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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] Category:TEST/INSPECTION/OPERATING PROCEDURES
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 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 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 ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class 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 ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20154M4361988-09-0909 September 1988 Rev a to EE-FP-0005, Evaluation of Cable Trays Outside of Congested Cable Area ML20154L8751988-05-26026 May 1988 Simulation Facility Program Plan ML20154L8911988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20150E3141988-03-18018 March 1988 Issue 1 to Procedure SR 5.4.1.3.8.abcd-R1, Steam Line Rupture Detection/Isolation Sys (Slrdis) Calibr & Testing for Panel I-93543 ML20150E2901987-12-31031 December 1987 Issue 5 to Procedure SR 5.3.4b1-A Loop I Shutdown Cooling Power Operated Valve Test ML20238E3541987-08-0707 August 1987 Rev a to EE-ISI-002, Condensate Line Erosion Insp Program ML20236N8681987-08-0505 August 1987 Exercise Manual Fort St Vrain Nuclear Generating Station Nrc/Fema Graded Exercise 870805 ML20235Y7861987-07-29029 July 1987 Issue 2 to MAP-4, Maint Dept Personnel Experience, Qualification & Training Requirements ML20237J6921987-06-0909 June 1987 Issue 6 to MQCIM-1, Maint QC Insp Program. Annotated Page to Rev 4 to Updated FSAR Encl ML20235Y7731987-05-25025 May 1987 Training Mgt Procedure Index ML20237J7151987-05-0101 May 1987 Issue 12 to Q-18, QA Monitoring & Audit Program ML20215H9731987-04-30030 April 1987 Revised Buckle Users Manual:Creep Collapse of Thin-Walled Circular Cylindrical Shells Subj to Radial Pressure & Thermal Gradients ML20215H6101987-04-10010 April 1987 Program Plan for Integrated Validation of NUREG-0737 Initiatives ML20215H6031987-04-10010 April 1987 SOAP-2,Issue 1 of Guidelines for Preparation of Emergency Procedures ML20215H5951987-04-10010 April 1987 Procedures Generation Package:Public Svc Co of Colorado Fort St Vrain Nuclear Generating Station ML20150E3041987-03-20020 March 1987 Issue 1 to Procedure SR 5.4.1.3.8.abcd-R2, Steam Line Rupture Detection/Isolation Sys (Slrdis) Calibr & Testing for Panel I-93544 ML20237J7231987-02-20020 February 1987 Issue 5 to QAAP-1, Planning & Scheduling Fort St Vrain QA Audits ML20212B3081987-02-15015 February 1987 Issue 7 to Procedure G-9, Controlled Work Procedures ML20210E3001987-02-0303 February 1987 Revised Administration Procedures Consisting of Issue 7 to G-3, Action Request-Preparation & Processing, Issue 21 to G-2, Fort St Vrain Procedure Sys & Issue 6 to G-6, Compliance w/10CFR21 Requirements ML20210A7571987-01-30030 January 1987 Fort St Vrain 1987 Power Ascension Plan ML20237J7421987-01-19019 January 1987 QA Audit QAA-502-87-01, Audit Plan - QA Program for Transport of Radioactive Matls ML20212B2851986-10-24024 October 1986 Issue 10 to Procedure Q-3, Design Control Sys ML20238E3461986-10-0202 October 1986 Rev C to EE-ISI-0001, Extraction Steam Lines & Turbine Vent & Drain Lines Erosion Insp Program 1997-06-17
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Text
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r Enclosure (3) to P- 20064 O
FORT ST. VRAIN INSERVICE INSPECTION AND TESTING PROPOSED TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS FOR THE
_ SECONDARY COOLANT SYSTEM
.P B 004 Osp f g3 Draft Rev. 2 March 25n 1980
Draft Rev.2 5.3-1 5.3 SECONDARY COOLANT SYSTEM - SURVEILLANCE REQUIREMENTS Applicability Applies to the surveillance of the secondary (steamJ coolant system including the steam generators and turbine plant.
