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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 ML20036A8241993-05-0707 May 1993 Proposed TS 4.3 Re Prestressed Concrete Reactor Vessel Water Leakage Protection 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 ML20034C7851990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-EP Q, Steam Leak or Inadvertent Lifting of Steam Relief Valve ML20034C7781990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-2, Abnormal Radioactive Gas Release from Plant ML20034C7831990-04-19019 April 1990 Issue 56 to Abnormal Operating Procedure AOP-N, Loss of Instrument Bus ML20034C7761990-04-19019 April 1990 Issue 55 to Abnormal Operating Procedure AOP D-1, Single Circulator Trip ML20034C7771990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-1, Abnormal Radioactive Liquid Waste from Plant ML20034C7841990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-P, Loss of DC Bus ML20034C7801990-04-19019 April 1990 Issue 59 to Abnormal Operating Procedure AOP-K-1, Environ Disturbances - Earthquake ML20034C7821990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20034C7791990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-3, High Activity in Plant 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 ML20034C7781990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-2, Abnormal Radioactive Gas Release from Plant ML20034C7851990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-EP Q, Steam Leak or Inadvertent Lifting of Steam Relief Valve ML20034C7841990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-P, Loss of DC Bus ML20034C7751990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-B, Reactor Scram ML20034C7771990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-1, Abnormal Radioactive Liquid Waste from Plant ML20034C7761990-04-19019 April 1990 Issue 55 to Abnormal Operating Procedure AOP D-1, Single Circulator Trip ML20034C7801990-04-19019 April 1990 Issue 59 to Abnormal Operating Procedure AOP-K-1, Environ Disturbances - Earthquake ML20034C7831990-04-19019 April 1990 Issue 56 to Abnormal Operating Procedure AOP-N, Loss of Instrument Bus ML20034C7791990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-3, High Activity in Plant ML20034C7821990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header 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 ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20154L8911988-03-31031 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 1997-06-17
[Table view] |
Text
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Pub llg FORT ST. VRAIN NUCLEAR GENERATING STATION age ;1: of 2 P
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$9FVlC9' Pusuc sem'ica COfWPANY OF COLORADO-h TITLE:
ABNORMAL RADIOACTIVE GAS RELEASE FROM PLANT RESPONSIBLE h.
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FOR 3"*"%.7L EFFECTIVE RE Sw--
PORC 8 7 8 APRl 81990 DATE 4-25 DCCF NUMBER (S) 90e\\QB -
P FT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRlOR TO USE l
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ABNORMAL RADIOACTIVE CAS REl_ EASE FROM Pl.AllT SYMPIOM-ACTION MATRIX-I l
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SYMPTOMS I
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IReactor IReactor
'lActivity-IAny Release in I l
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i IVentilation
-IVentilatlon IRIS-6314-1 &
.lSet Forth On Thel l
l IExhaust Moble IExhaust Part-IRIS-6314-2, IAuthorization I
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IGas Activity liculate/ lodine Il-OIC, 5-3 I Fo rm f or The 1
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IHigh IActivity High,'l IRelease Or I
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IRIS-7324-1, IRIS-73437-1, I
IRadiological I
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II-03A, 3-6, IRIS-73437-2, 1
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l 8 Ensure FV-6351 closed.
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I i Evacuate reactor building i XX l XX I
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A0P APP H Issue 57 Public FORT ST. VRAIN NUCLEAR GENERATING STATIOgage 1-of 3-
- SerVICO*
PUBLIC SERVICE COMPANY,OF COLORADO O
ABNORMAL-RADI0 ACTIVE GAS RELEASE FROM PLANT t
DISCUSSION OF SYMPTOMS SYMPTOMS
'1.1 Reactor Bui'iding Ventilation Exhaust Noble Gas Activity 4
High.
RIS-7324-1 I-03A, 3-6.
RIS-7324-2 I-03A,- 1-7.
This-is the primary indication of concentrations of mixed I
noble gas releases.
All-gas exhausted from'the Reactor q
Building; passes through the ventilation system and past 1
-the exhaust vent monitor.-
j 1.2-Reactor Building Ventilation Exhaust Particulate / Iodine
.i Activity High.
