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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
n..
,y A0P-H-3e
. (q Issue 57-OPublic.
FORT ST. VRAIN NUCLEAR GENERATING STATION Page;1-of 2.
$6rVlC9'
- PUBL8C SERVICE COMPANY OF COLORADO --
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O TITLE:
HIGH ACTIVITY IN THE PLANT-
"a*""*'*!' uALJ_
AUTHORIQ 7
BY PORC PORC 8'7 7 A3R 11 IWWW.
EFFECTIVEN-$-$D REVIEW -
DATE DCCF NUMBER (S)
@D-D14l j
a O
I L1 FT, ST. VRAIN
-i NON-CONTROLLED i
COPY a
VERIFY ISSUE STATUS l
WITH SITE DOCUMENT _
CONTROL CENTER PRIOR TO USE j
4 i
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PDR FORM (D1372 22 3642
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l AOP-H-3 l
Issue 57--
'Page 2 of 2
( ll-3 )
!I1Gil ACT IVI TV IN THE Pt AM SYMPIOM-ACT10N MATR1X I
1 SYMPIOMS.
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ACTIONS
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.I 1 OP[RATOR ACTION i
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If control i
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Sound the I
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local alarm in the fuel Storage Building would alert personnel.of a criticality accident during new.
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.AOPJAPP.H-3 Issue 57
' Public FORT ST. VRAIN NUCLEAR' GENERATING STATION "9'
service
DISCUSSION OF SYMPT 0MS SYMPTOMS l
1.1 Gas Waste Compressor Cooling Activity Hith'RIS-46212,
- l
'I-03A, 4-6, RIS-46211, 1-13C, 1-5.
RIS-46211 and RIS-46212 are in series on the discharge
piping of the-Gas Waste Compressor's cooling water, and monitor for cooling' jacket leaks which could allow contaminated-gases to enter the service: water system.
j l
-1.2 Area Monitor Activity High I-01C, 4-1.
Twenty monitors placed in various locations in-the Reactor, Turbine, and Service Building continuously,
'l monitor for radiation in the plant environment.
)
i 1
1.3_. Activity Detected Locally.
j i
It is possible that personnel could detect activity locally with:the use of the Continuous Air-Monitors (CAMS), portable instruments, or Health Physics surveys l;
before a level was reached that would alarm one or more of-the permane'ntly installed monitors.
l 1.4 Critically Alarm Fuel Storage Building.
A local alarm in=the Fuel Storage Building would alert
.i personnel of a criticality accident during new fuel
(
handling.
DISCUSSION OF OPERATOR ACTIONS ~
OPERATOR ACTIONS 2.1 Determine source of radiation.
i a)
Check System 63, Radioactive Gas Waste.
b)
Check System 23, Helium Purification, c)
Check System 11, PCRV Auxiliary Piping, d)
Check System 13, Fuel Handling Purge.
e)
Check System 14, Fuel Storage Building.
O FORM (ol372 22 341 1
x <
p'
- A0P APP H l Issue 57.
- 9' U
APublic FORT _ ST. VRAIN NUCLEAR GENERATING STATION
%F Service *-
rusuc sanwen COMPANY OF COLORADO p
4 i
A./
If the activity is coming from one of the plant systems, prompt operator action can greatly reduce. the extent of the problem. The above systems ware identified as the most likely and extensive sources' of potential leakage, l
but are not the only possible sources of activity.
2.2 Evacuate affected' area.
If control room, evacuate per l
AOP-R.
Sound the radiological alarm.
.l Personnel should^be evacuated from area of radiation:
exposure and directed to the Health Physics Access Area i
for contamination' checks to avoid the spread of contamination. Sound the plant Radiological Alarm under the_ conditions specified.in Administrative Procedure G-5, i
Personnel Emergency Response, t
2.3 _ Shutdown affected gas waste compressor ~and manually isolate the cooling water.
If a gas waste compressor. cooling jacket-develops a leak, it must be isolated to avoid' contaminating the service water system.
I p~
l 2.4 Notify Coritrol Room.
t
-Q The Control Room is the focal point of plant N
communications and control. Plant personnel are at the disposal of the Shift Supervisor to perform whatever tasks may be necessary to deal with the specific situation.
t However, personnel should not be needlessly exposed to radiation and should be directed away from areas of radiation expcsure if they are not needed.
l 2.5 Attemot to isolate / remedy radiation source.
l 2.6 Ensure CAS-reports personnel accountability.
Initiate search if necessary.
This will insure that all personnel are safe and accounted for or wnether a search for missing persons needs'to be started..
l
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. FORM (DW72 22 3643
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