Objective To ensure the core cooling capability of the components of the steam plant system.
i Specification SR 5.3.1 - Steam / Water Dump Systen, Surveillance The steam / water dump valves shall be tested individually every three months.
i The steam / water dump tank level indicators shall be c..ecked daily, and functionally tested every three months.
The steam / water dump tank level, pressure and temperature in-struments (including indicators, alarms, and interlocks - where applicable) shall be functionally tested and calibrated annually, or at the next scheduled plant shutdown if such surveillance has not been performed during the previous year.
Basis for Specification SR 5.3.1 The steam / water dump system is provided to minimize water inleakage into the core as a result of a steam generator tube rupture (FSAR Section 6.3) . Satisfactory operation of the dump valves,as is sufficiently demonstrated by testing every three months, will minimize core damage and primary coolant system pressure rise in the event of a steam generator tube l rupture.
l The dump valve test will be accomplished by closing the (normally locked open) block valve downstream of the dump valve l 1
Draft Rev.2 l 5.3-la .
to be tested. After~ operation of the dump valve, the block valve will again be locked open, returning the dump valve to service.
The specified frequency for instrumentation functional test and calibration is adequate to assure that the water level in the steam / water dump tank does not exceed the limits of LCO 4.3.3, and, in case of dump, to confirm that the proper superheater has been dumped, and to prevent venting and draining of the tank to the radioactive gaseous and liquid systems before the contents have been adequately cooled.
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I Draft Rev. 2 l
5.3-2 1 Specification SR 5.3.2 - Main and flot Reheat Steam Stop Check Valves, Surveillance The main steam and hot ;eheat steam stop check valves shall be full stroke '
- ted in accordance with specification SR 5.3.4 and partial stroke tested once per week.
Basis for Specification SR 5.3.2 The main steam stop check and hot reheat stop check valves will be partially stroked once a week during plant operation.
Full stroking tests are impractical because complete closure of any one valve would automatically shut down one or more circulators. Therefore, the valves will be stroked dur.ing power operation by means of special electrical circuitry in the hydraulic control system which limits closure to ten percent without interfering with emergency closure action called for by the plant protective system. This test will demonstrate that the valves are free to close when required, without causing severe pressure, temperature, flow, or power generation transients.
Specification SR 5.3.3 - Bypass and Pressure Relief Valves, Surveillance The main steam and hot reheat steam power operated (electromatic) pressure relief valves, and the six hot reheat i
steam bypass valves shall be tested once per year, or at the next scheduled plant shutdown if the' valves have not been tested during the previous year. The main steam bypass valves shall be tested in accordance with specification SR 5.3.4.
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Draft Rev. 2 5.3-3 Basis for Specification SR 5.3.3 The specified secondary (steam) coolant system bypass valves and pressure relief valves will be tested during plant shutdown -as follows: - -
a) The main steam and hot reheat steam power operated pressure relief valves will be tested by exercising the relief.
b) The six hot reheat steam bypass valves will be tested by exercising each valve to ensure freedom of movement.
c) The main steam bypass valves will be tested for operability ,
by cycling the valves.
The main steam bypass valves divert up to 77% steam flow (via desuperheaters) to the bypass flash tank on turbine trip or loop isolation, so that the steam is available for driving helium circulators, boiler feed pump turbines, etc. The main steam power operated relief valves divert the remaining steam flow to atmosphere.
The six hot reheat steam bypass valv's and the power operated pressure relief valve ensure a continuous steam flow path from the helium circulators for decay heat removal.
The tests required on the above valves will demonstrate that each valve will function properly. Test frequency is considered adequate for assuring valve operability at all times .
Specification SR 5.3.4 - Safe Shutdown Cooling valves, Surveillance Those valves that are pneumatically, hydraulically, or electrically operated, that are required for actuation of the
. Safe Shutdown Cooling mode of operation, shall be tested
Draft Rev. 2 5.1-3a annually, or at the next scheduled plant shutdown if these valves have not been tested during the previous year.