RIS-73437-1, RIS-73437-2, I-01C, 2-1, 4
This is the primary indication of concentrations of I-131 l
releases. All gas exhausted from-the Reactor Building
- j passes through the ventilation system and past.the exhaust 1
vent monitor.
'i
~1.3 Activity Monitors HioS RIS-6314-1 & -2, I-01C, 5-3.
These activity mon _itors detect concentrations of mixed noble gases at the-discharge of the gas waste-blowers.
i Upon detection of activity at the discharge of the' gas waste _ blowers, diversion valves in the gas waste blower suction line will divert the flow to the gas waste vacuum
-i tank. This action is necessary to control the release of radioactive gas to the environment.
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1.4 Any Release In Excess Of Linits Set Forth On The I
Authorization Form For The Release Of Radioactive Wastes.
Each planned discharge of rac'ioactive material must be specifically approved and docamented'on an authorization form (see Administrative Procedure P-3).
The' i
authorization may set specific limits on quantities and/or i
radiation levels. The discharge should be terminated if any of the stipulations of the authorization form are not met.
}
O l
FORM (D)372 22 3643
I AOPAPPH-2L Issue 57 i..
A Public' FORT ST. VRAIN NUCLEAR GENERATING-STA'ilON age 2 of 3--
p 107 Service
DISCUSSION OF OPERATOR ACTION OPERATOR ACTION 2.1 Ensure that flow to the gas waste blowers has been diverted to the gas waste vacuum tank.
When a Stack Monitor. or a Gas Waste Blower Monitor trips, the suction of the Gas Waste Blowers is automatically diverted to the Vacuum Tank because the_ inputs to the-Blowers have a potential for containing radioactive gases.
The operator serves as back up to the automatic action.
2.2 Ensure FV-6351 clo' sed.
I FV-6351' is used only for making authorized gas waste _
releases from the Gas Waste Surge Tanks. In the event of a Stack Monitor trip,-FV-6351 should trip closed automatically to prevent ~ compounding _the: release..-The operator acts as a backup in this case.
If a release is inadvertently being made in excess of the limits set forth.
on the authorization form for a gas waste release, the a
operator must manually terminate the release.
1 2.3.
Evacuate reactor building and sound radiological' alarm.
I In keeping with the concept of maintaining personnel I
exposure as low as reasonably achievable, personnel should-
,l evacuate the Reactor Building and personnel entering the I
Reactor Building to perform corrective or lifesaving i
action should don protective devices (Anti-C's,' Scott Air l
Pack, etc.) prior to re-entry.
9
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I FORM 101372 22 3643
li l
A0P APP H !
.t Issue 57-nPublic FORT ST. VRAIN NUCLEAR GENERATING STATiogage 3 of 3_
^
107 Service
f l
2.4 Direct operator to attempt to isolate / remedy radiation source.
l If.the activity'is coming from one of-the plant. systems,
. prompt operator' action can greatly reduce the extent of the problem. The following systems were_ identified as the-most likely and extensive sources of potential' leakage; s
however they are not the only possibilities._ The i
operator's knowledge of plant systems, conditions, and his-ingenuity in spotting indications of unusual conditions.
are important factors in-troubleshooting the situation and isolating _the source of activity. Experience has shown l-the buffer helium system to be a possible source of.High Activity..
a)
Check System 63, Radioactive Gas Waste, l
b)
Check System 23, Helium Purification'.-
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c)
Check System 11, PCRV-Auxiliary Piping.
4 d)
Check System 13, Fuel Handling Purge.-
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Check System 14, Fuel Storage Faci.lity, OV f)
Check System 21, Helium Circulator Auxiliaries, j
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2.5 Swap suction of breathing air compressors.
In the event of possible radioactive contamination.of l
breathing air system, swap suction to TSC per 50P 45-03.
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2,6 Ensure CAS reports personnel accountability.
Initiate search, if necessary.
This will insure that all personnel are safe and accounted-for or whether a search for missing persons needs to be started.
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v FORM (D)372 22 3643 i