tests were performed during the 90 days ending November 22, 1979.
The Fort St. Vrain Nuclear Generating Station was accepted for commercial operation at 70% power by Public Service Company of Colorado on July 1,1979.
Future interim reports will report the results of any startup tests at power levels above 70%.
1637 126