In addition, the above test shall include the normally closed check valves which are required to open for actuation of the Safe Shutdown Cooling mode of operation, when such testing 16 practical.
Basis for Specification SR 5.3.4 The Safe Shutdown Cooling mode of operation utilizes systems or portions of systems that are in use during normal plant operation. In many cases, those valves required to initiate Safe Shutdown Cooling are not called upon to function during normal operation of the plant, except to stand fully closed or open.
Testing of these valves will assure their operation if
, called upon to initiate the Safe Shutdown Cooling mode of operation.
During reactor operation, the instrumentation required to monitor and control the Safe-Shutdown mode of cooling is normally in use and any malfunction would be immediately brought to the attention of the operator. That instrumentation not normally in use is tested at intervals specified by other surveillance requirements in this Technical Specification.
Safe Shutdown Cooling, the systems or cortions of systems involved, are discussed in Sections 10.3.9 and 10.3.10 of the FSAR and are represented in FSAR Figure 10.3-4.
Valve testing will include, as applicable, full stroking each valve, or an observation that the valve disc travels l
from the valve nor~ mal operating position to the position required
a Draft Rev. 2 5.3-4 to perform the safety function, an observation that the remote position indicators accurately reflect actual valve position, and a measurement of the full stroke time for the hydraulically
~
~ actuated'~ automatic valves.
- Specification SR 5.3.5 - Hydraulic Power System Surveillance Requirements The pressure indicators and low pressure alarms on the hydraulic oil accumulators pressurizing gas and on the hydraulic power supply lines shall be functionally tested once every three months and calibrated once per year.
Basis for Specification SR 5.3.5 The hydraulic power system is a normally operating system.
Malfunctions in this system will normally be detected by failure of the hydraulic oil pumps or hydraulic oil accumulators to maintain a supply of hydraulic oil at or above 2500 psig. Functiona.
tests and calibrations of the pressure indicators and low pressure alarms on the above basis will assure the actuation of these alarms upon a malfunction of the hydraulic power system which may compromise the capability of operating critical valves.
- Specification SR 5.3.6 - Instrument Air System - Surveillance !
l Requirements I l
I The pressure indicators and low pressure alarms on the instrument air receiver tanks and headers shall be functionally tested monthly and calibrated annually.
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- NOT REVIEWED AS PART OF THIS SUBMITTAL.
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l Draft Rev.2 5.3-9 Specification SR 5.3.'9 - Safety valves 3 Surveillance The steam generator superheater and reheater safety valves and the steam / water dump tank safety valves shall be
. tested at least once every five years to verify their set point.
Basis for Specification SR 5.3.9 The safety valves protect the integrity of the steam generators, which are part of the. reactor coolant boundary, and of the dump tank, which may contain radioactive fluids. Testing the safety valve set points will assure that the pressure within the equipment remains within design limits.
When practical, testing of the safety valves will be
, scheduled during the surveillance interval so that testing of one (or more) safety valve (s) of similar type and operating conditions several times during the interval will provide additional confidence in safety valve reliability and adequate overpressure protection.
Specification SR 5.3.10 - Secondary Coolant System Instrumentation, Surveillance The secondary coolant reheat steam instrumentation used a) for control and indication of emergency condensate flow to the reheaters and reheater backpressure, in case of safe shutdown cooling, b) to automatically open the reheater discharge bypass on high pressure, and c) to monitor reheater discharge bypass temperature, reheater inlet temperature and strainer pressure drop, and circulator
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Draft Rev. 2
, 5.3-9a protective screen pressure drop, shall be functionally tested and calibrated annually, or at the next scheduled plant shutdown if such surveillance was not performed during the previous year.
Basis for Specification SR 5.3.10 The frequency specified for surveillance of the above instrumentation will assure that they perform their expected automatic actions, and that the operator will be provided with accurate information which he can use for safe shutdown cooling or to avoid abnormal operation of the steam generator reheaters, the circulator steam turbine or the reheater dis-charge bypass.
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